ENDFB6 LIBRARY, DUMMY TAPE HEADER 1.002000+3 1.996800+0 -1 0 0 1 128 1451 1 0.000000+0 0.000000+0 0 0 0 6 128 1451 2 1.000000+0 0.000000+0 0 0 10 6 128 1451 3 0.000000+0 0.000000+0 0 0 80 2 128 1451 4 1-H - 2 LANL,AWRE EVAL-NOV67 L.STEWART (LASL) A.HORSLEY (AWRE) 128 1451 5 LA-3271 (1968) DIST-JUN90 900221 128 1451 6 ----ENDF/B-VI MATERIAL 128 128 1451 7 -----INCIDENT NEUTRON DATA 128 1451 8 ------ENDF-6 FORMAT 128 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 128 1451 10 ACTIVATION I 128 1451 11 ****************************************************************** 128 1451 12 128 1451 13 ****************************************************************** 128 1451 14 128 1451 15 CONVERTED FOR ENDF/B-VI AT LOS ALAMOS NATIONAL LABORATORY. 128 1451 16 THE CROSS SECTIONS, ELASTIC MF4, AND PHOTON PRODUCTION 128 1451 17 DATA WERE LEFT UNCHANGED. MF4 AND MF5 FOR THE (N,2N) 128 1451 18 REACTION WERE REMOVED AND REPLACED BY AN MF6 USING AN 128 1451 19 ANALYTIC PHASE-SPACE REPRESENTATION. THIS IS CONSISTANT 128 1451 20 WITH THE ORIGINAL EVALUATION, BUT PROVIDES A MORE 128 1451 21 ACCURATE REPRESENTATION OF THE ENERGY-ANGLE CORRELATION 128 1451 22 OF (N,2N) NEUTRONS. 128 1451 23 128 1451 24 ****************************************************************** 128 1451 25 128 1451 26 MF=2 128 1451 27 NO RESONANCE PARAMETERS GIVEN 128 1451 28 128 1451 29 MF=3 128 1451 30 MT=1 128 1451 31 TOTAL CROSS SECTIONS. ALL DATA PLOTTED AND COMPARED UP TO 128 1451 32 1967 IN LA-3271. CHANGES INCORPORATED BELOW 1.5 MEV BUT 128 1451 33 EVALUATION DOES NOT AGREE WITH LOW-ENERGY EXPERIMENTS AT 128 1451 34 NBS (WHICH ARE PRELIMINARY) BUT AGREES AT HIGHER ENERGIES. 128 1451 35 THE DAVIS DATA SHOW A PECULIAR DROP OF A FEW PERCENT FROM 128 1451 36 3.5 TO 9 MEV BUT AGREE ABOVE AND BELOW THESE ENERGIES. 128 1451 37 128 1451 38 MT=2 128 1451 39 ELASTIC CROSS SECTIONS. DATA OBTAINED FROM INTEGRATING N-D 128 1451 40 AND P-D ANGULAR DISTRIBUTIONS. SINCE THE RADIATIVE 128 1451 41 CAPTURE IS IN MICROBARNS, THE ELASTIC IS ESSENTIALLY 128 1451 42 EQUAL TO THE TOTAL CROSS SECTION BELOW THE N,2N 128 1451 43 THRESHOLD AND THE TOTAL MINUS THE N,2N ABOVE THE 128 1451 44 THRESHOLD. CHECKS AND BALANCES WERE ALWAYS MADE. SEE 128 1451 45 LA-3271 FOR THE GRAPHICAL COMPARISONS. 128 1451 46 128 1451 47 MT=16 128 1451 48 N,2N CROSS SECTION. DATA TAKEN FROM HOLMBERG AND FROM 128 1451 49 CATRON. SEE LA-3271. NOTHING IS KNOWN ABOUT THE CROSS 128 1451 50 SECTION ABOVE 14 MEV. 128 1451 51 128 1451 52 MT=102 128 1451 53 RADIATIVE CAPTURE CROSS SECTION. THE THERMAL CROSS SECTION 128 1451 54 IS 506 MICROBARNS WHICH WAS EXTRAPOLATED AS 1/V UP TO 128 1451 55 1 KEV. CURVE WAS DRAWN ABOVE THIS ENERGY TO INCLUDE 128 1451 56 MEASUREMENTS ON THE INVERSE REACTION BY BOSCH. THE 128 1451 57 14 MEV VALUE IS A FACTOR OF 3 LOWER THAN CERINEO. 128 1451 58 SEE LA-3271 FOR GRAPHICAL RESULTS. 128 1451 59 128 1451 60 128 1451 61 MF=4 128 1451 62 MT=2 128 1451 63 ELASTIC ANGULAR DISTRIBUTIONS TAKEN FROM N-D AND P-D SCAT. 128 1451 64 AGREEMENT IS GOOD WITH VAN OERS ANALYSIS. SEE LA-3271. 128 1451 65 128 1451 66 MF=6 128 1451 67 MT=16 128 1451 68 ENERGY-ANGLE DISTRIBUTIONS REPRESENTED AS A 128 1451 69 3-BODY PHASE SPACE DISTRIBUTION. 128 1451 70 128 1451 71 MF= 8 AND 9 128 1451 72 128 1451 73 MT=102 DECAY INFORMATION ADDED FOR TRITIUM PRODUCTION 128 1451 74 128 1451 75 MF=12 AND MF=14 128 1451 76 128 1451 77 MT=102 128 1451 78 ASSUMED A SINGLE GAMMA EMITTED AT ALL ENERGIES. 128 1451 79 EMPLOYED THE LP = 2 FLAG TO CONSERVE ENERGY 128 1451 80 128 1451 81 FOR REFERENCES, SEE LA-3271. 128 1451 82 128 1451 83 128 1451 84 1 451 86 1 128 1451 85 3 102 35 0 128 1451 86 128 1 0 87 128 0 0 88 1.002000+3 1.996800+0 0 0 0 0 128 3102 89 6.257400+6 6.257400+6 0 0 2 94 128 3102 90 10 5 94 2 0 0 128 3102 91 1.000000-5 2.530000-2 1.000000-4 8.000000-3 2.530000-2 5.060000-4 128 3102 92 1.000000+2 8.000000-6 1.000000+3 2.500000-6 2.000000+3 1.760000-6 128 3102 93 3.000000+3 1.470000-6 4.000000+3 1.300000-6 5.000000+3 1.190000-6 128 3102 94 1.000000+4 1.000000-6 2.000000+4 1.030000-6 3.000000+4 1.150000-6 128 3102 95 4.000000+4 1.270000-6 5.000000+4 1.390000-6 6.000000+4 1.500000-6 128 3102 96 7.000000+4 1.610000-6 8.000000+4 1.720000-6 9.000000+4 1.820000-6 128 3102 97 1.000000+5 1.940000-6 1.200000+5 2.100000-6 1.400000+5 2.290000-6 128 3102 98 1.600000+5 2.450000-6 1.800000+5 2.600000-6 2.000000+5 2.740000-6 128 3102 99 2.250000+5 2.950000-6 2.500000+5 3.100000-6 2.750000+5 3.210000-6 128 3102 100 3.000000+5 3.330000-6 3.500000+5 3.600000-6 4.000000+5 3.830000-6 128 3102 101 4.500000+5 4.000000-6 5.000000+5 4.260000-6 5.500000+5 4.400000-6 128 3102 102 6.000000+5 4.640000-6 6.500000+5 4.750000-6 7.000000+5 4.990000-6 128 3102 103 7.500000+5 5.100000-6 8.000000+5 5.300000-6 8.500000+5 5.400000-6 128 3102 104 9.000000+5 5.550000-6 9.500000+5 5.650000-6 1.000000+6 5.860000-6 128 3102 105 1.200000+6 6.350000-6 1.500000+6 7.000000-6 1.750000+6 7.400000-6 128 3102 106 1.950000+6 7.700000-6 2.000000+6 7.820000-6 2.250000+6 8.100000-6 128 3102 107 2.450000+6 8.400000-6 2.500000+6 8.500000-6 2.750000+6 8.800000-6 128 3102 108 3.000000+6 9.000000-6 3.270000+6 9.100000-6 3.339000+6 9.200000-6 128 3102 109 3.400000+6 9.300000-6 3.500000+6 9.400000-6 3.750000+6 9.600000-6 128 3102 110 4.000000+6 9.700000-6 4.250000+6 9.900000-6 4.500000+6 1.000000-5 128 3102 111 5.000000+6 1.015000-5 5.500000+6 1.030000-5 5.600000+6 1.040000-5 128 3102 112 6.000000+6 1.050000-5 6.500000+6 1.060000-5 7.000000+6 1.075000-5 128 3102 113 7.250000+6 1.080000-5 7.500000+6 1.080000-5 7.850000+6 1.075000-5 128 3102 114 8.000000+6 1.070000-5 8.500000+6 1.065000-5 9.000000+6 1.060000-5 128 3102 115 9.500000+6 1.045000-5 9.700000+6 1.035000-5 1.000000+7 1.030000-5 128 3102 116 1.050000+7 1.025000-5 1.100000+7 1.020000-5 1.150000+7 1.010000-5 128 3102 117 1.175000+7 1.000000-5 1.200000+7 1.000000-5 1.217000+7 1.000000-5 128 3102 118 1.225000+7 9.900000-6 1.250000+7 9.900000-6 1.300000+7 9.700000-6 128 3102 119 1.350000+7 9.600000-6 1.400000+7 9.500000-6 1.410000+7 9.400000-6 128 3102 120 1.450000+7 9.300000-6 1.500000+7 9.200000-6 1.600000+7 9.000000-6 128 3102 121 1.700000+7 8.700000-6 1.800000+7 8.500000-6 1.900000+7 8.200000-6 128 3102 122 2.000000+7 8.100000-6 0.000000+0 0.000000+0 0.000000+0 0.000000+0 128 3102 123 128 3 0 124 128 0 0 125 0 0 0 126 3.007000+3 6.955732+0 -1 0 0 1 328 1451 1 0.000000+0 0.000000+0 0 0 0 6 328 1451 2 1.000000+0 0.000000+0 0 0 10 6 328 1451 3 0.000000+0 0.000000+0 0 0 270 3 328 1451 4 3-LI- 7 LANL EVAL-AUG88 P.G.YOUNG 328 1451 5 DIST-JAN90 891221 328 1451 6 ----ENDF/B-VI MATERIAL 328 328 1451 7 -----INCIDENT NEUTRON DATA 328 1451 8 ------ENDF-6 FORMAT 328 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 328 1451 10 ACTIVATION I 328 1451 11 ****************************************************************** 328 1451 12 FILE INFORMATION 328 1451 13 *********** SUMMARY ******************************************** 328 1451 14 328 1451 15 PRELIMINARY EVALUATION FOR ENDF/B-VI 328 1451 16 328 1451 17 BASED ON AN UPDATE OF THE VARIANCE-COVARIANCE ANALYSIS PERFORMED 328 1451 18 FOR ENDF/B-V.2 (YO81). INCLUDES NEW (N,NT) DATA THROUGH 1/1/88 328 1451 19 (LI83, MA83, SM84, MA86, TA84, GO85, CH85, SW85, QA86), AS WELL 328 1451 20 AS NEW ELASTIC AND INELASTIC DATA (CH85, SH84, AL82, DR86, 328 1451 21 SC87, DE87). SIMILAR TECHNIQUES TO YO82 WERE USED EXCEPT 328 1451 22 CROSS CORRELATIONS AMONG (N,NT) MEASUREMENTS WERE INCLUDED. 328 1451 23 IN ADDITION, A SEPARATE COVARIANCE ANALYSIS WAS PERFORMED FOR 328 1451 24 THE (N,N2) DISCRETE INELASTIC CROSS SECTION TO THE 4.63-MEV 328 1451 25 STATE OF LI7. PRIMARY REFERENCE IS YO88. 328 1451 26 THE THERMAL NEUTRON DATA WERE UPDATED USING THE MU81 COMPILATION. 328 1451 27 328 1451 28 *********** GENERAL DESCRIPTION ********************************* 328 1451 29 328 1451 30 INDEPENDENT V-C ANALYSIS FOR THE FOLLOWING FOUR REACTIONS 328 1451 31 WAS PERFORMED USING THE GLUCS CODE SYSTEM (HE80). 328 1451 32 (1) TOTAL X/S (MT1) 328 1451 33 (2) ELASTIC + (N,NPRIME) X/S TO 1ST LEVEL (MT2+MT51) 328 1451 34 (3) (N,NT) X/S (SUM OF MT52 THRU MT82) 328 1451 35 (4) (N,2N)+(N,2ND)+(N,3NP)+(N,D) (MT16+MT24+MT25+MT104) 328 1451 36 VARIANCES AND COVARIANCES FROM THE GLUCS ANALYSIS WERE THEN AD- 328 1451 37 JUSTED WITH THE ALVIN CODE (HA75) UNDER THE CONSTRAINT THAT 328 1451 38 REACTIONS (2)-(4) SUM TO REACTION (1). MOST CROSS SECTIONS 328 1451 39 AND COVARIANCES IN MF=3 AND 33 ARE BASED ON THESE RESULTS. 328 1451 40 A SEPARATE GLUCS ANALYSIS WAS PERFORMED OF MT51 X/S DATA AND 328 1451 41 THEN SUBTRACTED FROM REACTION (2) TO OBTAIN MT2. TO SEPARATE 328 1451 42 COMPONENT MTS FROM REACTION (4), MT104 FROM ENDF/B-V.1 WAS 328 1451 43 ADOPTED, AND AD HOC CURVES WERE DRAWN FOR MT16+MT24 AND MT25 328 1451 44 USING THE MEAGER EXP DATA. MT16 AND MT24 WERE THEN SEPARATED 328 1451 45 USING STATISTICAL THEORY CALCULATIONS. 328 1451 46 COVARIANCE MATRICES WERE DEVELOPED FOR EACH EXPERIMENT. IN 328 1451 47 MOST CASES STANDARD DEVIATIONS WERE AVAILABLE BUT IT WAS USUALLY 328 1451 48 NECESSARY TO MAKE GENERIC ASSUMPTIONS FOR THE ERROR CORRELATIONS 328 1451 49 ACCORDING TO THE TYPE OF MEASUREMENT. EXPERIMENTAL DATA INCLUDED 328 1451 50 IN THE ANALYSIS ARE REFERENCED BELOW. CROSS CORRELATIONS 328 1451 51 BETWEEN DIFFERENT TRITIUM-PROD.EXPERIMENTS DUE TO STANDARDS 328 1451 52 AND TRITIUM HALF LIFE WERE INCLUDED IN V-C ANALYSIS. 328 1451 53 328 1451 54 *********** MF=2 RESONANCE PARAMETERS *************************** 328 1451 55 328 1451 56 MT=151 SCATTERING RADIUS ONLY. 328 1451 57 328 1451 58 *********** MF=3 SMOOTH NEUTRON CROSS SECTIONS ****************** 328 1451 59 328 1451 60 MT= 1 TOTAL CROSS SECTION. ENDF/B-V.1 ADOPTED BELOW 0.1 MEV 328 1451 61 EXCEPT THE THERMAL DATA OF MU81 WAS USED AND THE ELAST. 328 1451 62 DATA OF AL82 WAS MATCHED. V-C ANALYSIS ABOVE 0.1 328 1451 63 MEV BASED ON ME70, GO71, HA78, FO71, KA57, BR58, PE60, 328 1451 64 CO52, LA79, AND HI68. ERRORS DOUBLED NEAR 260-KEV 328 1451 65 RESONANCE FOR HI68, ME70 DATA. 328 1451 66 MT= 2 ELASTIC CROSS SECTION. V-C ANALYSIS USED DATA OF TH56, 328 1451 67 WI56, KN68, BA63A, HO68, LI80, CO67, WO62, RE66, AR64, 328 1451 68 HY68, LA61, KN81, KN79, HO79, LA64, CH85, SH84, AND 328 1451 69 DR86. THE ERRORS IN THE V-C ANALYSIS WERE TRIPLED NEAR 328 1451 70 260-KEV RESONANCE FOR LA61, LA64 DATA. OPTICAL MODEL 328 1451 71 ANALYSIS OF HO79 DATA USED TO CALCULATE X/S ABOVE 328 1451 72 14 MEV FOR V-C ANALYSIS. THERMAL CROSS SECTION OF MU81 328 1451 73 USED, AND EVALUATION MATCHED TO AL82 DATA BELOW 0.1 MEV. 328 1451 74 MT= 4 (N,NPRIME)GAMMA + (N,NPRIME)ALPHA-T. SUM OF MT=51-82. 328 1451 75 MT= 16 (N,2N) CROSS SECTION. V-C ANALYSIS OF MT16+MT24 USED 328 1451 76 DATA OF CH85, AS58, MC61, MA69. SEPARATION OF MT16 AND 328 1451 77 MT24 FOLLOWS THE RATIO OF THE ENDF/B-V.1 DATA. 328 1451 78 MT= 24 (N,2N)ALPHA-D CROSS SECTION. SEE COMMENT FOR MT16. 328 1451 79 MT= 25 (N,3N)ALPHA-P CROSS SECTION. SMOOTH CURVE DRAWN ABOVE 14 328 1451 80 MEV SO AS TO APPROXIMATELY AGREE WITH MA69, KO71 DATA. 328 1451 81 MT= 51 (N,NPRIME)GAMMA CROSS SECTION. SEPARATE V-C ANALYSIS 328 1451 82 USED DATA OF PR72, OL80, SM76, DI74, MO78, FR55, KN81, 328 1451 83 BE60, BA53, CH61, KN68, GL63, HO68, BA63A. ERRORS 328 1451 84 DOUBLED ON FR55, BE60, AND TRIPLED ON CH61. 328 1451 85 MT= 56 (N,NPRIME)ALPHA-T CROSS SECTION. SEPARATE V-C ANALYSIS 328 1451 86 PERFORMED USING DATA OF CH85, DR87, SC87, DE87, RE66, 328 1451 87 AR64, HY68, WO62, CO67, BI77, HO79, BA79, BA63, LI80, 328 1451 88 HO68, RO62 AND YO65. 328 1451 89 MT=52-82 (N,NPRIME)ALPHA-T CROSS SECTION. EXCEPT FOR MT56, 328 1451 90 EXCITATION ENERGY BINS WERE CONSTRUCTED SUCH THAT CALCU- 328 1451 91 LATED NEUTRON EMISSION SPECTRA AGREE WITH THE MEASURE- 328 1451 92 MENTS BY LI80 AT 5.96, 9.83, AND 14.1 MEV INCIDENT ENER- 328 1451 93 GY. INTERPOLATION OF CROSS SECTIONS BETWEEN ENERGIES 328 1451 94 BASED ON LINEAR INTERPOLATION OF COMPUTED CM EMISSION 328 1451 95 SPECTRA, SUITABLY CONTRACTED OR EXPANDED TO CONSERVE 328 1451 96 ENERGY. ABOVE 14.1 MEV, THE EXP EMISSION SHAPE WAS USED 328 1451 97 TO INFER THE X/S, WITH THE SHAPES AGAIN SUITABLY EX- 328 1451 98 PANDED TO CONSERVE ENERGY. 328 1451 99 AT ALL INCIDENT ENERGIES, THE SUM OF MT=52-82 WAS 328 1451 100 CONSTRAINED TO EQUAL THE (N,NT) CROSS SECTION FROM THE 328 1451 101 VARIANCE-COVARIANCE ANALYSIS. 328 1451 102 MT=102 (N,GAMMA) CROSS SECTION. SHAPE FROM ENDF/B-V.1 EXCEPT 328 1451 103 DATA RAISED ABOVE 10 EV TO AGREE WITH EXP.DATA (IM59). 328 1451 104 THERMAL CROSS SECTION OF MU81 USED. 328 1451 105 MT=104 (N,D) CROSS SECTION. ADOPTED FROM ENDF/B-V.1. DATA 328 1451 106 AGREE APPROXIMATELY WITH EXPS OF BA53, BA63B, LI73, 328 1451 107 AND DISAGREE WITH MI61. 328 1451 108 328 1451 109 *********** MF=4 NEUTRON ANGULAR DISTRIBUTIONS ****************** 328 1451 110 328 1451 111 MT= 2 LEGENDRE COEFFICIENTS OBTAINED BY DRAWING SMOOTH CURVE 328 1451 112 THROUGH FITTED COEFFICIENTS FROM MEASUREMENTS LISTED 328 1451 113 UNDER MF3/MT2. DATA OF LA61, KN68, KN79, KN81, HO79, 328 1451 114 EMPHASIZED. OPTICAL MODEL CALCULATIONS USED ABOVE 14 MEV. 328 1451 115 MT= 16 TABULATED DISTRIBUTION OBTAINED BY INTEGRATING THREE- 328 1451 116 BODY PHASE SPACE CALCULATION OVER SECONDARY ENERGY. 328 1451 117 MT= 24 TABULATED DISTRIBUTION OBTAINED BY INTEGRATING FOUR- 328 1451 118 BODY PHASE SPACE CALCULATION OVER SECONDARY ENERGY. 328 1451 119 MT= 25 TABULATED DISTRIBUTION OBTAINED BY INTEGRATING FIVE- 328 1451 120 BODY PHASE SPACE CALCULATION OVER SECONDARY ENERGY. 328 1451 121 MT= 51 LEGENDRE COEFFICIENTS OBTAINED FROM R-MATRIX ANALYSIS 328 1451 122 OF KN81 BELOW 6 MEV, JOINED SMOOTHLY TO DWBA CALCULATION 328 1451 123 ABOVE 8 MEV USING DWUCK CODE AND OPTICAL PARAMETERS FROM 328 1451 124 MT=2 ANALYSIS. SOME USE ALSO MADE OF LI7(P,PPRIME) DATA. 328 1451 125 MT=52-71 LEGENDRE COEFFICIENTS OBTAINED FROM ANALYSIS OF LI80 328 1451 126 EXPERIMENT DESCRIBED IN MF3 ABOVE (EXCEPT MT56). COEF- 328 1451 127 FICIENTS FOR MT=56 OBTAINED BY DRAWING SMOOTH CURVES 328 1451 128 THROUGH FITTED VALUES FROM EXPERIMENTS LISTED ABOVE 328 1451 129 UNDER MF3/MT56, ESPECIALLY HO68 AND HO79. 328 1451 130 MT=72,82 ISOTROPY ASSUMED. 328 1451 131 328 1451 132 *********** MF=5 NEUTRON ENERGY DISTRIBUTIONS ******************* 328 1451 133 328 1451 134 MT= 16 TABULATED DISTRIBUTION OBTAINED BY INTEGRATING THREE- 328 1451 135 BODY PHASE SPACE CALCULATION OVER SECONDARY ANGLE. 328 1451 136 MT= 24 TABULATED DISTRIBUTION OBTAINED BY INTEGRATING FOUR- 328 1451 137 BODY PHASE SPACE CALCULATION OVER SECONDARY ANGLE. 328 1451 138 MT= 25 TABULATED DISTRIBUTION OBTAINED BY INTEGRATING FIVE- 328 1451 139 BODY PHASE SPACE CALCULATION OVER SECONDARY ANGLE. 328 1451 140 328 1451 141 *********** MF=12 PHOTON MULTIPLICITIES ************************* 328 1451 142 328 1451 143 MT= 51 MULTIPLICITY IS 1.0 EVERYWHERE SINCE FIRST LEVEL IN 328 1451 144 LI7 IS ONLY KNOWN PHOTON EMITTER. 328 1451 145 MT=102 ADOPTED DIRECTLY FROM ENDF/B-V.1. DUE TO THE ABSENCE 328 1451 146 OF DATA, THE TRANSITIONS ARE SIMPLY REASONABLE GUESSES. 328 1451 147 328 1451 148 *********** MF=14 PHOTON ANGULAR DISTRIBUTIONS ****************** 328 1451 149 328 1451 150 MT= 51 ISOTROPY ASSUMED AT ALL ENERGIES. 328 1451 151 MT=102 ISOTROPY ASSUMED FOR ALL GAMMAS AT ALL ENERGIES. 328 1451 152 328 1451 153 *********** MF=33 NEUTRON CROSS SECTION COVARIANCES ************* 328 1451 154 328 1451 155 MT= 1 BELOW 100 KEV, DERIVED FROM MT2 + MT102. ABOVE 100 328 1451 156 KEV, TAKEN DIRECTLY FROM GLUCS-ALVIN ANALYSIS. 328 1451 157 MT= 2 BELOW 100 KEV, 5PC CORRELATED ERROR ASSUMED. ABOVE 100 328 1451 158 KEV, DERIVED FROM MT1-MT4-MT851(MT16+MT24 LUMP), WHICH 328 1451 159 IS THE GLUCS-ALVIN ANALYSIS RESULT. 328 1451 160 MT= 4 FROM GLUCS-ALVIN ANALYSIS (MT51 MATRIX SUBTRACTED FROM 328 1451 161 REACTION 3 (ABOVE) COVARIANCE MATRIX. 328 1451 162 MT= 16 LUMP INDICATOR ONLY. 328 1451 163 MT= 24 LUMP INDICATOR ONLY. 328 1451 164 MT= 25 AD HOC ESTIMATE. 328 1451 165 MT=51-82 LUMP INDICATORS ONLY. 328 1451 166 MT=102 AD HOC ESTIMATE BASED ON EXPERIMENTAL SPREAD AND ERROR 328 1451 167 BELOW 1 MEV. 328 1451 168 MT=104 AD HOC ESTIMATE BASED ON EXPERIMENTAL ERRORS. 328 1451 169 MT=851 LUMP OF MT16 + MT24 ERRORS, AS DETERMINED IN GLUCS-ALVIN 328 1451 170 ANALYSIS. 328 1451 171 MT=852 SINGLE LUMP OF MT=51 ERROR. DETERMINED IN INDEPENDENT 328 1451 172 GLUCS ANALYSIS OF MT51 EXPERIMENTAL DATA (SEE ABOVE). 328 1451 173 MT=853 LUMP OF MT=52-55 ERRORS. DETERMINED IN SIMULTANEOUS 328 1451 174 ANALYSIS USING ALVIN TO CONSTRAIN (ADJUST) THE PARTIAL 328 1451 175 REACTION COVARIANCES FOR MT=853-859 TO BE CONSISTENT 328 1451 176 WITH THE TOTAL (N,NT) COVARIANCE (REACTION 3 ABOVE) FROM 328 1451 177 THE GLUCS-ALVIN ANALYSIS. INPUT COVARIANCES PRIOR TO 328 1451 178 THE ADJUSTMENT WERE ESTIMATED FROM EXPERIMENTAL DATA 328 1451 179 DESCRIBED UNDER MF=3 ABOVE. COMBINED VARIANCES FOR 328 1451 180 MT852-859 CONSTRAINED TO EQUAL MT4 VARIANCES, I.E., 328 1451 181 CONSISTENT WITH THOSE FROM THE (N,NT) V-C ANALYSIS. 328 1451 182 MT=854 SINGLE LUMP OF MT=56 DETERMINED FROM SCATTER AND ERRORS 328 1451 183 OF EXPERIMENTAL DATA (SEE MF=3 DESCRIPTION). 328 1451 184 MT=855 LUMP OF MT=57-61 DETERMINED AS DESCRIBED UNDER MT-853. 328 1451 185 MT=856 LUMP OF MT=62-66 DETERMINED AS DESCRIBED UNDER MT-853. 328 1451 186 MT=857 LUMP OF MT=67-71 DETERMINED AS DESCRIBED UNDER MT-853. 328 1451 187 MT=858 LUMP OF MT=72-76 DETERMINED AS DESCRIBED UNDER MT-853. 328 1451 188 MT=859 LUMP OF MT=77-82 DETERMINED AS DESCRIBED UNDER MT-853. 328 1451 189 ***NOTE. THE PROCEDURE USED TO DETERMINE MT=852-859 HAS THE 328 1451 190 ***RESULT THAT THESE MATRICES SUM ONLY APPROXIMATELY TO MT=4. 328 1451 191 ***THEREFORE, IT IS RECOMMENDED THAT MT=852-859 BE USED ONLY FOR 328 1451 192 ***CALCULATING NEUTRON EMISSION SPECTRUM UNCERTAINTIES AND THAT 328 1451 193 ***MT=1,2,4,25,102,104,851 BE USED FOR CALCULATING CROSS SECTION 328 1451 194 ***UNCERTAINTIES. 328 1451 195 328 1451 196 *********** REFERENCES ****************************************** 328 1451 197 328 1451 198 AL82 V.ALFIMENKOV ET AL., JADERNAJA FIZIKA 35,542(1982). 328 1451 199 AR64 A.H.ARMSTRONG ET AL, NUCL.PHYS.52, 505(1964) 328 1451 200 AS58 V.J.ASHBY ET AL, UCRL-5239 (1958) 328 1451 201 BA53 M.E.BATTAT, F.L.RIBE, PHYS.REV.89, 80(1953) 328 1451 202 BA63A R.BATCHELOR, J.H.TOWLE, NUCL.PHYS.47, 385(1963) 328 1451 203 BA63B J.F.BARRY, J.NUCL.ENER.A/B17, 273(1963) 328 1451 204 BA79 M.BABA ET AL., CONF.NEUT.CROSS SECT.TECH., KNOXVILLE,1979 328 1451 205 BE60 J.BENVENISTE ET AL, UCRL-6074 (1960) 328 1451 206 BI77 N.S.BIRJUKOV ET AL., A.E. 43, 176(1977). 328 1451 207 BR58 A.BRATENAHL ET AL, PHYS.REV. 110,927 (1958) 328 1451 208 BR63 F.BROWN ET AL, J.NUCL.ENER.A/B17, 137(1963) 328 1451 209 CH61 D.M.CHITTENDEN, A-ARK-61, 1(1961) 328 1451 210 CH85 S.CHIBA ET AL., J.NUC.SCI.& TECH. 22,771(1985). 328 1451 211 CO52 J.H.COON ET AL, PHYS.REV. 88,562 (1952) 328 1451 212 CO67 J.A.COOKSON ET AL, NUCL.PHYS.A91, 273(1967) 328 1451 213 DE87 E.DEKEMPENEER ET AL., NSE 97,353(1987). 328 1451 214 DI74 J.K.DICKENS ET AL, ORNL-TM-4538 (1974) 328 1451 215 DR86 M.DROSG ET AL., RAD.EFFECTS 92,145(1986). 328 1451 216 FO71 D.G.FOSTER,JR., D.W.GLASGOW, PHYS.REV. C3,576 (1971) 328 1451 217 FR55 J.M.FREEMAN ET AL, PHIL.MAG.46, 17(1955) 328 1451 218 GL63 N.P.GLAZKOV, ATOMNAYA ENERGIYA 15, 416(1963) 328 1451 219 GO71 C.A.GOULDING ET AL, COO-3058-1 (1971) 328 1451 220 GO85 E.GOLDBERG ET AL., NSE 91,173(1985). 328 1451 221 HA75 D.R.HARRIS ET AL, LA-5987 (1975) 328 1451 222 HE80 D.M.HETRICK, C.Y.FU, ORNL/TM-7341 (1980) 328 1451 223 HI68 C.T.HIBDON, F.P.MOORING, CONF.NEUT.X/S.TECH,WASH(1968)P159 328 1451 224 HA78 J.A.HARVEY ET AL, DOE/NDC-12/U (1978)P229 328 1451 225 HO68 J.C.HOPKINS ET AL, NUCL.PHYS.107, 139(1968) 328 1451 226 HO79 H.H.HOGUE ET AL, NUCL.SCI.ENG.69, 22(1979) 328 1451 227 HY68 M.HYAKUTAKE ET AL, EANDC(J)-10 (1968)P22 328 1451 228 IM59 W.IMHOF ET AL., PHYS.REV.114,1037(1959). 328 1451 229 KA57 L.N.KATSAUROV ET AL, ATOM.ENER.SUPPL.5, 90(1957) 328 1451 230 KN68 H.-H.KNITTER, M.COPPOLA, CONF.NEUT.X/S.TECH,WASH(1968)P827 328 1451 231 KN79 H.D.KNOX ET AL, NUCL.SCI.ENG.69, 223(1979) 328 1451 232 KN81 H.D.KNOX, R.O.LANE, NUCL.PHYS.A359, 131(1981) 328 1451 233 KO71 K.F.KORAL ET AL, NUCL.PHYS.A175, 156(1971) 328 1451 234 LA61 R.O.LANE ET AL, ANN.PHYSICS 12, 135(1961) 328 1451 235 LA64 R.O.LANE ET AL, PHYS.REV.136, B1710(1964) 328 1451 236 LA79 G.P.LAMAZE ET AL, BULL.AM.PHYS.SOC.24, 862(1979) 328 1451 237 LI73 R.H.LINDSAY ET AL, NUCL.PHYS.A199, 513(1973) 328 1451 238 LI80 P.W.LISOWSKI ET AL, LA-8342 (1980) 328 1451 239 LI81 H.LISKIEN, A.PAULSEN, ANNALS NUCL.ENER.8, 423(1981) 328 1451 240 MA69 D.S.MATHER, L.F.PAIN, AWRE-O-47/69 (1969) 328 1451 241 MA83 H.MAEKAWA ET AL., JAERI-M-83-196 (1983). 328 1451 242 MA86 H.MAEKAWA ET AL., PERSONAL COMMUNICATION (1986). 328 1451 243 MC61 M.H.MCTAGGART, H.GOODFELLOW (AWRE), PERSONAL COMM.TO , 328 1451 244 R.J.HOWERTON (1961) 328 1451 245 ME70 J.W.MEADOWS, J.F.WHALEN, NUCL.SCI.ENG. 41,351 (1970) 328 1451 246 MI61 M.MIKHAILINA ET AL, SOV.PROG.NEUT.PHYS. (1961)P185 328 1451 247 MO78 G.L.MORGAN, ORNL/TM-6247 (1978) 328 1451 248 MU81 S.F.MUGHABGHAB ET AL., NEUTRON RES.PARAMETERS AND 328 1451 249 THERMAL CROSS SECT., ACADEMIC PRESS (1981) V1. 328 1451 250 OL80 D.K.OLSEN ET AL, NUCL.SCI.ENG.74, 219(1980) 328 1451 251 OS61 A.R.OSBORN, H.W.WILSON, AWRE-NR/C-1/61 (1961) 328 1451 252 PE60 J.M.PETERSON ET AL, PHYS.REV. 120,521 (1960) 328 1451 253 PR72 G.PRESSER, R.BASS, NUCL.PHYS.A182, 321(1972) 328 1451 254 QA86 S.M.QAIM, R.WOLFLE, NSE 96,52(1986). 328 1451 255 RE66 V.REGIS ET AL, J.PHYSIQUE SUPPL.C1-84 (1966) 328 1451 256 RO62 L.ROSEN, L.STEWART, PHYS.REV.126, 1150(1962) 328 1451 257 SC87 D.SCHMIDT ET AL., NSE 96,159(1987). 328 1451 258 SH84 G.SHEN ET AL.,NSE 86,184(1984). 328 1451 259 SM76 D.L.SMITH, NUCL.SCI.ENG.61, 540(1976) 328 1451 260 SM81 D.L.SMITH ET AL, NUCL.SCI.ENG.78, 359(1981) 328 1451 261 SM84 D.L.SMITH ET AL., ANL/NDM-87 (1984). 328 1451 262 SW79 M.T.SWINHOE, C.A.UTTLEY, NBS SPEC.PUB.594, 246(1980) 328 1451 263 SW85 M.T.SWINHOE, C.A.UTTLEY, NSE 89,261(1985). 328 1451 264 TA84 A.TAKAHASHI ET AL., SYMP.FUSION TECH.,VARESE,ITALY (1984) 328 1451 265 P.1325. 328 1451 266 TH56 R.G.THOMAS ET AL, PHYS.REV.101, 759(1956) 328 1451 267 WI56 H.B.WILLARD ET AL, PHYS.REV.101, 765(1956) 328 1451 268 WO62 C.WONG ET AL, NUCL.PHYS.33, 680(1962) 328 1451 269 WY58 M.E.WYMAN, M.M.THORPE, LA-2235 (1958) 328 1451 270 YO65 A.YOSHIMURA ET AL (KYUSHU U.), PERSONAL COMM. NNDC (1965) 328 1451 271 YO81 P.G.YOUNG, TRANS.AM.NUCL.SOC.39, 272(1981) 328 1451 272 YO88 P.G.YOUNG, INT.CONF.NUCL.DATA SCI.& TECH., MITO (1988). 328 1451 273 328 1451 274 1 451 277 1 328 1451 275 3 102 11 1 328 1451 276 33 102 10 0 328 1451 277 328 1 0 278 328 0 0 279 3.007000+3 6.955732+0 0 0 0 0 328 3102 280 2.032800+6 2.032800+6 0 0 1 23 328 3102 281 23 5 0 0 0 0 328 3102 282 1.000000-5 2.284000+0 2.530000-2 4.540000-2 1.000000-1 2.284000-2 328 3102 283 1.000000+0 7.221000-3 1.000000+1 2.284000-3 1.000000+2 7.221000-4 328 3102 284 1.000000+3 2.000000-4 1.000000+4 1.000000-4 5.000000+4 3.650000-5 328 3102 285 8.000000+4 2.800000-5 1.000000+5 2.500000-5 1.400000+5 2.150000-5 328 3102 286 1.800000+5 2.250000-5 2.000000+5 2.550000-5 2.300000+5 3.300000-5 328 3102 287 2.600000+5 3.750000-5 3.000000+5 2.500000-5 3.500000+5 1.500000-5 328 3102 288 4.000000+5 1.100000-5 5.000000+5 8.000000-6 6.000000+5 6.000000-6 328 3102 289 1.000000+6 5.000000-6 2.000000+7 4.000000-6 0.000000+0 0.000000+0 328 3102 290 328 3 0 291 328 0 0 292 3.007000+3 6.955732+0 0 0 0 1 32833102 293 0.000000+0 0.000000+0 0 102 0 2 32833102 294 0.000000+0 0.000000+0 0 1 6 3 32833102 295 1.000000-5 2.250000-2 1.000000+5 0.000000+0 2.000000+7 0.000000+0 32833102 296 0.000000+0 0.000000+0 0 1 28 14 32833102 297 1.000000-5 0.000000+0 1.000000+3 2.250000-2 1.000000+4 2.500000-1 32833102 298 1.000000+5 4.000000+0 1.000000+6 4.000000+0 3.000000+6 4.000000+0 32833102 299 5.000000+6 4.000000+0 7.000000+6 4.000000+0 9.000000+6 4.000000+0 32833102 300 1.100000+7 4.000000+0 1.300000+7 4.000000+0 1.500000+7 1.600000+1 32833102 301 1.700000+7 1.000000+2 2.000000+7 0.000000+0 0.000000+0 0.000000+0 32833102 302 32833 0 303 328 0 0 304 0 0 0 305 4.009000+3 8.934780+0 -1 0 0 1 425 1451 1 0.000000+0 0.000000+0 0 0 0 6 425 1451 2 1.000000+0 0.000000+0 0 0 10 6 425 1451 3 0.000000+0 0.000000+0 0 0 280 5 425 1451 4 4-BE- 9 LLNL EVAL-JAN86 PERKINS, PLECHATY, HOWERTON 425 1451 5 DIST-JAN90 891211 425 1451 6 ----ENDF/B-VI MATERIAL 425 425 1451 7 -----INCIDENT NEUTRON DATA 425 1451 8 ------ENDF-6 FORMAT 425 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 425 1451 10 ACTIVATION I 425 1451 11 ****************************************************************** 425 1451 12 425 1451 13 BE-9 EVALUATED NEUTRON CROSS SECTIONS FOR 425 1451 14 ENDF/B-VI. EVALUATED BY S.T. PERKINS, E.F. 425 1451 15 PLECHATY, AND R.J. HOWERTON. LAWRENCE LIVERMORE 425 1451 16 NATIONAL LABORATORY, LIVERMORE CA., JAN. 1986. 425 1451 17 425 1451 18 GENERAL COMMENTS 425 1451 19 THE NEUTRON ENERGY RANGE COVERED EXTENDS FROM .00001 EV TO 425 1451 20 20 MEV. IN ADDITION TO ELASTIC SCATTERING WHICH OF COURSE IS 425 1451 21 EVERYWHERE ENERGETICALLY POSSIBLE, THE FOLLOWING REACTIONS HAVE 425 1451 22 THRESHOLDS AT ENERGIES LESS THAN 20 MEV (UCRL 50400, VOL. 9, 425 1451 23 (1970)): 425 1451 24 reaction threshold (mev) 425 1451 25 n,2n 1.85 425 1451 26 n,p 14.26 425 1451 27 n,np 18.76 425 1451 28 n,d 16.29 425 1451 29 n,nd 18.55 425 1451 30 n,t 11.60 425 1451 31 n,nt 19.65 425 1451 32 n,alpha 0.67 425 1451 33 n,n alpha 2.74 425 1451 34 n,gamma exoergic 425 1451 35 FOR THE (N,NP), (N,ND), AND (N,NT) REACTIONS, THERE ARE 425 1451 36 NO MEASUREMENTS AND SINCE THE THRESHOLDS ARE SUFFICIENTLY 425 1451 37 HIGH, THESE CROSS SECTIONS ARE ASSUMED TO BE NEGLIGIBLE. THE 425 1451 38 (N,N ALPHA) REACTION IS A DECAY MODE FOR THE (N,2N) 425 1451 39 REACTION SINCE HE-5 IS UNSTABLE, DECAYING IMMEDIATELY TO A 425 1451 40 NEUTRON AND AN ALPHA PARTICLE . THE INELASTIC SCATTERING 425 1451 41 REACTION IS ALSO A DECAY MODE FOR THE (N,2N) REACTION 425 1451 42 SINCE THE BE-9* RECOIL NUCLEUS ALWAYS DECAYS TO THE FINAL END 425 1451 43 PRODUCTS OF A NEUTRON AND TWO ALPHA PARTICLES. THE SELECTION OF 425 1451 44 THE CROSS SECTIONS FOR ELASTIC SCATTERING, (N,2N), 425 1451 45 (N,P), (N,D), (N,T), (N, ALPHA), (N, GAMMA), AND THE 425 1451 46 (N,X GAMMA) REACTION IS DISCUSSED BELOW. 425 1451 47 425 1451 48 ELASTIC SCATTERING CROSS SECTION 425 1451 49 THE FREE ATOM CROSS SECTION IS USED FOR ALL ENERGIES BELOW 425 1451 50 THE UPPER LIMIT OF THE MOLECULAR BINDING ENERGY (ABOUT 10 EV). 425 1451 51 THIS IS EFFECTIVELY ONLY THE NUCLEAR PART OF THE CROSS SECTION OF 425 1451 52 A STATIONARY TARGET AT ZERO DEGREES KELVIN. IT IS STRONGLY 425 1451 53 EMPHASIZED THAT THE NUMBERS ARE MEANINGLESS IN THE ABSENCE OF A 425 1451 54 PROPER THERMAL TREATMENT BY EITHER THE PROCESSING CODE OR THE 425 1451 55 NEUTRONICS CODE WHICH USES THESE NUMBERS. THEY ARE LIKEWISE 425 1451 56 MEANINGLESS IF THE MATERIALS FOR WHICH THEY ARE TO BE USED ARE 425 1451 57 BOUND IN MOLECULES UNLESS MOLECULAR BINDING IS TAKEN INTO 425 1451 58 ACCOUNT. 425 1451 59 THE SCATTERING CROSS SECTION WAS TAKEN EQUAL TO 6.15 BARNS 425 1451 60 (NEUTRON CROSS SECTIONS, VO1. 1, PT. A, ACADEMIC PRESS (1981), 425 1451 61 S. F. MUGHABGHAB, M. DIVADEENAM, AND N. E. HOLDEN) 425 1451 62 FROM 0.00001 EV TO 0.01 MEV. FROM .01 MEV TO THE (N,ALPHA) 425 1451 63 THRESHOLD AT 0.67 MEV, THE ELASTIC SCATTERING CROSS SECTION IS 425 1451 64 EQUAL TO THE TOTAL CROSS SECTION SINCE THE (N,GAMMA) CROSS 425 1451 65 SECTION IS NEGLIGIBLE. THE CROSS SECTION WAS BASED ON DATA OF 425 1451 66 REFS. 63, 92, 720, 772, AND 1002. 425 1451 67 ABOVE THE (N,ALPHA) THRESHOLD, THE SCATTERING CROSS SECTION 425 1451 68 WAS TAKEN AS THE DIFFERENCE BETWEEN THE TOTAL AND THE NONELASTIC, 425 1451 69 WITH THE NONELASTIC BEING EQUAL TO THE SUM OF ITS PARTS. UP TO 2 425 1451 70 MEV, THE TOTAL CROSS SECTION WAS BASED ON THE PREVIOUSLY 425 1451 71 MENTIONED DATA, AND THOSE FROM REFS. 72, 336 AND 1642. 425 1451 72 FROM 3.2-4.4 MEV, THE ARGONNE TOTAL CROSS SECTION DATA WAS USED 425 1451 73 (A.B. SMITH, PRIVATE COMMUNICATION, 1988). FROM 4.5-10. MEV 425 1451 74 THE ARGONNE ELASTIC CROSS SECTION DATA WAS USED (A.B. SMITH, 425 1451 75 PRIVATE COMMUNICATION, 1988). 425 1451 76 ALSO ABOVE 2. MEV, WE RELIED ON THE RESULTS OF REF. 3088 425 1451 77 OVER THE 2.7 MEV RESONANCE, AND REF. 750 AND THE ELASTIC 425 1451 78 SCATTERING DATA FROM REF. 4113 AND 4473 UP TO 15 MEV. FOR 425 1451 79 INCIDENT NEUTRON ENERGIES FROM 15 TO 20 MEV, THE DATA FROM 425 1451 80 REFS. 107, 673, AND 682 WERE USED. 425 1451 81 425 1451 82 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS 425 1451 83 (NORMALIZED PROBABILITIES) 425 1451 84 UP TO 7 MEV, THERE ARE EXPERIMENTAL DIFFERENTIAL SCATTERING 425 1451 85 DATA IN REFS. 121, 151, 231, 296, 500, 571, 945, 1643, 1645, 1646 425 1451 86 AND 1647. THESE RESULTS WERE USED TO DETERMINE THE NORMALIZED 425 1451 87 PROBABILITIES. IN BE BELOW THE (N,2N) THRESHOLD, THE TOTAL 425 1451 88 SCATTERING DATA ARE EQUIVALENT TO THOSE FOR ELASTIC SCATTERING. 425 1451 89 THE CHANGE IN SHAPE OF THE ANGULAR DISTRIBUTION GOING THROUGH 425 1451 90 THE SCATTERING RESONANCES WAS TAKEN INTO ACCOUNT. FROM 4.5-10. 425 1451 91 THE ARGONNE DIFFERENTIAL ELASTIC SCATTERING CROSS SECTIONS WERE 425 1451 92 USED (A.B. SMITH, PRIVATE COMMUNICATION, 1988). FROM 6 TO 15 425 1451 93 MEV, THE RESULTS OF REFS. 4113, 4473, 402, 2585, AND 3106 425 1451 94 WERE ALSO USED. A SMOOTH EXTRAPOLATION WAS MADE TO 20 MEV. 425 1451 95 425 1451 96 THE (N,2N) EVALUATION 425 1451 97 THE EVALUATION FOR THE BE-9 (N,2N) REACTION IS 425 1451 98 DESCRIBED IN DETAIL IN NUCL. SCI. & ENG. 90, 85 (1985), S. T. 425 1451 99 PERKINS, E. F. PLECHATY, AND R. J. HOWERTON. IT INVOLVED USING 425 1451 100 A MONTE CARLO TECHNIQUE AND COMPARING THE CALCULATED SPECTRA 425 1451 101 AGAINST RECENT DOUBLE DIFFERENTIAL CROSS SECTION MEASUREMENTS. 425 1451 102 AT EACH INCIDENT NEUTRON ENERGY, 5,000,000 EVENTS WERE 425 1451 103 SAMPLED, RESULTING IN 10,000,000 SECONDARY NEUTRONS. THE 425 1451 104 (N,2N) REACTION WAS DESCRIBED BY THE FOLLOWING FOUR EVENTS: 425 1451 105 BE9(N,N1)BE9*(N2)BE8*(A1)A2, 425 1451 106 BE9(N,N1)BE9*(A1)HE5*(N2)A2, 425 1451 107 BE9(N,A1)HE6*(N1)HE5*(N2)A2, 425 1451 108 BE9(N,HE5*1)HE5*2, 425 1451 109 HE5*1(N1)A1, 425 1451 110 HE5*2(N2)A2. 425 1451 111 WHERE, N IS NEUTRON, A IS ALPHA PARTICLE, AND * DENOTES AN 425 1451 112 EXCITED STATE. WIDE LEVEL TRANSITIONS WERE CONSIDERED AS 425 1451 113 REQUIRED. 425 1451 114 425 1451 115 TOTAL (N,2N) CROSS SECTION 425 1451 116 THE TOTAL (N,2N) CROSS SECTION WAS BASED ON THE DATA FROM 425 1451 117 REF. 683, 763, 3320, 4473, 4871, AND 5660. AT 14 MEV, THE 425 1451 118 WEIGHTED MEAN OF THE EIGHT VALUES MEASURED BETWEEN 1958-1963 425 1451 119 WAS ALSO CONSIDERED. THE RESULTING CURVE IS SIMILAR TO THAT 425 1451 120 USED IN ENDF/B-V. 425 1451 121 425 1451 122 (N,2N) DOUBLE DIFFERENTIAL SPECTRA 425 1451 123 THE CALCULATED DOUBLE DIFFERENTIAL SPECTRA WERE COMPARED 425 1451 124 TO 51 MEASUREMENTS BETWEEN 3.25 AND 15.4 MEV: 425 1451 125 REF. 4871 (3.25-15.4 MEV), REF. 4473 (5.9-14.2 MEV), AND 425 1451 126 PROC. INT. CONF. NUCL. DATA FOR SCI. AND TECH., ANTWERP, 425 1451 127 CONF-820906, P. 360 (1982), A. TAKAHASHI ET. AL.; SEE ALSO 425 1451 128 OKTAVIAN REPORT A-83-01, OSAKA UNIV., JAPAN (1983), (14 MEV). 425 1451 129 COMPARISONS WERE MADE AFTER WEIGHING THE CALCULATED RESULTS 425 1451 130 WITH THE EXPERIMENTAL RESOLUTION FUNCTION. THE FINAL 425 1451 131 CALCULATED SPECTRA WERE THEN SMOOTHED AND THINNED. THIS YIELDED 425 1451 132 DOUBLE DIFFERENTIAL SPECTRA FOR BOTH THE SECONDARY NEUTRONS 425 1451 133 AND THE SECONDARY ALPHA PARTICLES. 425 1451 134 425 1451 135 (N,P) CROSS SECTION 425 1451 136 THIS CROSS SECTION IS ENTIRELY FOR THE (N,P0) REACTION 425 1451 137 AND WAS BASED ON THE DATA FROM REFS. 913 AND 3492. IT WAS 425 1451 138 SMOOTHLY EXTRAPOLATED FROM 15.5 TO 20 MEV. THE PROTON WAS 425 1451 139 ASSUMED ISOTROPIC IN ITS CENTER OF MASS SYSTEM. 425 1451 140 425 1451 141 (N,D) CROSS SECTION 425 1451 142 THIS CROSS SECTION IS ENTIRELY FOR THE (N,D0) REACTION 425 1451 143 AND WAS BASED ON THE DATA BETWEEN 15.5 AND 19 MEV REPORTED 425 1451 144 IN REF. 4841. THE DEUTERON WAS ASSUMED ISOTROPIC IN ITS 425 1451 145 CENTER OF MASS SYSTEM. 425 1451 146 425 1451 147 (N,T) CROSS SECTION 425 1451 148 THE CROSS SECTION FOR THE (N,T) REACTION IS BASED ON A 425 1451 149 (N,T0) AND A(N,T1) COMPONENT, WHICH PROCEED THROUGH THE 0. AND 425 1451 150 THE 0.477 MEV LEVELS IN LI-7 RESPECTIVELY. THE TOTAL (N,T) 425 1451 151 CROSS SECTION NEAR 14 MEV WAS DETERMINED FROM REF. 496, 3996 425 1451 152 AND 5722. 425 1451 153 THE (N,T1) CROSS SECTION WAS BASED ON THE WORK IN REF. 5529 425 1451 154 AND SMOOTHLY EXTRAPOLATED FROM 15 TO 20 MEV. 425 1451 155 THE RESONANCE NEAR THRESHOLD IS CONSISTENT WITH STRUCTURE IN THE 425 1451 156 COMPOUND SYSTEM BE-10. 425 1451 157 BOTH TRITONS WERE ASSUMED ISOTROPIC IN THEIR CENTER 425 1451 158 OF MASS SYSTEMS. 425 1451 159 425 1451 160 (N,ALPHA) CROSS SECTION 425 1451 161 THE CROSS SECTION WAS BASED ON THE MEASUREMENTS REPORTED 425 1451 162 IN REF. 160, 494 AND 733 UP TO NEUTRON ENERGIES OF 8.6 MEV. IT 425 1451 163 WAS THEN TIED INTO THE FOUR VALUES GIVEN AT 14 MEV BY REFS. 86, 425 1451 164 650, 2367, AND NUCL. PHYS. A227, 330 (1978), J. P. PERROUD 425 1451 165 AND CH. SELLEM. IT WAS THEN EXTRAPOLATED TO 20 MEV. NOTE 425 1451 166 THAT THE MEASURED CROSS SECTION IS TO HE-6(0. MEV) WHICH BETA 425 1451 167 DECAYS TO LI-6; HIGHER STATES IN HE-6 DECAY TO ALPHA + 2N. 425 1451 168 THE ALPHA PARTICLE ANGULAR DISTRIBUTION WAS TAKEN AS ISOTROPIC 425 1451 169 IN THE CENTER OF MASS SYSTEM AT THRESHOLD. AT 14.1 MEV THE 425 1451 170 DATA FROM THE MEASUREMENT OF REF; 4351 WAS USED; THIS 425 1451 171 DISTRIBUTION WAS ALSO USED AT 20 MEV. 425 1451 172 425 1451 173 (N,GAMMA) CROSS SECTION 425 1451 174 THE CROSS SECTION WAS ASSUMED TO BE 1/V BELOW 100 EV WITH 425 1451 175 A 2200 M/SEC CROSS SECTION OF 8.6 MB. THIS IS IN AGREEMENT WITH 425 1451 176 THE CSEWG DOSIMETRY AND ACTIVATION FILES. IT WAS THEN 425 1451 177 EXTRAPOLATED LINEARLY ON A LOG-LOG BASIS TO 0.1 MB AT 1 KEV AND 425 1451 178 THEN HELD CONSTANT AT THIS VALUE UP TO 20 MEV. 425 1451 179 425 1451 180 (N,X GAMMA) CROSS SECTION 425 1451 181 GAMMA RAYS IN BE-9 ARE PRODUCED BY THE (N,GAMMA) AND THE 425 1451 182 (N,T) REACTIONS. AT THERMAL ENERGIES, REF. 2415 QUOTES GAMMA RAY 425 1451 183 ENERGIES OF 0.8535, 2.59, 3.368, 3.444, 5.958 AND 6.81 MEV AND 425 1451 184 THE CORRESPONDING (N,X GAMMA) CROSS SECTIONS. 425 1451 185 THE PHOTON SPECTRUM FROM THIS WORK WAS USED AT ALL NEUTRON 425 1451 186 ENERGIES. THE MULTIPLICITY VARIED WITH NEUTRON ENERGY AS 425 1451 187 M(E)=M(0)(E(CM)+Q)/Q, WHERE M(0) IS THE MULTIPLICITY AT THERMAL 425 1451 188 AND Q IS THE (N,GAMMA) Q VALUE. THIS COMBINATION OF SPECTRA 425 1451 189 AND MULTIPLICITY CONSERVES ENERGY. THERE ARE NO DOUBT OTHER 425 1451 190 LEVELS IN BE-10 WITH ENERGIES GREATER THAN 6.81 MEV EXCITED AS 425 1451 191 THE INCIDENT NEUTRON ENERGY IS INCREASED. THE ENERGIES OF THE 425 1451 192 HIGHER STATES HAVE NOT YET BEEN DETERMINED SO WE USE THIS 425 1451 193 ARTIFACT TO CONSERVE ENERGY. THE COMPONENT RESULTING FROM THE 425 1451 194 (N,T) REACTION IS EQUAL TO THE (N,T1) CROSS SECTION SINCE ITS 425 1451 195 MULTIPLICITY IS UNITY. 425 1451 196 425 1451 197 REFERENCES 425 1451 198 (REFERENCE NUMBERS QUOTED HERE REFER TO DATA IN THE LLNL 425 1451 199 EXPERIMENTAL NEUTRON CROSS SECTION LIBRARY. SEE UCRL-50400,VOL. 425 1451 200 2 AND 3 FOR COMMENTS AND INDEXES TO THE DATA). 425 1451 201 63. PHYS. REV. 80, 1011 (1950) C.K. BOCKELMAN. 425 1451 202 72. PHYS. REV. 84, 69 (1951) C.K. BOCKELMAN, D.W. MILLER, 425 1451 203 R.K. ADAIR, H.H. BARSCHALL. R 425 1451 204 86. PHYS. REV. 89, 80 (1953) M.E. BATTAT, F.L. RIBE. 425 1451 205 92. PRIVATE COMMUNICATION (1954) P.H. STELSON. 425 1451 206 107. PHYS. REV. 94, 651 (1954) C.F. COOK, T.W. BONNER. 425 1451 207 121. PHYS. REV. 98, 669 (1955) J.D. SEAGRAVE, R.L. HENKEL. 425 1451 208 151. PHYS. REV. 104, 1319 (1956) J.R. BEYSTER, M. WALT, 425 1451 209 E.W. SALMI. 425 1451 210 160. PHYS. REV. 106, 1252 (1957) P.H. STELSON, E.C. CAMPBELL. 425 1451 211 231. ANL-5567 (1956) A. LANGSDORF, JR., R.O. LANE, J.E. MONAHAN, 425 1451 212 SEE ALSO, ANL-5554 P. 22 (1956), PHYS. REV. 107, 1077 425 1451 213 (1957), ANL-5567 (REV.) (1961). 425 1451 214 296. PHYS. REV. 98, 677 (1955) M. WALT, J.R. BEYSTER. 425 1451 215 336. PROC. PHYS. SOC. (LONDON) 64, 388 (1951) G.H. ST AFFORD. 425 1451 216 402. PHYS. REV. 110, 1439 (1959) M.P. NAKADA, J.D. ANDERSON, 425 1451 217 C.C. GARDNER, C. WONG. 425 1451 218 494. DOKLADY AKAD. NAUK S.S.S.R. 119, 914 (1958) S.S. VASILEV, 425 1451 219 V.V. KUMAROV, A.M. POPOVA, SEE ALSO, J. EXPTL. THEORET. 425 1451 220 PHYS. (USSR) 33, 527 (1957). 425 1451 221 496. PHYS. REV. 112, 1264 (1958) M.E. WYMAN, E.M. FRYER, 425 1451 222 M.M. THORPE. 425 1451 223 500. PHYS. REV. 114, 1584 (1959) J.B. MARION, J.S. LEVIN, 425 1451 224 L. CRANBERG. 425 1451 225 571. ANL-6172 (1960) R.O. LANE, A.S. LANGSDORF, JR., 425 1451 226 J.E. MONAHAN, A.J. ELWYN, SEE ALSO, ANN. PHYS. (N.Y.) 12, 425 1451 227 135 (1961). 425 1451 228 650. J. EXPTL. THEORET. PHYS. (USSR), 40, 1244 (1961), 425 1451 229 S. A. MYACHKOVA AND V. P. PERELYGIN. 425 1451 230 673. PHYS. REV. 120, 521 (1960) J.M. PETERSON, A. BRATENAHL, 425 1451 231 J.P. STOERING. 425 1451 232 682. PHYS. REV. 123, 209 (1961) D.B. FOSSAN, R.L. WALTER, 425 1451 233 W.E. WILSON, H.H. BARSCHALL. 425 1451 234 720. PRIVATE COMMUNICATION (1962) E.G. BILPUCH, J.A. FARRELL, 425 1451 235 G.C. KYKER, JR., P.B. PARKS, H. NEWSON. 425 1451 236 733. NUCLEAR PH YS. 23, 122 (1961) R. BASS, T.W. BONNER, 425 1451 237 H.P.HAENNI. 425 1451 238 750. PRIVATE COMMUNICATION (1967) D.G. FOSTER, JR., 425 1451 239 D.W. GLASGOW, SEE ALSO, HW-73116 (1962), HW-77311 (1963), 425 1451 240 PHYS. REV. C, 3, 576 (1971), PHYS. REV. C, 3, 604 (1971). 425 1451 241 763. NUCLEAR PHYS. 129, 305 (1969) M. HOLMBERG, J. HANSEN, SEE 425 1451 242 ALSO, IAEA CONFERENCE ON NUCLEAR DATA, PARIS, PAPER 425 1451 243 CN-23/18 (1966). 425 1451 244 772. COMPT. REND. 255, 277 (1962) A. PERRIN, G. SURGET, 425 1451 245 C. THIBAULT, F. VERRIERE. 425 1451 246 913. PHYS. REV. 132, 328 (1963) D.E. ALBUGER. 425 1451 247 945. ORNL-2610 P. 14 (1958) H.O. COHN, J.L. FOWLER, SEE ALSO, 425 1451 248 BULL. AM. PHYS. SOC. 3, 305 (1958). 425 1451 249 1002. PRIVATE COMMUNICATION (1954) C.T. HIBDON, A. LANGSDORF. 425 1451 250 1642. BULL. AM. PHYS. SOC. 4, 385 (1959) J.L. FOWLER, H.O. COHN. 425 1451 251 1643. DOKLADY AKAD. NAUK S.S.S.R. 158, 574 (1964) G.V. GORLOV, 425 1451 252 N.S. LEBEDEVA, V.M. MOROZOV, SEE ALSO, YAD. FIZ. 5, 910 425 1451 253 (1967). 425 1451 254 1645. PRIVATE COMMUNICATION (1960) J.S. LEVIN, L. CRANBERG, SEE 425 1451 255 ALSO, WASH-1028 P. 26 (1960), WASH-1029 P. 44 (1960). 425 1451 256 1646. PRIVATE COMMUNICATION (1961) D.D. PHILLIPS. 425 1451 257 1647. PHYS. REV. 133, 409 (1964) R.O. LANE, A.J. ELWYN, 425 1451 258 A. LANGSDORF, JR. 425 1451 259 2367. NUCLEAR PHYS. 96, 476 (1967) G. PAIC, D. RENDIC, P. TOMAS. 425 1451 260 2415. GA-10248 (DASA-2570) (1970) N.C. RASMUSSEN, V.J. ORPHAN, 425 1451 261 T.L. HARPER, J. CUNNINGHAM, S.A. ALI. 425 1451 262 2585. PRIVATE COMMUNICATION (1966) R. BOUCHEZ, SEE ALSO, IAEA 425 1451 263 CONFERENCE ON NUCLEAR DATA, PARIS, PAPER CN-23/75 (1966). 425 1451 264 3088. CONFERENCE ON NEUTRON CROSS SECTION TECHNOLOGY, 425 1451 265 WASHINGTON D. C., P. 851 (1968) C.H. JOHNSON, F.X. HAAS, 425 1451 266 J.L. FOWLER, F.D. MARTIN, R.L. KERNELL, H.O. COHN. 425 1451 267 3106. NP-17794 (1968) J. ROTURIER, SEE ALSO, COMPT. REND. 260, 425 1451 268 4491 (1965), BNL-400, 3RD ED. (1970). 425 1451 269 3320. ATOMKERNENERGIE 20,309 (1972) M. BLOSER 425 1451 270 3492. NUCL. SCI. AND ENG. 54,190 (1974), R. H. AUGUSTSON AND 425 1451 271 H. O. MENLOVE. 425 1451 272 3996. J. INORG. NUCL. CHEM. 37, 1583, (1975), T. BIRO, ET. AL. 425 1451 273 4113. NUCL. SCI. & ENG. 68, 38 (1978), H. H. HOGUE EL. AL. 425 1451 274 4351. NUCL. PHYS. 257, 397 (1976), W. SMOLEC ET. AL. 425 1451 275 4473. NUCL. SCI. & ENG. 63,401 (1977), D. M. DRAKE, G. F. 425 1451 276 AUCHAMPAUGH, E. D. ARTHUR, C. E. RAGAN, AND P. G. YOUNG. 425 1451 277 4841. Z. NATURFORSCHG. 25, 1460 (1970), W. SCOBEL AND M. 425 1451 278 BORMANN. 425 1451 279 5529. NUCL. SCI. & ENG. 61, 267 (1976), F. S. DIETRICH, L. F. 425 1451 280 HANSEN AND R. P. KOOPMAN. 425 1451 281 5722. NUCL. DATA. FOR SCI. AND TECH., ANTWERP, P. 368 (1982), 425 1451 282 Z. T. BODY ET. AL. 425 1451 283 425 1451 284 1 451 289 1 425 1451 285 3 102 26 1 425 1451 286 3 103 6 1 425 1451 287 3 104 7 1 425 1451 288 3 107 12 1 425 1451 289 425 1 0 290 425 0 0 291 4.009000+3 8.934780+0 0 0 0 0 425 3102 292 6.820000+6 6.820000+6 0 0 1 69 425 3102 293 69 2 0 0 0 0 425 3102 294 1.000000-5 1.366500-1 1.331000-4 1.184500-1 1.610500-4 1.076900-1 425 3102 295 2.143600-4 9.334800-2 2.593700-4 8.486500-2 3.452300-4 7.356400-2 425 3102 296 4.177200-4 6.687800-2 5.054500-4 6.080100-2 6.115900-4 5.527500-2 425 3102 297 7.400200-4 5.025200-2 8.954300-4 4.568500-2 1.083500-3 4.153300-2 425 3102 298 1.311000-3 3.775900-2 1.586300-3 3.432800-2 1.919400-3 3.120800-2 425 3102 299 2.554800-3 2.705200-2 3.091300-3 2.459400-2 3.740400-3 2.235900-2 425 3102 300 4.978500-3 1.938100-2 6.626400-3 1.680000-2 8.819700-3 1.456300-2 425 3102 301 1.173900-2 1.262400-2 1.420400-2 1.147600-2 1.890600-2 9.948000-3 425 3102 302 2.287600-2 9.044000-3 2.530000-2 8.600000-3 3.044800-2 7.839600-3 425 3102 303 4.052700-2 6.795600-3 5.394100-2 5.890600-3 6.526800-2 5.355300-3 425 3102 304 8.687200-2 4.642100-3 1.051200-1 4.220300-3 1.271900-1 3.836700-3 425 3102 305 1.539000-1 3.488100-3 1.862200-1 3.171100-3 2.253200-1 2.882900-3 425 3102 306 2.726400-1 2.620900-3 3.299000-1 2.382700-3 3.991800-1 2.166200-3 425 3102 307 4.830000-1 1.969300-3 6.428800-1 1.707100-3 8.556700-1 1.479700-3 425 3102 308 1.035400+0 1.345300-3 1.252800+0 1.223000-3 1.515900+0 1.111900-3 425 3102 309 1.834200+0 1.010800-3 2.219400+0 9.189700-4 2.685500+0 8.354500-4 425 3102 310 3.249400+0 7.595300-4 3.931800+0 6.905100-4 4.757400+0 6.277600-4 425 3102 311 6.332200+0 5.441600-4 7.661900+0 4.947100-4 9.270900+0 4.497500-4 425 3102 312 1.234000+1 3.898600-4 1.642400+1 3.379400-4 2.186000+1 2.929300-4 425 3102 313 2.909600+1 2.539200-4 3.872700+1 2.201100-4 5.154500+1 1.908000-4 425 3102 314 6.237000+1 1.734600-4 8.301500+1 1.503600-4 1.000000+2 1.370000-4 425 3102 315 1.464100+2 1.300400-4 2.143600+2 1.234400-4 3.797500+2 1.141500-4 425 3102 316 6.115900+2 1.069500-4 1.000000+3 1.000000-4 2.000000+7 1.000000-4 425 3102 317 425 3 0 318 4.009000+3 8.934780+0 0 0 0 0 425 3103 319 -1.283000+7-1.283000+7 0 0 1 8 425 3103 320 8 2 0 0 0 0 425 3103 321 1.426596+7 0.000000+0 1.465000+7 1.200000-4 1.520000+7 4.000000-4 425 3103 322 1.565000+7 7.000000-4 1.595000+7 8.400000-4 1.655000+7 1.080000-3 425 3103 323 1.800000+7 1.300000-3 2.000000+7 1.500000-3 0.000000+0 0.000000+0 425 3103 324 425 3 0 325 4.009000+3 8.934780+0 0 0 0 0 425 3104 326 -1.466000+7-1.466000+7 0 0 1 11 425 3104 327 11 2 0 0 0 0 425 3104 328 1.630078+7 0.000000+0 1.655000+7 1.000000-4 1.670000+7 5.000000-4 425 3104 329 1.695000+7 2.000000-3 1.710000+7 4.000000-3 1.735000+7 6.000000-3 425 3104 330 1.785000+7 8.300000-3 1.820000+7 9.500000-3 1.890000+7 1.100000-2 425 3104 331 1.950000+7 1.170000-2 2.000000+7 1.200000-2 0.000000+0 0.000000+0 425 3104 332 425 3 0 333 4.009000+3 8.934780+0 0 0 0 0 425 3107 334 -6.000000+5-6.000000+5 0 0 1 25 425 3107 335 25 2 0 0 0 0 425 3107 336 6.671530+5 0.000000+0 7.400000+5 2.000000-5 9.000000+5 3.000000-4 425 3107 337 1.000000+6 7.000000-4 1.050000+6 1.000000-3 1.100000+6 1.700000-3 425 3107 338 1.150000+6 2.800000-3 1.200000+6 4.000000-3 1.330000+6 8.000000-3 425 3107 339 1.500000+6 1.600000-2 2.000000+6 4.500000-2 2.600000+6 9.500000-2 425 3107 340 2.800000+6 1.050000-1 3.000000+6 1.050000-1 4.000000+6 8.500000-2 425 3107 341 5.000000+6 6.500000-2 5.500000+6 5.600000-2 6.250000+6 4.400000-2 425 3107 342 7.000000+6 3.500000-2 8.000000+6 2.750000-2 9.000000+6 2.200000-2 425 3107 343 1.100000+7 1.550000-2 1.250000+7 1.200000-2 1.450000+7 1.000000-2 425 3107 344 2.000000+7 5.000000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 425 3107 345 425 3 0 346 425 0 0 347 0 0 0 348 5.010000+3 9.926921+0 -1 0 0 1 525 1451 1 0.000000+0 0.000000+0 0 0 0 6 525 1451 2 1.000000+0 0.000000+0 0 0 10 6 525 1451 3 0.000000+0 0.000000+0 0 0 301 3 525 1451 4 5-B - 10 LANL EVAL-NOV89 G.M.HALE, P.G.YOUNG 525 1451 5 DIST-JAN90 900108 525 1451 6 ----ENDF/B-VI MATERIAL 525 525 1451 7 -----INCIDENT NEUTRON DATA 525 1451 8 ------ENDF-6 FORMAT 525 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 525 1451 10 ACTIVATION I 525 1451 11 ****************************************************************** 525 1451 12 525 1451 13 ****************************************************************** 525 1451 14 525 1451 15 ENDF/VI EVALUATION 525 1451 16 G. M. Hale and P. G. Young 525 1451 17 525 1451 18 MAJOR CHANGES FROM VERSION V OF ENDF/B ARE: 525 1451 19 525 1451 20 1. Inclusion of the ENDF/B-VI standard (n,alpha) and (n,alpha1) 525 1451 21 results from the simultaneous standards analysis (Ca85) over 525 1451 22 the standard energy range thermal to 100 keV. 525 1451 23 2. Replacement of all major cross sections and elastic angular 525 1451 24 distributions from 10-5 eV to 1 MeV with results from the 525 1451 25 R-matrix analysis performed in conjunction with the 525 1451 26 simultaneous standards analysis. 525 1451 27 3. Replaced the total cross section 1-20 MeV with results 525 1451 28 from a covariance analysis of available data. 525 1451 29 4. Revised elastic and inelastic cross sections for low-lying 525 1451 30 levels incorporating new elastic, inelastic, and (n,xgamma) 525 1451 31 experimental data. We attempted to better reconcile the 525 1451 32 inelastic and gamma ray data. 525 1451 33 5. Refit all elastic angular distributions from 1-20 MeV with 525 1451 34 Legendre expansions and incorporated results from new 525 1451 35 measurements. 525 1451 36 6. Fit inelastic neutron angular distributions for first 5 525 1451 37 excited states of B10 with Legendre expansions. 525 1451 38 7. Incorporated new (n,t2alpha) cross section data into MT113 525 1451 39 and adjusted (n,alpha) cross sections above standard region 525 1451 40 for better consistency with data as well as other cross 525 1451 41 sections (esp. total and elastic) determined by data. 525 1451 42 525 1451 43 *****Note that covariance data will be added at a later date. 525 1451 44 525 1451 45 ****************************************************************** 525 1451 46 525 1451 47 mf=2 --------- resonance parameters ---------------------------- 525 1451 48 525 1451 49 mt=151 effective scattering radius = 4.129038-13 cm 525 1451 50 525 1451 51 525 1451 52 mf=3 --------- smooth cross sections --------------------------- 525 1451 53 525 1451 54 the 2200 m/s cross sections are as follows, 525 1451 55 mt=1 sigma = 3842.146 barns 525 1451 56 mt=2 sigma = 2.142435 barns 525 1451 57 mt=102 sigma = 0.5 barns 525 1451 58 mt=103 sigma = 0.000566 barns 525 1451 59 mt=107 sigma = 3839.496 barns 525 1451 60 mt=113 sigma = 0.0069993 barns 525 1451 61 mt=600 sigma = 0.000566 barns 525 1451 62 mt=800 sigma = 241.2677 barns 525 1451 63 mt=801 sigma = 3598.228 barns 525 1451 64 525 1451 65 mt=1 total cross section 525 1451 66 0 to 1 mev, calculated from r-matrix parameters obtained 525 1451 67 from simultaneous standards analysis (ca85) used to 525 1451 68 obtain the endf/b-vi standard cross sections. 525 1451 69 1 to 20 mev, covariance analysis of measurements of di67, 525 1451 70 ts62,fo61,co52,au79, and co54, constrained to match 525 1451 71 r-matrix fit at 1 mev. glucs covariance analysis code 525 1451 72 (he80) was used in the calculations. 525 1451 73 525 1451 74 mt=2 elastic scattering cross section 525 1451 75 0 to 1 mev, calculated from the r-matrix parameters 525 1451 76 described for mt=1. experimental elastic scattering data 525 1451 77 included in the fit are those of as70 and la71. 525 1451 78 1 to 6 mev, smooth curve through measurements of la71, po70, 525 1451 79 sa88, and ho69, constrained to be consistent with total 525 1451 80 and reaction cross section measurements. 525 1451 81 6 to 14 mev, smooth curve through measurements of ho69,co69, 525 1451 82 te62,va70, va65, sa88, and gl82. Note that the data of 525 1451 83 sa88 above 9 MeV were discounted. 525 1451 84 14 to 20 mev, optical model extrapolation from 14 mev data 525 1451 85 525 1451 86 mt=4 inelastic cross section 525 1451 87 thres.to 20 mev, sum of mt=51-85 525 1451 88 525 1451 89 mt=51-61 inelastic cross sections to discrete states 525 1451 90 mt=51 q=-0.717 mev mt=55 q=-4.774 mev mt=59 q=-5.923 mev 525 1451 91 52 -1.740 56 -5.114 60 -6.029 525 1451 92 53 -2.154 57 -5.166 61 -6.133 525 1451 93 54 -3.585 58 -5.183 525 1451 94 thres.to 20 mev, based on (n,nprime) measurements of po70, 525 1451 95 co69,ho69,va70,sa88, and gl82, and the (n,xgam) measure- 525 1451 96 ments of da56,da60,ne70, and di88, using a gamma-ray 525 1451 97 decay scheme from analysis of aj88. hauser-feshbach 525 1451 98 calculations were used to estimate shapes and relative 525 1451 99 magnitudes where experimental data were lacking. 525 1451 100 525 1451 101 mt=62-85 inelastic cross sections to groups of levels in 525 1451 102 0.5-mev wide bands centered about the q-values given 525 1451 103 below (used in lieu of mt=91 and file 5) 525 1451 104 mt=62 q=-6.5 mev mt=70 q=-10.5 mev mt=78 q=-14.5 mev 525 1451 105 63 -7.0 71 -11.0 79 15.0 525 1451 106 64 -7.5 72 -11.5 80 15.5 525 1451 107 65 -8.0 73 -12.0 81 16.0 525 1451 108 66 -8.5 74 -12.5 82 16.5 525 1451 109 67 -9.0 75 -13.0 83 17.0 525 1451 110 68 -9.5 76 -13.5 84 17.5 525 1451 111 69 -10.0 77 -14.0 85 18.0 525 1451 112 thres. to 20 mev, integrated cross section obtained by sub- 525 1451 113 tracting the sum of mt=2,51-61,103,104,107,and 113 from 525 1451 114 mt=1. cross section distributed among the bands with 525 1451 115 an evaporation model using a nuclear temperature given 525 1451 116 by t=0.9728*sqrt(en) in mev,taken from ir67. 525 1451 117 525 1451 118 mt=102 (n,gamma) cross section 525 1451 119 0 to 1 mev, assumed 1/v dependence with thermal value of 525 1451 120 0.5 barn. 525 1451 121 1 to 20 mev, assumed negligable, set equal to zero. 525 1451 122 525 1451 123 mt=103 (n,p) cross section 525 1451 124 thres.to 20 mev, sum of mt=600-605 525 1451 125 525 1451 126 mt=104 (n,d) cross section 525 1451 127 thres. to 20 mev, based on be9(d,n)b11 measurements of si65 525 1451 128 and ba60, and the (n,d) measurement of va65. 525 1451 129 525 1451 130 mt=107 (n,alpha) cross section 525 1451 131 0 to 20 mev, sum of mt=800,801. 525 1451 132 525 1451 133 mt=113 (n,t2alpha) cross section 525 1451 134 0 to 2.3 mev, based on a single-level fit to the resonance 525 1451 135 measured at 2 mev by da61, assuming l=0 incoming neu- 525 1451 136 trons and l=2 outgoing tritons. the thermal measure- 525 1451 137 ment (7+-2 mb) of ka87 was included in the analysis. 525 1451 138 2.3 to 20 mev, smooth curve through measurements of fr56, 525 1451 139 wy58, qa88, following general shape of da61 measurement 525 1451 140 from 4 to 9 mev. we assumed that the experimental data 525 1451 141 of qa88 supercedes reference qa85. 525 1451 142 525 1451 143 mt=600-605 (n,p) cross section to discrete levels 525 1451 144 0 to 20 mev, crudely estimated from the calculations 525 1451 145 of po70 and the (n,xgamma) measurements of ne70. cross 525 1451 146 section for mt=600 assumed similar to mt=113 below 525 1451 147 1 mev. gamma-ray decay scheme for be-10 from aj88. 525 1451 148 525 1451 149 mt=800 (n,alpha0) cross section 525 1451 150 0 to 1 mev, calculated from the r-matrix parameters 525 1451 151 described for mt=1. experimental (n,alpha0) data input 525 1451 152 to the fit were those of ma68 and da61. in addition, the 525 1451 153 angular distributions of va72 for the inverse reaction 525 1451 154 were included in the analysis. 525 1451 155 1 to 20 mev, based on da61 measurements, with smooth extra- 525 1451 156 polation from 8 to 20 mev using 14-MeV data of an69. The 525 1451 157 da61 data above approximately 2 mev were renormalized 525 1451 158 by a factor of approximately 1.4. Note that some of the 525 1451 159 structure seen in da61 was expanded to give consistent 525 1451 160 nonelastic, elastic, and total cross sections when 525 1451 161 compared with experimental data. 525 1451 162 525 1451 163 mt=801 (n,alpha1) cross section 525 1451 164 0 to 1 mev, calculated from the r-matrix parameters 525 1451 165 described for mt=1. experimental (n,alpha1) data in- 525 1451 166 cluded in the fit are those of sc76. in addition, the 525 1451 167 absolute differential cross-section measurements of 525 1451 168 se76 were included in the analysis. 525 1451 169 1 to 20 mev, smooth curve through measurements of da61 and 525 1451 170 ne70, with smooth extrapolation from 15 to 20 mev. the 525 1451 171 da61 data above approximately 2 mev were renormalized 525 1451 172 by a factor of approximately 1.4. Note that some of the 525 1451 173 structure seen in da61 was expanded to give consistent 525 1451 174 nonelastic, elastic, and total cross sections when 525 1451 175 compared with experimental data. 525 1451 176 525 1451 177 525 1451 178 mf=4---------- neutron angular distributions ------------------- 525 1451 179 525 1451 180 mt=2 elastic angular distributions 525 1451 181 0 to 1 mev, calculated from the r-matrix parameters 525 1451 182 described for mf=1,mt=1. experimental angular distri- 525 1451 183 butions input to the fit for both the elastic scatter- 525 1451 184 ing cross section and polarization were obtained from 525 1451 185 available measurements. 525 1451 186 1 to 14 mev, smoothed representation of legendre coeffi- 525 1451 187 cients derived from the measurements of la71, ha73, 525 1451 188 po70, ho69, co69, va69, va65, sa88, gl82, constrained 525 1451 189 to match the r-matrix calculations at en=1 mev. 525 1451 190 14 to 20 mev, optical model extrapolation of 14-mev data 525 1451 191 525 1451 192 mt=51 inelastic angular distribution to first level 525 1451 193 thres. to 12 mev, fit Legendre expansions to exp. data of 525 1451 194 Po70, Gl82, and Sa88. 525 1451 195 12 - 20 MeV, assumed similar distribution as 12 MeV. 525 1451 196 525 1451 197 mt=52-55 inelastic angular distribution to first level 525 1451 198 thres. to 12 mev, fit Legendre expansions to exp. data of 525 1451 199 Sa88. 525 1451 200 12 - 20 MeV, assumed similar distribution as 12 MeV. 525 1451 201 525 1451 202 mt=56-85 inelastic angular distributions 525 1451 203 thres. to 20 mev, assumed isotropic in center of mass 525 1451 204 525 1451 205 525 1451 206 mf=12 -------- gamma ray multiplicities ------------------------ 525 1451 207 525 1451 208 mt=102 capture gamma rays 525 1451 209 0 to 20 mev, capture spectra and transition probabilities 525 1451 210 derived from the thermal data of th67, after slight 525 1451 211 changes in the probabilities and renormalization to the 525 1451 212 energy levels of aj75. the lp flag is used to conserve 525 1451 213 energy and to reduce significantly the amount of data 525 1451 214 required in the file. except for the modification due 525 1451 215 to the lp flag, the thermal spectrum is used over the 525 1451 216 entire energy range. 525 1451 217 525 1451 218 mt=801 0.4776-mev photon from the (n,alpha1) reaction 525 1451 219 0 to 20 mev, multiplicity of 1.0 at all energies 525 1451 220 525 1451 221 525 1451 222 mf=13 -------- gamma-ray production cross sections ------------- 525 1451 223 525 1451 224 mt=4 (n,ngamma) cross section 525 1451 225 thres. to 20 mev, obtained from mt=51-60 using b-10 decay 525 1451 226 scheme obtained from aj88. 525 1451 227 525 1451 228 mt=103 (n,pgamma) cross sections 525 1451 229 thres. to 20 mev, obtained from mt=601-605 using be-10 525 1451 230 decay scheme deduced from aj88. 525 1451 231 525 1451 232 525 1451 233 mf=14 -------- gamma ray angular distributions ----------------- 525 1451 234 525 1451 235 mt=4 (n,ngamma) angular distributions 525 1451 236 thres. to 20 mev, assumed isotropic 525 1451 237 525 1451 238 mt=102 (n,gamma) angular distributions 525 1451 239 0 to 20 mev, assumed isotropic. 525 1451 240 525 1451 241 mt=103 (n,pgamma) angular distributions 525 1451 242 thres. to 20 mev, assumed isotropic 525 1451 243 525 1451 244 mt=801 (n,alpha1/gamma) angular distribution 525 1451 245 0 to 20 mev, assumed isotropic 525 1451 246 525 1451 247 525 1451 248 ----------------------- references ----------------------------- 525 1451 249 525 1451 250 aj75 f. ajzenberg-selove, nucl. phys. a248,6 (1975) 525 1451 251 aj88 f. ajzenberg-selove, nucl. phys. a490,1 (1988) 525 1451 252 an69 B. Antolkovic, Nuc.Phys.A139, 10 (1969). 525 1451 253 as70 a. asami and m.c. moxon, j.nucl.energy 24,85 (1970) 525 1451 254 au79 g.auchampaugh et al., nucl.sci.eng.69,30(1979) 525 1451 255 ba60 r.bardes and g.e. owen, phys.rev.120,1369 (1960) 525 1451 256 be56 r.l. becker and h.h. barschall, phys.rev.102,1384 (1956) 525 1451 257 bo51 c.k.bockelman et al., phys.rev. 84,69 (1951) 525 1451 258 bo69 d.bogart and l.l.nichols, nucl.phys.a125,463 (1969) 525 1451 259 ca85 a.carlson et al., nuc.data for basic & applied science, 525 1451 260 santa fe, nm (1985) p.1429. 525 1451 261 co52 j.h.coon et al., phys.rev. 88,562 (1952) 525 1451 262 co54 c.f.cook and t.w. bonner,phys.rev. 94,651 (1954) 525 1451 263 co67 s.a. cox and f.r. pontet, j.nucl.energy 21,271 (1967) 525 1451 264 co69 j.a. cookson and j.g.locke,nucl.phys.a146,417(1970) 525 1451 265 co73 m.s. coates et al., priv. comm. to l.stewart (1973) 525 1451 266 da56 r.b.day,phys.rev.102,767 (1956) 525 1451 267 da60 r.b. day and m.walt,phys.rev.117,1330 (1960) 525 1451 268 da61 e.a. davis et al., nucl.phys.27,448 (1961) 525 1451 269 di67 k.m. diment, aere-r-5224 (1967) 525 1451 270 di88 j.k.dickens, proc.conf. on nuc.data for sci.& tech.,mito, 525 1451 271 japan (1988) p.213. 525 1451 272 fo61 d.m. fossan et al., phys.rev. 123,209 (1961) 525 1451 273 fr56 g.m. frye and j.h. gammel,phys.rev. 103,328 (1956) 525 1451 274 gl82 s.glendinning, nuc.sci.eng.80,256(1982) 525 1451 275 ha73 s.l.hausladen, thesis, ohio univ. coo-1717-5 (1973) 525 1451 276 he80 d.hetrick & c.y.fu, ornl/tm-7341 (1980). 525 1451 277 hy69 m.hyakutake, eandc(j)-13 (1969) p.29 525 1451 278 ho69 j.c. hopkins, priv. comm. lasl (1969) 525 1451 279 ir67 d.c.irving, ornl-tm-1872 (1967) 525 1451 280 ka87 R.Kavanagh & R.Marcley, Phys.Rev.C36, 1194 (1987). 525 1451 281 la71 r.o. lane et al., phys.rev.c4,380 (1971) 525 1451 282 ma68 r.l.macklin and j.h.gibbons,phys.rev.165,1147 (1968) 525 1451 283 mo66 f.p.mooring et al.,nucl.phys.82,16 (1966) 525 1451 284 ne54 n.g.nereson,la-1655 (1954) 525 1451 285 ne70 d.o.nellis et al., phys.rev. c1,847 (1970) 525 1451 286 po70 d.porter et al., awre o 45/70 (1970) 525 1451 287 qa85 S.Qaim et al., Santa Fe Conf. (1985)p.97. 525 1451 288 qa88 S.Qaim et al., Mito Conf. (1988) p.225. 525 1451 289 sa88 E.T. Sadowski, Ph.D thesis, Ohio U., (Nov.,1988). 525 1451 290 sc76 r.a. schrack et al., proc.icinn(erda-conf-760715-p2),1345 525 1451 291 (1976) 525 1451 292 se76 r.m. sealock and j.c. overley, phys.rev.c13,2149 (1976) 525 1451 293 si65 r.h.siemssen et al., nucl.phys.69,209 (1965) 525 1451 294 sp73 r.r. spencer et al., eandc(e)147,al (1973) 525 1451 295 te62 k.tesch, nucl.phys.37,412 (1962) 525 1451 296 th67 g.e. thomas et al., nucl.instr.meth.56,325 (1967) 525 1451 297 ts63 k.tsukada and o.tanaka,j.phys.soc.japan 18,610 (1963) 525 1451 298 va65 v.valkovic et al., phys.rev. 139,331 (1965) 525 1451 299 va70 b.vaucher et al.,helv.phys.acta 43,237 (1970) 525 1451 300 va72 l.van der zwan and k.w.geiger, nucl.phys. a180,615 (1972) 525 1451 301 wi55 h.b. willard et al., phys.rev. 98,669(1955) 525 1451 302 wy58 m.e. wyman et al., phys.rev.112,1264 (1958) 525 1451 303 525 1451 304 525 1451 305 1 451 308 1 525 1451 306 3 103 35 1 525 1451 307 3 107 61 1 525 1451 308 525 1 0 309 525 0 0 310 5.010000+3 9.926921+0 0 0 0 0 525 3103 311 2.262410+5 2.262410+5 0 0 2 94 525 3103 312 5 5 94 2 0 0 525 3103 313 1.000000-5 2.845000-2 2.530000-2 5.660000-4 1.000000+0 9.000000-5 525 3103 314 1.000000+3 2.920000-6 5.100000+4 1.370000-6 1.000000+5 2.520000-6 525 3103 315 2.000000+5 7.980000-6 4.000000+5 4.370000-5 6.000000+5 1.490000-4 525 3103 316 8.000000+5 4.020000-4 1.000000+6 9.530000-4 1.200000+6 2.140000-3 525 3103 317 1.300000+6 3.293458-3 1.400000+6 4.650000-3 1.500000+6 5.754682-3 525 3103 318 1.550000+6 6.353862-3 1.600000+6 7.000000-3 1.700000+6 8.453875-3 525 3103 319 1.800000+6 1.011480-2 2.000000+6 1.400000-2 2.200000+6 1.728422-2 525 3103 320 2.400000+6 1.879142-2 2.600000+6 1.906461-2 2.800000+6 1.874185-2 525 3103 321 3.000000+6 1.830000-2 3.200000+6 1.792865-2 3.400000+6 1.757205-2 525 3103 322 3.458281+6 1.747323-2 3.600000+6 1.748217-2 3.700000+6 1.748149-2 525 3103 323 3.800000+6 1.772722-2 3.900000+6 1.839205-2 4.000000+6 1.928000-2 525 3103 324 4.200000+6 2.161979-2 4.400000+6 2.431697-2 4.600000+6 2.647751-2 525 3103 325 4.800000+6 2.785689-2 5.000000+6 2.881487-2 5.200000+6 2.913396-2 525 3103 326 5.400000+6 2.930610-2 5.600000+6 2.937958-2 5.800000+6 2.934495-2 525 3103 327 6.000000+6 2.928000-2 6.200000+6 2.917415-2 6.300000+6 2.910464-2 525 3103 328 6.309584+6 2.909838-2 6.311246+6 2.909755-2 6.400000+6 2.905993-2 525 3103 329 6.500000+6 2.901114-2 6.552747+6 2.899022-2 6.600000+6 2.897026-2 525 3103 330 6.645209+6 2.895127-2 6.700000+6 2.897518-2 6.800000+6 2.897716-2 525 3103 331 6.900000+6 2.903755-2 7.000000+6 2.914815-2 7.100000+6 2.915411-2 525 3103 332 7.200000+6 2.950712-2 7.300000+6 3.051271-2 7.400000+6 3.222840-2 525 3103 333 7.500000+6 3.436774-2 7.600000+6 3.668446-2 7.800000+6 4.151681-2 525 3103 334 8.000000+6 4.560800-2 8.200000+6 4.733367-2 8.400000+6 4.816578-2 525 3103 335 8.600000+6 4.861492-2 8.800000+6 4.881710-2 9.000000+6 4.889150-2 525 3103 336 9.200000+6 4.881504-2 9.400000+6 4.862432-2 9.600000+6 4.833812-2 525 3103 337 9.800000+6 4.798500-2 1.000000+7 4.756536-2 1.050000+7 4.629352-2 525 3103 338 1.100000+7 4.494420-2 1.150000+7 4.319474-2 1.200000+7 4.144371-2 525 3103 339 1.250000+7 3.969315-2 1.300000+7 3.794343-2 1.350000+7 3.619249-2 525 3103 340 1.400000+7 3.444315-2 1.450000+7 3.269221-2 1.500000+7 3.094245-2 525 3103 341 1.550000+7 2.912206-2 1.600000+7 2.731129-2 1.650000+7 2.550732-2 525 3103 342 1.700000+7 2.371346-2 1.750000+7 2.192561-2 1.800000+7 2.014907-2 525 3103 343 1.850000+7 1.838100-2 1.900000+7 1.661781-2 1.950000+7 1.486100-2 525 3103 344 2.000000+7 1.312000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+0 525 3103 345 525 3 0 346 5.010000+3 9.926921+0 0 0 0 0 525 3107 347 2.790000+6 2.790000+6 0 0 2 174 525 3107 348 120 5 174 2 0 0 525 3107 349 1.000000-5 1.931800+5 2.530000-2 3.839496+3 9.400000+0 1.989352+2 525 3107 350 1.500000+2 4.961720+1 2.500000+2 3.837760+1 3.500000+2 3.240060+1 525 3107 351 4.500000+2 2.854440+1 5.500000+2 2.579550+1 6.500000+2 2.371760+1 525 3107 352 7.500000+2 2.206610+1 8.500000+2 2.071300+1 9.500000+2 1.957360+1 525 3107 353 1.500000+3 1.553510+1 2.500000+3 1.198710+1 3.500000+3 1.010500+1 525 3107 354 4.500000+3 8.892400+0 5.500000+3 8.028200+0 6.500000+3 7.374000+0 525 3107 355 7.500000+3 6.855100+0 8.500000+3 6.432100+0 9.500000+3 6.078500+0 525 3107 356 1.500000+4 4.821100+0 2.000000+4 4.170300+0 2.400000+4 3.807200+0 525 3107 357 3.000000+4 3.410700+0 4.500000+4 2.808100+0 5.500000+4 2.560500+0 525 3107 358 6.500000+4 2.377500+0 7.500000+4 2.235400+0 8.500000+4 2.121200+0 525 3107 359 9.500000+4 2.027500+0 1.000000+5 1.985100+0 1.200000+5 1.844300+0 525 3107 360 1.500000+5 1.674700+0 1.700000+5 1.572900+0 1.800000+5 1.524800+0 525 3107 361 1.900000+5 1.477400+0 2.000000+5 1.431400+0 2.100000+5 1.385600+0 525 3107 362 2.200000+5 1.341100+0 2.300000+5 1.298200+0 2.350000+5 1.277600+0 525 3107 363 2.400000+5 1.256500+0 2.450000+5 1.236500+0 2.500000+5 1.216800+0 525 3107 364 2.600000+5 1.178100+0 2.700000+5 1.140800+0 2.800000+5 1.105300+0 525 3107 365 3.000000+5 1.037340+0 3.200000+5 9.780500-1 3.400000+5 9.279900-1 525 3107 366 3.600000+5 8.892600-1 3.800000+5 8.630200-1 4.000000+5 8.490400-1 525 3107 367 4.200000+5 8.452800-1 4.400000+5 8.464200-1 4.600000+5 8.438100-1 525 3107 368 4.800000+5 8.287000-1 5.000000+5 7.971800-1 5.200000+5 7.520500-1 525 3107 369 5.400000+5 6.998100-1 5.600000+5 6.466400-1 5.800000+5 5.964400-1 525 3107 370 6.000000+5 5.509900-1 6.500000+5 4.592600-1 7.000000+5 3.929700-1 525 3107 371 7.500000+5 3.441300-1 8.000000+5 3.071500-1 8.500000+5 2.784700-1 525 3107 372 9.000000+5 2.558200-1 9.500000+5 2.376900-1 1.000000+6 2.230560-1 525 3107 373 1.050000+6 2.139881-1 1.100000+6 2.107045-1 1.150000+6 2.113211-1 525 3107 374 1.200000+6 2.145886-1 1.250000+6 2.196000-1 1.300000+6 2.273315-1 525 3107 375 1.350000+6 2.388980-1 1.400000+6 2.538785-1 1.450000+6 2.719450-1 525 3107 376 1.500000+6 2.928000-1 1.550000+6 3.248122-1 1.600000+6 3.721273-1 525 3107 377 1.650000+6 4.273298-1 1.700000+6 4.798547-1 1.750000+6 5.165000-1 525 3107 378 1.800000+6 5.262540-1 1.850000+6 5.215069-1 1.900000+6 5.060907-1 525 3107 379 1.950000+6 4.847658-1 2.000000+6 4.596000-1 2.050000+6 4.280959-1 525 3107 380 2.100000+6 3.958590-1 2.150000+6 3.647927-1 2.200000+6 3.384507-1 525 3107 381 2.250000+6 3.194910-1 2.300000+6 3.052108-1 2.350000+6 2.938520-1 525 3107 382 2.400000+6 2.849606-1 2.450000+6 2.810818-1 2.500000+6 2.878578-1 525 3107 383 2.550000+6 3.034110-1 2.600000+6 3.200000-1 2.650000+6 3.357468-1 525 3107 384 2.700000+6 3.518343-1 2.750000+6 3.815892-1 2.800000+6 4.000000-1 525 3107 385 2.850000+6 3.847509-1 2.900000+6 3.650000-1 2.950000+6 3.468235-1 525 3107 386 3.000000+6 3.300000-1 3.050000+6 3.154825-1 3.100000+6 3.032678-1 525 3107 387 3.150000+6 2.912017-1 3.200000+6 2.820000-1 3.300000+6 2.821814-1 525 3107 388 3.400000+6 2.960000-1 3.600000+6 3.300000-1 3.700000+6 3.474155-1 525 3107 389 3.800000+6 3.650000-1 4.000000+6 3.500000-1 4.200000+6 2.745479-1 525 3107 390 4.300000+6 2.606951-1 4.400000+6 2.450000-1 4.600000+6 2.000000-1 525 3107 391 4.800000+6 1.712930-1 5.000000+6 1.478000-1 5.200000+6 1.318452-1 525 3107 392 5.400000+6 1.161278-1 5.500000+6 1.124321-1 5.600000+6 1.121000-1 525 3107 393 5.800000+6 1.147314-1 6.000000+6 1.165057-1 6.200000+6 1.181696-1 525 3107 394 6.400000+6 1.183391-1 6.600000+6 1.171288-1 6.800000+6 1.148436-1 525 3107 395 7.000000+6 1.104512-1 7.200000+6 1.041907-1 7.400000+6 9.738018-2 525 3107 396 7.600000+6 9.071085-2 7.800000+6 8.463679-2 8.000000+6 7.942750-2 525 3107 397 8.200000+6 7.465784-2 8.400000+6 7.052106-2 8.600000+6 6.689338-2 525 3107 398 8.800000+6 6.367160-2 9.000000+6 6.076367-2 9.200000+6 5.812695-2 525 3107 399 9.400000+6 5.577225-2 9.600000+6 5.369136-2 9.800000+6 5.187475-2 525 3107 400 1.000000+7 5.031229-2 1.050000+7 4.658572-2 1.100000+7 4.403554-2 525 3107 401 1.150000+7 4.218219-2 1.200000+7 4.126500-2 1.250000+7 4.130563-2 525 3107 402 1.300000+7 4.198975-2 1.350000+7 4.319183-2 1.400000+7 4.437300-2 525 3107 403 1.450000+7 4.490981-2 1.500000+7 4.459223-2 1.550000+7 4.317406-2 525 3107 404 1.600000+7 4.164776-2 1.650000+7 4.015499-2 1.700000+7 3.870001-2 525 3107 405 1.750000+7 3.722898-2 1.800000+7 3.576560-2 1.850000+7 3.430929-2 525 3107 406 1.900000+7 3.285713-2 1.950000+7 3.141235-2 2.000000+7 2.998125-2 525 3107 407 525 3 0 408 525 0 0 409 0 0 0 410 5.011000+3 1.091470+1 -1 0 0 1 528 1451 1 0.000000+0 0.000000+0 0 0 0 6 528 1451 2 1.000000+0 0.000000+0 0 0 10 6 528 1451 3 0.000000+0 0.000000+0 0 0 185 2 528 1451 4 5-B - 11 LANL EVAL-MAY89 P.G.YOUNG 528 1451 5 DIST-JAN90 900123 528 1451 6 ----ENDF/B-VI MATERIAL 528 528 1451 7 -----INCIDENT NEUTRON DATA 528 1451 8 ------ENDF-6 FORMAT 528 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 528 1451 10 ACTIVATION I 528 1451 11 ****************************************************************** 528 1451 12 FILE INFORMATION 528 1451 13 528 1451 14 *********** GENERAL DESCRIPTION ********************************* 528 1451 15 528 1451 16 this evaluation is a synthesis of experimental results and 528 1451 17 theoretical calculations using the gnash hauser-feshbach, stat. 528 1451 18 theory code gnash (ar88, yo77). it replaces a pre-1970 u.k. 528 1451 19 evaluation that was adapted for endf/b in 1971 (co79). major 528 1451 20 emphasis was placed on experimental data where possible, usually 528 1451 21 using the calculations to estimate shapes and exp. data to 528 1451 22 normalize the calculations. spherical optical model calculations 528 1451 23 were used to obtain particle transmission coefficients, using 528 1451 24 global potentials for protons and alphas, and the work of dave 528 1451 25 et al.(da83) for the neutron potential. gilbert-cameron level 528 1451 26 density parameters were used and preequilibrium corrections 528 1451 27 from an exciton model were included. in general, the calculations 528 1451 28 were required for the gamma and particle emission spectra from 528 1451 29 charged-particle reactions, as well as for inelastic neutron 528 1451 30 and gamma emission above the third excited state of b11, and 528 1451 31 for all states above an incident neutron energy of about 8 mev. 528 1451 32 528 1451 33 *********** mf=2 resonance parameters *************************** 528 1451 34 528 1451 35 mt=151 scattering radius only. 528 1451 36 528 1451 37 *********** mf=3 thermal cross sections************************** 528 1451 38 528 1451 39 the 1981 evaluation by mughabghab (mu81) was used for 528 1451 40 the 2200 m/s cross sections, as follows: 528 1451 41 mt = 1 sigma = 4.8455 b 528 1451 42 mt = 2 sigma = 4.8400 b 528 1451 43 mt =102 sigma = 0.0055 b 528 1451 44 528 1451 45 *********** mf=3 smooth neutron cross sections ****************** 528 1451 46 528 1451 47 mt= 1 Total Cross Section. At low energies, evaluation by Mu81a 528 1451 48 of thermal data used. At higher energies exp. data of 528 1451 49 Mo66, La70, Ca73, Au79, Co52 & Co54 were used. The high 528 1451 50 resolution data of Au79 were emphasized. Optical model 528 1451 51 calculations with the Da83 potential used to define shape 528 1451 52 above 14 MeV. 528 1451 53 mt= 2 Elastic Cross Section. Based on exp. data of La70, 528 1451 54 Wi55, Po70, Ne73, Wh80, Ko82, Ho69, Gl82, Co70 & Al69. 528 1451 55 Optical model calculations with potential of Da83 528 1451 56 used with renormalization above 14 MeV. Thermal eval. 528 1451 57 of Mu81a used at low energies. 528 1451 58 mt= 4 (n,nprime)gamma+(n,nprime)continuum. sum of mt=51-60,91. 528 1451 59 mt= 16 (n,2n) Cross Section. Based entirely on GNASH analysis. 528 1451 60 mt= 22 (n,na) Cross Section. Based entirely on GNASH analysis. 528 1451 61 mt= 28 (n,np) Cross Section. Based entirely on GNASH analysis. 528 1451 62 mt=51-54 (n,n'gamma) Cross Sections. Based on exp. data of 528 1451 63 Au86, Gl82, Ho69, Po70, Co70, Ko82, Ba85. The Au86 data 528 1451 64 shapes were used to establish low energy behavior. 528 1451 65 mt=55-60 (n,n'gamma) Cross Sections. Shapes of excitation 528 1451 66 curves calculated with GNASH. Absolute magnitudes obtain- 528 1451 67 ed by renormalizing such that sum of all partials gave 528 1451 68 reaction, elastic, total x/s consistent with avail. data. 528 1451 69 mt= 91 (n,n'continuum) Cross Section. Based on GNASH calculation 528 1451 70 entirely. 528 1451 71 mt=102 (n,gamma) Cross Section. adopted from endf/b-v.1 except 528 1451 72 thermal cross section of Mu81a used. 528 1451 73 mt=103 (n,p) Cross Section. Based on GNASH calculation and exp. 528 1451 74 data of Sc70a,Fl67, St65, etc. 528 1451 75 mt=105 (n,t) Cross Section. Similar to endf/b-v data, with a 528 1451 76 smooth curve passing thru exp. data of Wy58 at 14.1 MeV. 528 1451 77 mt=107 (n,alpha) Cross Section. Based on GNASH calculation and 528 1451 78 exp. data (An79, Sc70b,Ar56). 528 1451 79 528 1451 80 *********** mf=4 neutron angular distributions ****************** 528 1451 81 528 1451 82 mt= 2 legendre coefficients obtained by drawing smooth curve 528 1451 83 through fitted coefficients from measurements listed 528 1451 84 under mf3/mt2. data of La60,Gl79,Wh80,Ne73,Ho69,Hy74 528 1451 85 emphasized. optical model calculations used above 14 mev. 528 1451 86 mt=51-54 Legendre coefficients obtained by fitting exp.data, 528 1451 87 especially Al69, Hy74, Po70, Ho69, Gl79 & Co69. Smooth 528 1451 88 curves then passed through fitted coefficients. 528 1451 89 mt=55-60 Isotropy assumed. 528 1451 90 528 1451 91 *********** mf=6 energy-angle correlated distributions ********** 528 1451 92 528 1451 93 mt= 16 Neutron and photon distributions are given based on 528 1451 94 GNASH calculations described above to obtain spectra 528 1451 95 and multiplicities. Kalbach-Mann (Ka81) systematics (KMS) 528 1451 96 used for neutron angular distributions. Photon distri- 528 1451 97 butions taken as isotropic. 528 1451 98 mt= 22 Neutron and alpha distributions are based on KMS. 528 1451 99 Photon distributions assumed isotropic. Multiplicities 528 1451 100 and spectra based on GNASH calculations. 528 1451 101 mt= 28 Neutron and proton distributions are based on KMS. 528 1451 102 Photon distributions assumed isotropic. Multiplicities 528 1451 103 and spectra based on GNASH calculations. 528 1451 104 mt= 91 Neutron distributions based on KMS and isotropic photon 528 1451 105 distributions given. Multiplicities and spectra obtained 528 1451 106 from GNASH analysis. 528 1451 107 mt=103 Proton distributions based on KMS and isotropic photon 528 1451 108 distributions given. Multiplicities and spectra obtained 528 1451 109 from GNASH analysis. 528 1451 110 mt=107 Alpha distributions based on KMS and isotropic photon 528 1451 111 distributions given. Multiplicities and spectra obtained 528 1451 112 from GNASH analysis. 528 1451 113 528 1451 114 *********** mf=12 photon multiplicities ************************* 528 1451 115 528 1451 116 mt=102 Radiative Capture Photon Yields obtained from theoretical 528 1451 117 calculations (Mu81) based on Lane-Lynn Theory of Direct 528 1451 118 Capture. 528 1451 119 528 1451 120 *********** mf=13 photon cross sections ************************* 528 1451 121 528 1451 122 mt= 4 gamma ray production cross sections from inelastic scat. 528 1451 123 Obtained using discrete data (MF=3, MT=51-60) and photon 528 1451 124 branching ratios (Aj85). 528 1451 125 528 1451 126 *********** mf=14 photon angular distributions ****************** 528 1451 127 528 1451 128 mt= 51 isotropy assumed at all energies. 528 1451 129 mt=102 isotropy assumed for all gammas at all energies. 528 1451 130 528 1451 131 *********** mf=33 neutron cross section covariances ************* 528 1451 132 528 1451 133 To be provided in the future. 528 1451 134 528 1451 135 *********** references ****************************************** 528 1451 136 528 1451 137 Aj85 F.Ajzenberg-Selove, N.P.A433,1(1985). 528 1451 138 Al69 J.Alder et al., Nuc.Phys.147,657(1969). 528 1451 139 An79 B.Antolkovic et al., Nuc.Phys.A235,189(1979). 528 1451 140 Ar56 A.Armstrong et al., Phys.Rev.103,335(1956). 528 1451 141 Ar88 E.Arthur, ICTP Workshop, Trieste (1988) [LA-UR 88-1753]. 528 1451 142 Au79 G.Auchampaugh et al., NSE 69,30(1979). 528 1451 143 Au86 G.Auchampaugh & S.Wender, personal communcation (1986). 528 1451 144 Ba85 M.Baba et al., Santa Fe Nuc.Data Conf. (1985)p.223. 528 1451 145 Ca73 J.Cabe et al., CEA-R-4524 (1973). 528 1451 146 Co52 J.Coon, PR 88,562(1952). 528 1451 147 Co54 C.Cook & T.Bonner, PR 94,651(1954). 528 1451 148 Co70 J.Cookson et al., NP A146,417(1970). 528 1451 149 Co79 C.Cowan, Summary Documentation ENDF/B-V, ENDF-201 (1979). 528 1451 150 Da83 J.Dave & C.Gould, Phys.Rev. C28, 2212(1983). 528 1451 151 Fl67 F.Flesch et al., OAW 176, 45(1967). 528 1451 152 Gl82 S.Glendinning et al., NSE 80,256(1982). 528 1451 153 Ho69 J.Hopkins et al., NSE 36,275(1969). 528 1451 154 Hy74 M.Hyakutake et al., J.Nuc.Sci.Tech. 11,407(1974). 528 1451 155 Ka81 C.Kalbach & F.Mann, P.R.C23,112(1981). 528 1451 156 Ko83 P.Koehler et al., NP A294,221(1983). 528 1451 157 La70 R.Lane et al., PR C2,2097(1970). 528 1451 158 Mo66 F.Mooring et al., NP 82,16(1966). 528 1451 159 Mu81a S.F.Mughabghab et al., Neutron Res.Parameters and 528 1451 160 Thermal Cross Sect., Academic Press (1981) v1. 528 1451 161 Mu81b S.F.Mughabghab, Proc.Conf.on Nuc.Data Eval.Meth. & Proc. 528 1451 162 BNL-NCS-51363 (1981),V1,p.339. 528 1451 163 Ne73 C.Nelson et al., COO-1717-8 (1973). 528 1451 164 Po70 D.Porter et al., AWRE-O-45-70 (1970). 528 1451 165 Sc70a Schantl, personal communication to NNDC (1970). 528 1451 166 Sc70b W.Scobel et al., ZN A25,1406,(1970). 528 1451 167 St65 J.Strain et al., ORNL-3672 (1965). 528 1451 168 Wh80 R.M.White et al., NP A340,13(1980). 528 1451 169 Wi55 H.Willard et al., PR 98,669(1955). 528 1451 170 Wy58 M.Wyman, PR 112,1264(1958). 528 1451 171 Yo77 P.Young & E.Arthur,LA-6947 (1977). 528 1451 172 528 1451 173 ***************************************************************** 528 1451 174 ***************** PROGRAM LINEAR (VERSION 89-1) ***************** 528 1451 175 DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.300 PER-CENT 528 1451 176 ***************** PROGRAM FIXUP (VERSION 89-2) ****************** 528 1451 177 *RECONSTRUCTED MT NUMBERS 528 1451 178 4 =+( 50, 91) 528 1451 179 103 =+(600,649) 528 1451 180 104 =+(650,699) 528 1451 181 105 =+(700,749) 528 1451 182 106 =+(750,799) 528 1451 183 107 =+(800,849) 528 1451 184 101 =+( 18, 18)+(102,116) 528 1451 185 27 =+(101,101) 528 1451 186 3 =+( 4, 5)+( 16, 17)+( 22, 37)+( 41, 42) 528 1451 187 19 =+( 18, 18)-( 20, 21)-( 38, 38) 528 1451 188 1 =+( 2, 3) 528 1451 189 1 451 191 1 528 1451 190 3 107 84 1 528 1451 191 528 1 0 192 528 0 0 193 5.011000+3 1.091470+1 0 99 0 0 528 3107 194 -6.630950+6-6.630950+6 0 0 1 243 528 3107 195 243 2 0 0 0 0 528 3107 196 7.238500+6 0.000000+0 7.300000+6 1.12483-11 7.303104+6 1.26649-11 528 3107 197 7.306113+6 1.42071-11 7.309029+6 1.58800-11 7.311855+6 1.76883-11 528 3107 198 7.314593+6 1.96361-11 7.317247+6 2.17274-11 7.319819+6 2.39656-11 528 3107 199 7.322312+6 2.63534-11 7.324727+6 2.88932-11 7.327068+6 3.15869-11 528 3107 200 7.329336+6 3.44356-11 7.331534+6 3.74401-11 7.333664+6 4.06005-11 528 3107 201 7.335728+6 4.39163-11 7.339728+6 5.11309-11 7.343481+6 5.89674-11 528 3107 202 7.347001+6 6.74016-11 7.350302+6 7.64012-11 7.353398+6 8.59267-11 528 3107 203 7.356302+6 9.59327-11 7.359026+6 1.06369-10 7.361580+6 1.17182-10 528 3107 204 7.363975+6 1.28315-10 7.366222+6 1.39712-10 7.368328+6 1.51313-10 528 3107 205 7.372280+6 1.75726-10 7.375739+6 2.00297-10 7.378767+6 2.24599-10 528 3107 206 7.381418+6 2.48271-10 7.383738+6 2.71021-10 7.387800+6 3.15965-10 528 3107 207 7.390848+6 3.54499-10 7.393135+6 3.86454-10 7.396567+6 4.39867-10 528 3107 208 7.400000+6 5.00663-10 7.403104+6 5.58923-10 7.406113+6 6.21819-10 528 3107 209 7.409030+6 6.89492-10 7.411856+6 7.62065-10 7.414594+6 8.39648-10 528 3107 210 7.417248+6 9.22330-10 7.419821+6 1.010180-9 7.422313+6 1.103270-9 528 3107 211 7.424729+6 1.201610-9 7.427069+6 1.305230-9 7.429338+6 1.414130-9 528 3107 212 7.431536+6 1.528280-9 7.435796+6 1.776340-9 7.439793+6 2.045330-9 528 3107 213 7.443542+6 2.334400-9 7.447058+6 2.642400-9 7.450356+6 2.967960-9 528 3107 214 7.453449+6 3.309510-9 7.456350+6 3.665330-9 7.459070+6 4.033570-9 528 3107 215 7.461622+6 4.412330-9 7.464015+6 4.799660-9 7.466259+6 5.193610-9 528 3107 216 7.470468+6 6.021490-9 7.474153+6 6.853450-9 7.477379+6 7.675190-9 528 3107 217 7.480203+6 8.474640-9 7.482675+6 9.242180-9 7.487002+6 1.075640-8 528 3107 218 7.490249+6 1.205280-8 7.492686+6 1.312660-8 7.496342+6 1.491930-8 528 3107 219 7.500000+6 1.695690-8 7.503105+6 1.870670-8 7.506114+6 2.057380-8 528 3107 220 7.509030+6 2.256000-8 7.511856+6 2.466690-8 7.514595+6 2.689540-8 528 3107 221 7.517250+6 2.924610-8 7.519822+6 3.171910-8 7.522315+6 3.431400-8 528 3107 222 7.527147+6 3.996120-8 7.531679+6 4.609670-8 7.535931+6 5.270170-8 528 3107 223 7.539920+6 5.975090-8 7.543661+6 6.721360-8 7.547170+6 7.505420-8 528 3107 224 7.550461+6 8.323350-8 7.553548+6 9.170930-8 7.556442+6 1.004380-7 528 3107 225 7.559157+6 1.093730-7 7.561704+6 1.184720-7 7.566480+6 1.376200-7 528 3107 226 7.570662+6 1.568960-7 7.574323+6 1.759660-7 7.577528+6 1.945440-7 528 3107 227 7.580333+6 2.124020-7 7.585245+6 2.476880-7 7.588931+6 2.779490-7 528 3107 228 7.591697+6 3.030470-7 7.595847+6 3.450060-7 7.600000+6 3.927750-7 528 3107 229 7.603105+6 4.268810-7 7.606114+6 4.627420-7 7.609031+6 5.003540-7 528 3107 230 7.614685+6 5.821450-7 7.619989+6 6.709280-7 7.624965+6 7.664220-7 528 3107 231 7.629634+6 8.682570-7 7.634013+6 9.759819-7 7.638120+6 1.089080-6 528 3107 232 7.641973+6 1.206990-6 7.645587+6 1.329100-6 7.648976+6 1.454770-6 528 3107 233 7.652155+6 1.583360-6 7.655137+6 1.714210-6 7.660730+6 1.989410-6 528 3107 234 7.665628+6 2.266220-6 7.669916+6 2.539850-6 7.673670+6 2.806250-6 528 3107 235 7.676956+6 3.062160-6 7.682711+6 3.567450-6 7.687029+6 4.000420-6 528 3107 236 7.690270+6 4.359300-6 7.695133+6 4.958860-6 7.700000+6 5.640900-6 528 3107 237 7.706212+6 6.430640-6 7.712041+6 7.271150-6 7.717509+6 8.158650-6 528 3107 238 7.722639+6 9.088820-6 7.727451+6 1.005690-5 7.731966+6 1.105800-5 528 3107 239 7.736200+6 1.208680-5 7.740173+6 1.313810-5 7.743898+6 1.420660-5 528 3107 240 7.750889+6 1.644970-5 7.757011+6 1.870120-5 7.762371+6 2.092260-5 528 3107 241 7.767065+6 2.308180-5 7.771174+6 2.515310-5 7.778371+6 2.923510-5 528 3107 242 7.783772+6 3.272570-5 7.787826+6 3.561460-5 7.793910+6 4.043300-5 528 3107 243 7.800000+6 4.590330-5 7.806213+6 5.024420-5 7.812041+6 5.468600-5 528 3107 244 7.817510+6 5.920610-5 7.827774+6 6.871260-5 7.836766+6 7.827490-5 528 3107 245 7.844642+6 8.772750-5 7.851541+6 9.693020-5 7.857582+6 1.057710-4 528 3107 246 7.868165+6 1.232270-4 7.876112+6 1.381850-4 7.882077+6 1.505840-4 528 3107 247 7.891033+6 1.712980-4 7.900000+6 1.948610-4 7.912431+6 2.131900-4 528 3107 248 7.923325+6 2.306370-4 7.942424+6 2.646740-4 7.956779+6 2.934600-4 528 3107 249 7.978360+6 3.426130-4 8.000000+6 4.000000-4 8.024883+6 4.334330-4 528 3107 250 8.062354+6 4.888930-4 8.100000+6 5.514500-4 8.149846+6 6.404610-4 528 3107 251 8.200000+6 7.438390-4 8.249848+6 8.548130-4 8.300000+6 9.823421-4 528 3107 252 8.349850+6 1.117370-3 8.400000+6 1.270950-3 8.449852+6 1.431310-3 528 3107 253 8.500000+6 1.611910-3 8.549854+6 1.797810-3 8.600000+6 2.005150-3 528 3107 254 8.649855+6 2.215490-3 8.700000+6 2.447900-3 8.749857+6 2.680110-3 528 3107 255 8.800000+6 2.934360-3 8.849859+6 3.184350-3 8.900000+6 3.455650-3 528 3107 256 9.000000+6 4.000000-3 9.100000+6 4.599950-3 9.200000+6 5.299140-3 528 3107 257 9.300000+6 6.096940-3 9.400000+6 6.986370-3 9.500000+6 7.952110-3 528 3107 258 9.600000+6 8.968760-3 9.700000+6 1.000000-2 9.800000+6 1.107940-2 528 3107 259 9.900000+6 1.226870-2 1.000000+7 1.356230-2 1.009951+7 1.492150-2 528 3107 260 1.020000+7 1.641680-2 1.029952+7 1.788920-2 1.040000+7 1.949360-2 528 3107 261 1.060000+7 2.254570-2 1.080000+7 2.523990-2 1.100000+7 2.720000-2 528 3107 262 1.120000+7 2.853180-2 1.140000+7 2.959760-2 1.160000+7 3.042400-2 528 3107 263 1.180000+7 3.104530-2 1.200000+7 3.150000-2 1.220000+7 3.192070-2 528 3107 264 1.240000+7 3.235830-2 1.260000+7 3.273330-2 1.280000+7 3.297030-2 528 3107 265 1.300000+7 3.300000-2 1.320000+7 3.288110-2 1.340000+7 3.271740-2 528 3107 266 1.360000+7 3.251330-2 1.380000+7 3.227280-2 1.400000+7 3.200000-2 528 3107 267 1.420000+7 3.170520-2 1.440000+7 3.139690-2 1.460000+7 3.107600-2 528 3107 268 1.480000+7 3.074340-2 1.500000+7 3.040000-2 1.520000+7 3.002640-2 528 3107 269 1.540000+7 2.960100-2 1.560000+7 2.912190-2 1.580000+7 2.858820-2 528 3107 270 1.600000+7 2.800000-2 1.620000+7 2.736330-2 1.640000+7 2.669090-2 528 3107 271 1.660000+7 2.599260-2 1.680000+7 2.527730-2 1.700000+7 2.455280-2 528 3107 272 1.720000+7 2.382590-2 1.740000+7 2.310260-2 1.760000+7 2.238780-2 528 3107 273 1.780000+7 2.168570-2 1.800000+7 2.100000-2 1.820000+7 2.033260-2 528 3107 274 1.840000+7 1.968270-2 1.860000+7 1.904910-2 1.880000+7 1.843070-2 528 3107 275 1.900000+7 1.782670-2 1.920000+7 1.723630-2 1.940000+7 1.665890-2 528 3107 276 1.960000+7 1.609400-2 1.980000+7 1.554120-2 2.000000+7 1.500000-2 528 3107 277 528 3 0 278 528 0 0 279 0 0 0 280 7.014000+3 1.388278+1 -1 0 0 1 725 1451 1 0.000000+0 0.000000+0 0 0 0 6 725 1451 2 1.000000+0 0.000000+0 0 0 10 6 725 1451 3 0.000000+0 0.000000+0 0 0 289 4 725 1451 4 7- N- 14 LANL EVAL-MAY90 P.YOUNG, G.HALE, M.CHADWICK 725 1451 5 DIST-JUN90 900607 725 1451 6 ----ENDF/B-VI MATERIAL 725 725 1451 7 -----INCIDENT NEUTRON DATA 725 1451 8 ------ENDF-6 FORMAT 725 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 725 1451 10 ACTIVATION I 725 1451 11 ****************************************************************** 725 1451 12 725 1451 13 ---------------------------------------------------------------- 725 1451 14 N-14 FREE ATOM EVALUATION 725 1451 15 ---------------------------------------------------------------- 725 1451 16 725 1451 17 GENERAL COMMENTS: 725 1451 18 725 1451 19 THE ENDF/B-VI DATA FILE FOR N14 IS AN ESSENTIALLY COMPLETE NEW 725 1451 20 EVALUATION. BELOW 2.5 MEV, IT CONSISTS OF AN R-MATRIX ANALYSIS OF 725 1451 21 THE AVAILABLE EXPERIMENTAL TOTAL, ELASTIC, (N,P0), AND (N,A0) 725 1451 22 CROSS SECTIONS AND ANGULAR DISTRIBUTIONS USING THE EDA COUPLED- 725 1451 23 CHANNEL R-MATRIX CODE. AT HIGHER ENERGIES, THE EVALUATION 725 1451 24 IS AN UPDATE OF THE 1972 EVALUATION OF YOUNG AND FOSTER (YO72) 725 1451 25 TO INCLUDE NEW EXPERIMENTAL DATA SINCE THAT TIME. MORE DETAILS 725 1451 26 OF THE EVALUATION ARE INCLUDED BELOW. 725 1451 27 725 1451 28 ******************************** MF=2 ************************* 725 1451 29 725 1451 30 MT=451 NO RESONANCE PARAMETERS. SCATTERING RADIUS =8.86366-13 CM 725 1451 31 725 1451 32 ******************************** MF=3 ************************* 725 1451 33 725 1451 34 THERMAL (2200 M/S) CROSS SECTIONS 725 1451 35 TOTAL 11.7958 B (N,GAMMA) 0.075 B 725 1451 36 ELASTIC 9.8726 B (N,P) 1.8482 B 725 1451 37 NONELASTIC 1.9232 B 725 1451 38 725 1451 39 MT=1 TOTAL CROSS SECTION 725 1451 40 ZERO TO 2.2 MEV, SIGT IS OBTAINED FROM SUM OF ELASTIC,(N,P0), 725 1451 41 (N,A0) CROSS SECTIONS FROM R-MATRIX ANALYSIS, PLUS THE (N,G) 725 1451 42 CROSS SECTION DESCRIBED BELOW. THE COUPLED-CHANNEL R-MATRIX 725 1451 43 ANALYSIS WAS PERFORMED WITH THE EDA CODE, FITTING SIMULTANE- 725 1451 44 OUSLY ALMOST ALL AVAILABLE TOTAL, (N,N), (N,P0), AND (N,A0) 725 1451 45 EXP. DATA. THE MOST IMPORTANT TOTAL CROSS SECTION USED WERE 725 1451 46 ME49, BI59, BI69 AT LOWER ENERGIES, AND CA70, HE70, AND FO71 725 1451 47 AT HIGHER ENERGIES. SIGNIFICANT SHAPE DIFFERENCE FOUND IN 725 1451 48 THE 0.1 - 20 KEV REGION AS COMPARED TO ENDF/B-V. 725 1451 49 2.2 MEV TO 20 MEV, FROM CA70, HE70, AND FO71 USING CA70 ALONE 725 1451 50 AT SHARP RESONANCES. SMOOTHED BY APPROPRIATE FITS, LOG-LOG 725 1451 51 INTERPOLATIONS IS GOOD TO 1.3 PCT TO 0.4 MEV, LINEAR INTER- 725 1451 52 POLATION IS GOOD TO 0.5 PCT FROM 0.4 TO 20 MEV, ABSOLUTE 725 1451 53 ERROR LESS THAN 1 PCT ABOVE 2.2 MEV. MINOR CHANGES MADE IN 725 1451 54 ENDF/V.2 EVALUATION IN CERTAIN REGIONS OF HIGH STRUCTURE. 725 1451 55 MT=2 ELASTIC SCATTERING CROSS SECTION 725 1451 56 ZERO TO 2.2 MEV, BASED UPON R-MATRIX ANALYSIS DESCRIBED 725 1451 57 ABOVE. EXPERIMENTAL ELASTIC ANGULAR DISTRIBUTIONS IN ANALYSIS 725 1451 58 WERE FO55 AND FO66. 725 1451 59 2.2 TO 20 MEV, BASED UPON DATA OF CH61,BA67,ST61,BA63,FO55, 725 1451 60 FO66,PH61,BE66,LU67 AND, ESPECIALLY, CH86,TE85,BA85,PE85, 725 1451 61 PE74 AND NE72. NONELASTIC CROSS SECTIONS WERE ADJUSTED 725 1451 62 SOMEWHAT TO ACHIEVE AGREEMENT WITH ELASTIC DATA. 725 1451 63 MT=4 SUM OF MT=51-82 CROSS SECTIONS. 725 1451 64 MT=16 (N,2N) BASED ON FE60,BR61,BO65,PR60. 30 PER ERROR EST 725 1451 65 MT=51-62 DISCRETE INELASTIC, INCLUDING N,NP DECAY (LR=28) 725 1451 66 THRESHOLD TO 20 MEV. FROM (N,NG) DATA OF DI70, OR69, CL69, 725 1451 67 BU71, NY71, CO68, HA59, BE70, DI73 AND, ESPECIALLY, NE89, 725 1451 68 RO74, NE72 AND AU86, TOGETHER WITH THE (N,N') DATA OF CH86, 725 1451 69 PE74, BA63, BA85, AND TA87. THE LEVEL DECAY SCHEME OF AJ86 725 1451 70 WAS USED TO INTERPRET THE (N,NG) DATA. 725 1451 71 MT=63-82 INELASTIC ASSUMING ENERGY BANDS CENTERED AROUND 725 1451 72 THE EXCITATION ENERGIES CHOSEN. NOTE THAT N,NP (LR=28) AND 725 1451 73 N,NALPHA (LR=22) DECAY ARE INCLUDED AND LABELED. THE CROSS 725 1451 74 SECTIONS ARE ADJUSTED BY DIFFERENCING BETWEEN TOTAL AND 725 1451 75 NONELASTIC. CROSS SECTIONS TO THE BANDS BASED ON HAUSER- 725 1451 76 FESHBACH AND NUCLEAR TEMPERATURE CALCULATIONS. 725 1451 77 MT=102 RADIATIVE CAPTURE 725 1451 78 ZERO TO 0.25 MEV, 1/V FROM 75 MB(+-10PCT) AT THERMAL (JU63). 725 1451 79 0.25 TO 1 MEV, TRANSITION REGION. 725 1451 80 1 TO 20 MEV, DEDUCED FROM N14(P,G)O15 DATA OF KU70,ASSUMING 725 1451 81 CHARGE INDEPENDENCE. ENERGY SCALE ADJUSTED TO MATCH FOOT- 725 1451 82 HILLS OF (P,G) GIANT RESONANCE TO RESONANCE CLUSTERS OB- 725 1451 83 SERVED IN N15 COMPOUND NUCLEUS. 725 1451 84 MT=103 SUM OF MT=700-704 CROSS SECTIONS. 725 1451 85 MT=104 SUM OF MT=720-723 CROSS SECTIONS. 725 1451 86 MT=105 SUM OF MT=740-741 CROSS SECTIONS. 725 1451 87 MT=107 SUM OF MT=780-790 CROSS SECTIONS. 725 1451 88 MT=108 (N,2ALPHA) CROSS SECTION. 725 1451 89 BASED ON LI52,MO67 AND HAUSER-FESHBACH CALCULATION. 725 1451 90 MT=700 (N,P) CROSS SECTION TO C14 GROUND STATE. 725 1451 91 ZERO TO 2.2 MEV, TAKEN FROM COUPLED-CHANNEL R-MATRIX ANALYSIS. 725 1451 92 R-MATRIX ANALYSIS BASED ON JO50,GA59, AND ESP. MO79. 725 1451 93 2.2 TO 13 MEV, BASED MAINLY ON MO79 AND INVERSE REACTION DATA 725 1451 94 OF WO67. 725 1451 95 13 TO 20 MEV, SMOOTH EXTRAPOLATION. 725 1451 96 MT=701-704 (N,P) CROSS SECTIONS TO C14 EXCITED STATES. 725 1451 97 THRES.TO 20 MEV, FROM (N,PG) DATA OF OR69,DI70,CL69,BU71,NY71 725 1451 98 AND RO74. 725 1451 99 MT=720 (N,D) CROSS SECTION TO C13 GROUND STATE. 725 1451 100 THRES.TO 15 MEV, FROM INVERSE CROSS SECTION DATA OF CH61,BE63 725 1451 101 NEAR THRES.AND DIRECT DATA OF MI68,FE67,CA57,ZA63 AT 14MEV 725 1451 102 PLUS THE (N,DG) DATA OF RO74 AND NE89. 725 1451 103 15 TO 20 MEV, SMOOTH EXTRAPOLATIONS. 725 1451 104 MT=721-723 (N,D) CROSS SECTION TO EXCITED C13 LEVELS. 725 1451 105 THRES.TO 20 MEV, DIRECT DATA OF FE67,ZA63,CA57,AND (N,DG) DATA 725 1451 106 OF OR69, DI70, RO74, AND NE89. 725 1451 107 MT=740-741 (N,T) CROSS SECTIONS TO C12 GROUND AND 4.439 MEV EX- 725 1451 108 CITED STATE. 725 1451 109 THRES.TO 15 MEV, DIRECT DATA OF GA59,SC66,RE67,FE67. 725 1451 110 15 TO 20 MEV, SMOOTH EXTRAPOLATIONS. 725 1451 111 MT=780-790 (N,ALPHA) CROSS SECTION TO DISCRETE B11 STATES. 725 1451 112 THRES.TO 2.2 MEV, TAKEN FROM COUPLED-CHANNEL R-MATRIX ANALYSIS. 725 1451 113 DIRECT (N,ALPHA) DATA INCLUDED JO50, GA59, SC66 BUT THE 725 1451 114 ANALYSIS MAINLY RELIED ON MO79. 725 1451 115 6 TO 20 MEV, USED ABOVE DIRECT DATA, TOGETHER WITH (N,AG) DATA 725 1451 116 OF HA59,DI70,OR69,NY71,BU71,BE70,CL68 AND, ESPECIALLY, THE 725 1451 117 DATA OF NE89 AND RO74. NEAR EN=14 MEV, THE DIRECT (N,A) 725 1451 118 DATA OF LI52,BA68,LE68,MA68 WERE ALSO USED. 725 1451 119 725 1451 120 ****************************** MF=4 *************************** 725 1451 121 725 1451 122 MT=2 ELASTIC ANGULAR DISTRIBUTIONS. 725 1451 123 ZERO TO 2.2 MEV, BASED UPON R-MATRIX ANALYSIS DESCRIBED 725 1451 124 ABOVE. EXPERIMENTAL ELASTIC ANGULAR DISTRIBUTIONS IN ANALYSIS 725 1451 125 WERE FO55 AND FO66. 725 1451 126 2.2 TO 20 MEV, BASED UPON DATA OF CH61,BA67,ST61,BA63,FO55, 725 1451 127 FO66,PH61,BE66,LU67 AND, ESPECIALLY, CH86,TE85,BA85,PE85, 725 1451 128 PE74 AND NE72. 725 1451 129 MT=16 ANGULAR DISTRIBUTION FOR (N,2N) REACTION 725 1451 130 IN THE ABSENCE OF DATA, ISOTROPY IN THE CM SYSTEM IS ASSUMED, 725 1451 131 AND THE CORRESPONDING 3-BODY PHASE-SPACE IS TRANSFORMED TO 725 1451 132 THE LAB SYSTEM. FOR ANY REASONABLE CM DISTRIBUTION 725 1451 133 THE STRONG FORWARD PEAKING OF THE TRANSFORMATION WILL 725 1451 134 DOMINATE. NORMALIZED FOR TRAPEZOIDAL INTEGRATION. 725 1451 135 IDENTICAL TO ENDF/B-V. 725 1451 136 MT=51 TO 62 ANGULAR DISTRIBUTIONS FOR INELASTIC SCATTERING 725 1451 137 BASED MAINLY ON (N,N') DATA OF CH86, BUT THE DATA OF PE74, 725 1451 138 TA87, BA63, BO61, AND BA85 WERE USED AS WELL. 725 1451 139 ABOVE 7 MEV ALSO USED PROTON DATA OF DO64, HA70, AND OD60 725 1451 140 ASSUMING CHARGE SYMMETRY, AND NEUTRON DATA OF BA63. 725 1451 141 THRESHOLD SHAPES MODELED AFTER HAUSER-FESHBACH CALCS. 725 1451 142 MT=63-82 ANGULAR DISTRIBUTIONS FOR INELASTIC SCATTERING. 725 1451 143 ASSUMED ISOTROPIC IN CM AT ALL ENERGIES. 725 1451 144 725 1451 145 ****************************** MF=5 *************************** 725 1451 146 725 1451 147 MT=16 SPECTRUM OF (N,2N) SECONDARY NEUTRONS 725 1451 148 IN THE ABSENCE OF DATA, ONLY THE 3-BODY PHASE-SPACE DISTRIBU- 725 1451 149 TION IS GIVEN. NORMALIZED FOR TRAPEZOIDAL INTEGRATION. 725 1451 150 IDENTICAL TO ENDF/B-V. 725 1451 151 725 1451 152 ****************************** MF=12 ************************** 725 1451 153 725 1451 154 MT=102 (N,GAMMA) MULTIPLICITIES (SAME AS ENDF/B-V) 725 1451 155 ZERO TO 0.25 MEV, THERMAL SPECTRUM BASED PRIMARILY UPON MEA- 725 1451 156 SUREMENTS OF TH67,JO69,GR68, AND MO62. 725 1451 157 .25 TO 1 MEV, TRANSITION REGION WHERE THERMAL SPECTRUM IS 725 1451 158 PHASED INTO SINGLE GROUND-STATE TRANSITION. 725 1451 159 1 TO 20 MEV, DEDUCED FROM N14(P,G)O15 DATA OF KU70,WHO OB- 725 1451 160 SERVED NO SIGNIFICANT TRANSITIONS EXCEPT TO GROUND STATE. 725 1451 161 725 1451 162 ****************************** MF=13 ************************** 725 1451 163 725 1451 164 ALL (N,XG) CROSS SECTIONS AGREE WITH THE EXCITATION CROSS 725 1451 165 SECTIONS IN MF=3 VIA THE RELEVANT DECAY SCHEME (AJ80,AJ86). 725 1451 166 725 1451 167 MT=4 (N,NG) CROSS SECTION 725 1451 168 FROM DATA OF HA59,DI70,OR69,CL69,BU71,NY71,CO68,BE70,DI73, &, 725 1451 169 ESPECIALLY, NE89, RO74, NE72, AU86 TOGETHER WITH THE (N,N') 725 1451 170 DATA OF CH86, PE74, BA63, BA85, TA87 AND THE LEVEL DECAY 725 1451 171 SCHEME OF AJ86. 725 1451 172 MT=28 (N,NPG) CROSS SECTION 725 1451 173 FROM DATA OF DI70,OR69,BU71,NY71,CL69,NE89,RO74,NE72,DI73, 725 1451 174 AFTER SUBTRACTION OF MF=13,MT=103 DATA. 725 1451 175 MT=32 (N,NAG) CROSS SECTION 725 1451 176 FROM DATA OF DI70,OR69,BU71,NY71,CL69,NE89,RO74,NE72,DI73, 725 1451 177 AFTER SUBTRACTION OF MF=13,MT=107 DATA. 725 1451 178 MT=103 (N,PG) CROSS SECTION 725 1451 179 FROM DATA OF DI70,OR69,BU71,NY71,CL69,NE89,RO74,NE72,DI73. 725 1451 180 MT=104 (N,DG) CROSS SECTION 725 1451 181 FROM DATA OF DI70,OR69,BU71,NY71,CL69,NE89,RO74,NE72,DI73, 725 1451 182 AND ESTIMATES OF MF=3,MT=651-653. 725 1451 183 MT=105 (N,TG) CROSS SECTION 725 1451 184 (N,TG) ESTIMATED FROM (N,T) AS DISCUSSED UNDER MF=3,MT=741, 725 1451 185 AND FROM (N,XG) DATA (SEE LIST BELOW FOR MT=107). 725 1451 186 MT=107 (N,AG) CROSS SECTION 725 1451 187 FROM (N,A) DATA OF GA59,SC66,MO79 AND (N,AG) DATA OF HA59, 725 1451 188 NY71,OR69,BU71,DI70,DI73,CL68,CO68 AND ESP. NE89,RO74,NE72. 725 1451 189 LEVEL DECAY SCHEME OF AJ80 WAS USED. 725 1451 190 725 1451 191 ****************************** MF=14 ************************** 725 1451 192 725 1451 193 DATA ON 9 STRONGEST LINES FROM INELASTIC SCATT. AND PARTICLE 725 1451 194 REACTIONS TAKEN FROM MO64 -- SAME AS ENDF/B-V. 725 1451 195 MT=4 INEL. SCATT. TO N14, 1.63 AND 4.91 MEV ANISTROPIC 725 1451 196 MT=102 (N,GAMMA) ANGULAR DISTRIBUTIONS. 725 1451 197 ZERO TO 0.4 MEV, ALL PHOTONS ARE ISOTROPIC. 725 1451 198 .4 TO 20 MEV, ANISOTROPIC DISTRIBUTION FOR THE SINGLE GROUND 725 1451 199 STATE TRANSITION IS BASED UPON N14(P,GO)O15 DATA BY KU70. 725 1451 200 MT=103 (N,P) TO C14, ALL ISOTROPIC. 725 1451 201 MT=104 (N,NP)+(N,D) TO C13, 3.85 MEV ANISOTROPIC 725 1451 202 MT=105 (N,ND)+(N,T) TO C12, ALL ISOTROPIC 725 1451 203 MT=107 (N,ALPHA) TO B11, ALL ISOTROPIC 725 1451 204 725 1451 205 ****************************** MF=33 ************************** 725 1451 206 725 1451 207 TO BE PROVIDED AT A LATER DATE. 725 1451 208 725 1451 209 --------------------------- REFERENCES -------------------------- 725 1451 210 725 1451 211 AJ80 F.AJZENBERG-SELOVE+C.BUSCH, NUCL.PHYS.A336,1(1980) 725 1451 212 AJ86 F.AJZENBERG-SELOVE, NUCL.PHYS.A449,1 (1986) 725 1451 213 BA63 R.W.BAUER ET AL.(LRL), NUCL. 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METH. 56, 325 (1967) 725 1451 289 WO67 C.WONG ET AL.(LRL), PHYS.REV.160, 769 (1967). 725 1451 290 YO72 P.G.YOUNG & D.G.FOSTER,JR., LA-4725 (1972). 725 1451 291 ZA63 M.R.ZATZICK+D.R.MAXSON (BRN), PHYS.REV.129, 1728 (1963). 725 1451 292 725 1451 293 1 451 297 1 725 1451 294 3 16 8 1 725 1451 295 3 103 144 1 725 1451 296 3 105 42 1 725 1451 297 725 1 0 298 725 0 0 299 7.014000+3 1.388278+1 0 0 0 0 725 3 16 300 -1.055347+7-1.055347+7 0 0 1 13 725 3 16 301 13 2 0 0 0 0 725 3 16 302 1.131365+7 0.000000+0 1.140000+7 2.980028-5 1.150000+7 4.958505-5 725 3 16 303 1.160000+7 1.188073-4 1.180000+7 2.960351-4 1.200000+7 6.392827-4 725 3 16 304 1.240000+7 1.563174-3 1.320000+7 3.855962-3 1.400000+7 6.263179-3 725 3 16 305 1.450000+7 7.429780-3 1.600000+7 9.111822-3 1.900000+7 1.014769-2 725 3 16 306 2.000000+7 1.021483-2 0.000000+0 0.000000+0 0.000000+0 0.000000+0 725 3 16 307 725 3 0 308 7.014000+3 1.388278+1 0 0 0 0 725 3103 309 6.258760+5 6.258760+5 0 0 2 421 725 3103 310 12 5 421 2 0 0 725 3103 311 1.000000-5 9.296400+1 1.000000-4 2.939800+1 1.000000-3 9.296400+0 725 3103 312 2.530000-2 1.848200+0 1.000000-1 9.296500-1 1.000000+0 2.940000-1 725 3103 313 1.000000+1 9.303300-2 1.000000+2 2.960600-2 1.000000+3 9.722400-3 725 3103 314 5.000000+3 4.134100-3 1.000000+4 2.512800-3 5.000000+4 8.639600-4 725 3103 315 1.000000+5 9.260800-4 2.000000+5 1.293900-3 3.000000+5 1.770100-3 725 3103 316 3.500000+5 2.102100-3 4.000000+5 2.801000-3 4.100000+5 3.191400-3 725 3103 317 4.200000+5 4.189900-3 4.300000+5 1.300200-2 4.320000+5 2.162300-2 725 3103 318 4.340000+5 2.418300-2 4.360000+5 1.425800-2 4.380000+5 8.487500-3 725 3103 319 4.400000+5 6.164900-3 4.500000+5 4.691500-3 4.600000+5 6.199400-3 725 3103 320 4.700000+5 1.068100-2 4.800000+5 2.913500-2 4.850000+5 6.792700-2 725 3103 321 4.900000+5 2.104800-1 4.920000+5 2.711700-1 4.940000+5 2.327700-1 725 3103 322 4.960000+5 1.532500-1 4.980000+5 9.717700-2 5.000000+5 6.460500-2 725 3103 323 5.100000+5 1.736000-2 5.200000+5 8.880300-3 5.300000+5 6.037000-3 725 3103 324 5.400000+5 4.807400-3 5.500000+5 4.289000-3 5.600000+5 4.282900-3 725 3103 325 5.700000+5 4.916000-3 5.800000+5 6.703300-3 5.900000+5 1.099000-2 725 3103 326 6.000000+5 2.132200-2 6.100000+5 4.755500-2 6.200000+5 1.138600-1 725 3103 327 6.250000+5 1.681800-1 6.300000+5 2.208900-1 6.350000+5 2.435000-1 725 3103 328 6.400000+5 2.285600-1 6.450000+5 1.956700-1 6.500000+5 1.623600-1 725 3103 329 6.550000+5 1.348500-1 6.600000+5 1.134600-1 6.800000+5 6.555700-2 725 3103 330 7.000000+5 4.343400-2 7.200000+5 3.044700-2 7.400000+5 2.209000-2 725 3103 331 7.600000+5 1.663700-2 7.800000+5 1.311100-2 8.000000+5 1.086000-2 725 3103 332 8.200000+5 9.459400-3 8.400000+5 8.640900-3 8.600000+5 8.248200-3 725 3103 333 8.800000+5 8.205900-3 9.000000+5 8.511000-3 9.100000+5 8.816800-3 725 3103 334 9.200000+5 9.253700-3 9.300000+5 9.860700-3 9.400000+5 1.069900-2 725 3103 335 9.500000+5 1.186100-2 9.600000+5 1.346800-2 9.650000+5 1.446800-2 725 3103 336 9.700000+5 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3.105730-2 725 3105 490 1.200000+7 3.119047-2 1.240000+7 3.145825-2 1.300000+7 3.112249-2 725 3105 491 1.360000+7 2.999612-2 1.400000+7 2.890950-2 1.500000+7 2.554763-2 725 3105 492 1.550000+7 2.353085-2 1.600000+7 2.050236-2 1.650000+7 1.766638-2 725 3105 493 1.700000+7 1.523305-2 1.800000+7 1.125789-2 1.900000+7 8.584296-3 725 3105 494 2.000000+7 6.896211-3 0.000000+0 0.000000+0 0.000000+0 0.000000+0 725 3105 495 725 3 0 496 725 0 0 497 0 0 0 498 7.015000+3 1.487100+1 -1 0 0 1 728 1451 1 0.000000+0 0.000000+0 0 0 0 6 728 1451 2 1.000000+0 0.000000+0 0 0 10 6 728 1451 3 0.000000+0 0.000000+0 0 0 207 5 728 1451 4 7- N- 15 LANL EVAL-SEP83 E.ARTHUR,P.YOUNG,G.HALE 728 1451 5 DIST-JUN90 900507 728 1451 6 ----ENDF/B-VI MATERIAL 728 728 1451 7 -----INCIDENT NEUTRON DATA 728 1451 8 ------ENDF-6 FORMAT 728 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 728 1451 10 ACTIVATION I 728 1451 11 ****************************************************************** 728 1451 12 728 1451 13 **************************************************************** 728 1451 14 728 1451 15 ENDF/B-VI MODIFICATIONS 728 1451 16 _____________________________ 728 1451 17 728 1451 18 REVISED SPRING, SUMMER OF 1983 BY YOUNG AND ARTHUR TO INCLUDE 728 1451 19 IMPROVED OPTICAL MODEL PARAMETERS, UPDATED LEVEL SCHEMES, IM- 728 1451 20 PROVED VERSION OF GNASH, AND MORE CAREFUL TREATMENT OF 728 1451 21 LEVEL DENSITY PARAMETERS. SEE ARTHUR AND YOUNG ARTICLES IN THE 728 1451 22 OCT.1982 - MAR.1983 T-2 PROGRESS REPORT (LA-9841-PR, 1983) 728 1451 23 FOR DETAILS. SECTIONS UPDATED ARE, 728 1451 24 728 1451 25 MF= 3/ MT=2,4,16,22,28,51-57,91,103,104,105,107 728 1451 26 MF=13/ MT=4,16,22,28,103,104,105,107 728 1451 27 MF=14/ MT=22,28 728 1451 28 MF=15/ MT=4,16,22,28,103,104,105,107 728 1451 29 728 1451 30 **************************************************************** 728 1451 31 728 1451 32 ENDF/B-V DESCRIPTION 728 1451 33 __________________________ 728 1451 34 728 1451 35 THE LACK OF EXPERIMENTAL DATA, WITH THE EXCEPTION OF TOTAL 728 1451 36 CROSS SECTION MEASUREMENTS,LED US TO OBTAIN CROSS SECTIONS WITH 728 1451 37 A VARIETY OF NUCLEAR MODEL CODES. WE USED AN ENERGY DEPENDENT 728 1451 38 R MATRIX ANALYSIS TO FIT THE TOTAL CROSS SECTION DATA OF 728 1451 39 ZE71 FOR NEUTRON ENERGIES FROM 0.8 TO 5.4 MEV. AS A STARTING 728 1451 40 POINT WE USED THE LEVEL SCHEME REPORTED IN ZE71. ALSO USED 728 1451 41 IN THE R MATRIX ANALYSIS WERE THE ELASTIC ANGULAR DISTRIBU- 728 1451 42 TIONS OF SI62 AND ZE71 IN THE ENERGY RANGE FROM 1.9 TO 3.64 728 1451 43 MEV. THE PARAMETERS OF THE R-MATRIX ANALYSIS WERE THEN USED 728 1451 44 TO GENERATE CROSS SECTIONS AND TO DETERMINE LEGENDRE COEFFI- 728 1451 45 CIENTS IN THE RANGE FROM 1.0E-05 EV TO 5.4 MEV. IN THE ENERGY 728 1451 46 REGION FROM 6 TO 20 MEV WE USED TWO STATISTICAL MODEL CODES TO 728 1451 47 GENERATE CROSS SECTIONS. WITH THE FIRST,COMNUC, WE COMPUTED 728 1451 48 THE ANGULAR DISTRIBUTIONS OF ELASTICALLY SCATTERED NEUTRONS. 728 1451 49 THE LEGENDRE COEFFICIENTS OBTAINED WERE THEN JOINED SMOOTHLY 728 1451 50 WITH THOSE FROM THE R-MATRIX ANALYSIS. WE ALSO OBTAINED 728 1451 51 ANGULAR DISTRIBUTIONS OF NEUTRONS LEADING TO THE FIRST SEVEN 728 1451 52 EXCITED STATES OF N15. TO GENERATE NEUTRON TRANSMISSION 728 1451 53 COEFFICIENTS FOR THIS PART OF THE ANALYSIS WE USED THE GLOBAL 728 1451 54 OPTICAL MODEL PARAMETERS OF WILMORE AND HODGSON AS REPORTED BY 728 1451 55 PE74, AND ADJUSTED THEM TO GIVE GOOD AGREEMENT WITH THE 728 1451 56 MEASURED TOTAL CROSS SECTION. THE GENERATION OF CAPTURE, 728 1451 57 INELASTIC, AND NON ELASTIC CROSS SECTIONS AS WELL AS 728 1451 58 NEUTRON,GAMMA-RAY, AND CHARGED-PARTICLE SPECTRA WAS DONE WITH 728 1451 59 THE STATISTICAL MODEL CODE,GNASH. THIS NEWLY DEVELOPED CODE IS 728 1451 60 BASED LARGELY ON THE STATISTICAL MODEL FORMALISM OF UH71. 728 1451 61 AGAIN NEUTRON TRANSMISSION COEFFICIENTS WERE BASED ON THE 728 1451 62 OPTICAL MODEL PARAMETERS OF WILMORE AND HODGSON. TRANSMISSION 728 1451 63 COEFFICIENTS WERE GENERATED FOR PROTONS,DEUTERONS, AND 728 1451 64 HE4, WITH THE APPROPRIATE GLOBAL FORMS REPORTED IN PE74. FOR 728 1451 65 TRITONS WE USED THE GLOBAL PARAMETERS FOR HE3 REPORTED IN PE74 728 1451 66 SINCE THESE WERE CONSISTENT WITH TRITON OPTICAL MODEL 728 1451 67 PARAMETERS FOR INDIVIDUAL LIGHT NUCLEI AS COMPILED BY PE74. 728 1451 68 THE GILBERT-CAMERON LEVEL DENSITY MODEL WAS USED WITH STANDARD 728 1451 69 VALUES FOR LEVEL DENSITY PARAMETERS (GI64). TO ACCOUNT FOR 728 1451 70 DIRECT AND SEMI-DIRECT PROCESSES WE USED THE PREEQUILIBRIUM 728 1451 71 MODEL OF BLANN AND CLINE (CL71) AND ASSUMED A TEN PERCENT 728 1451 72 PREEQUILIBRIUM FRACTION. 728 1451 73 728 1451 74 MF=2 --- RESONANCE PARAMETERS --- 728 1451 75 MT=151 EFFECTIVE SCATTERING RADIUS = 0.592916E-12 CM 728 1451 76 MF=3 --- SMOOTH CROSS SECTIONS --- 728 1451 77 THE 2200 M/S CROSS SECTIONS ARE 728 1451 78 MT= 1 SIGMA = 4.4185 BARNS 728 1451 79 MT= 2 SIGMA = 4.418 BARNS 728 1451 80 MT=102 SIGMA = 24.0E-06 BARNS 728 1451 81 MT=1 TOTAL CROSS SECTION 728 1451 82 FROM 1.0E-05 EV TO 5.4 MEV TOTAL CROSS SECTION VALUES ARE 728 1451 83 BASED ON THE R-MATRIX ANALYSIS DESCRIBED ABOVE. FROM 5.5 728 1451 84 TO 20 MEV THE EVALUATED CROSS SECTION IS BASED ON THE 728 1451 85 SMOOTHED RESULTS OF ZE71. 728 1451 86 MT=2 ELASTIC SCATTERING CROSS SECTION 728 1451 87 ZERO TO 20 MEV, SUBTRACTED EVALUATED NON-ELASTIC FROM TOTAL 728 1451 88 TO GIVE ELASTIC CROSS SECTION 728 1451 89 MT=3 SUM OF ALL CROSS SECTIONS EXCEPT ELASTIC 728 1451 90 MT=4 SUM OF MT=51-57, 91 CROSS SECTIONS 728 1451 91 MT=16 (N,2N) CROSS SECTION 728 1451 92 BASED ON SMOOTH CURVE DRAWN THROUGH RESULTS OF THE 728 1451 93 STATISTICAL MODEL CALCULATIONS DESCRIBED BEFORE 728 1451 94 MT=22 (N,N ALPHA) CROSS SECTION 728 1451 95 BASED ON SMOOTHED RESULTS OF STATISTICAL MODEL CALCULATION 728 1451 96 MT=28 (N,NP) CROSS SECTION 728 1451 97 BASED ON SMOOTHED RESULTS OF STATISTICAL MODEL CALCULATION 728 1451 98 MT=51-57 INELASTIC CROSS SECTION TO DISCRETE STATES 728 1451 99 MT=51 Q=-5.27 MEV MT=55 Q=-7.301 MEV 728 1451 100 MT=52 Q=-5.299MEV MT=56 Q=-7.566 MEV 728 1451 101 MT=53 Q=-6.324MEV MT=57 Q=-8.313 MEV 728 1451 102 MT=54 Q=-7.155MEV 728 1451 103 MT=91 (N,N) TO CONTINUUM 728 1451 104 CONTINUUM DEFINED TO BEGIN AT 0.1 MEV ABOVE LAST N-15 728 1451 105 DISCRETE LEVEL INCLUDED IN CALCULATION, I.E. CONTINUUM 728 1451 106 BEGINS AT 8.413 MEV 728 1451 107 MT=102 (N,GAMMA) CROSS SECTION 728 1451 108 ZERO TO 0.010 MEV, 1/V FROM 24.0E-06 BARNS AT THERMAL 728 1451 109 6 TO 20 MEV CALCULATED FROM STATISTICAL MODEL WITH AXEL 728 1451 110 (AX62) GIANT DIPOLE RESONANCE APPROXIMATION FOR GAMMA- 728 1451 111 RAY TRANSMISSION COEFFICIENTS 728 1451 112 .010 TO 6 MEV, CROSS SECTION BASED ON SMOOTHED CURVE FROM 728 1451 113 REGION WHERE 1/V DEPENDENCE ENDS TO REGION WHERE 728 1451 114 CALCULATED VALUES BEGIN. 728 1451 115 MT=103 SUM OF MT= 700,701, AND 718 CROSS SECTIONS 728 1451 116 MT=104 SUM OF MT= 720,721,722,AND 738 CROSS SECTIONS 728 1451 117 MT=105 SUM OF MT=740,741, AND 758 CROSS SECTIONS 728 1451 118 MT=107 SUM OF MT= 780-785 AND 798 CROSS SECTIONS 728 1451 119 MT=700,701 (N,P) CROSS SECTION TO C15 GROUND AND FIRST EXCITED 728 1451 120 STATES 728 1451 121 MT=700 Q=-8.990 MEV EX=0. MEV 728 1451 122 701 Q=-9.737 EX=.747 728 1451 123 MT=738 (N,D) TO CONTINUUM STATES OF C14 728 1451 124 CONTINUUM DEFINED TO BEGIN AT 0.85 MEV, JUST ABOVE FIRST 728 1451 125 EXCITED STATE 728 1451 126 MT=720-722 (N,D) CROSS SECTION TO C14 GROUND,FIRST,AND SECOND 728 1451 127 EXCITED STATES 728 1451 128 MT=720 Q=-7.984 MEV EX=0. MEV 728 1451 129 MT=721 Q=-14.079 EX=6.095 728 1451 130 MT=722 Q=-14.567 EX=6.583 728 1451 131 MT=740-742 (N,T) CROSS SECTION TO C13 GROUND,FIRST,AND SECOND 728 1451 132 EXCITED STATES 728 1451 133 MT=738 (N,D) TO CONTINUUM STATES OF C15 728 1451 134 CONTINUUM DEFINED TO BEGIN AT 6.681 MEV, JUST ABOVE SECOND 728 1451 135 EXCITED LEVEL IN C14 728 1451 136 MT=740 Q=-9.902 MEV EX=0. MEV 728 1451 137 741 Q=-12.992 3.09 728 1451 138 742 -13.586 3.684 728 1451 139 MT=780-785 (N,ALPHA) CROSS SECTION TO B12 GROUND AND FIRST 728 1451 140 FIVE EXCITED STATES 728 1451 141 MT=780 Q=-7.623 MEV EX=0. MEV 728 1451 142 781 -8.576 .953 728 1451 143 782 -9.297 1.674 728 1451 144 783 -10.244 2.621 728 1451 145 784 -10.343 2.72 728 1451 146 785 -11.013 3.39 728 1451 147 MT=758 (N,T) TO CONTINUUM STATES OF C13 728 1451 148 CONTINUUM BEGINS AT 3.784 MEV, ABOVE SECOND EXCITED LEVEL 728 1451 149 IN C13 728 1451 150 MT=798 (N,ALPHA) TO CONTINUUM STATES OF B12 728 1451 151 CONTINUUM BEGINS AT 3.49 MEV, JUST ABOVE FIFTH EXCITED 728 1451 152 STATE IN B12 728 1451 153 MF=4 --- SECONDARY NEUTRON AND CHARGED PARTICLE ANGULAR 728 1451 154 DISTRIBUTIONS 728 1451 155 MT=2 ELASTIC ANGULAR DISTRIBUTIONS 728 1451 156 ZERO TO 5.4 MEV BASED ON RESULTS OBTAINED FROM R MATRIX 728 1451 157 THEORY ANALYSIS 728 1451 158 6 TO 20 MEV BASED ON OPTICAL MODEL CALCULATION 728 1451 159 MT=16 ANGULAR DISTRIBUTION FOR (N,2N) REACTION 728 1451 160 IN THE ABSENCE OF DATA ISOTROPY IN THE LAB SYSTEM IS ASSUMED 728 1451 161 MT=22 ANGULAR DISTRIBUTION OF NEUTRONS FROM (N,NALPHA) 728 1451 162 REACTION ASSUED ISOTROPIC IN THE LAB SYSTEM 728 1451 163 MT=28 ANGULAR DISTRIBUTION OF NEUTRONS FROM (N,NP) REACTION 728 1451 164 ASSUMED ISOTROPIC IN THE LAB SYSTEM 728 1451 165 MT=51-57 ANGULAR DISTRIBUTION CALCULATED USING HAUSER- 728 1451 166 FESHBACH THEORY 728 1451 167 MT=718 ANGULAR DISTRIBUTION OF PROTONS FROM (N,P) REACTION 728 1451 168 ASSUMED ISOTROPIC IN THE LAB 728 1451 169 MT=719 ANGULAR DISTRIBUTION OF PROTONS FROM (N,NP) ASSUMED 728 1451 170 ISOTROPIC IN THE LAB 728 1451 171 MT=738 ANGULAR DISTRIBUTION OF DEUTRONS FROM (N,D) ASSUMED 728 1451 172 ISOTROPIC IN THE LAB 728 1451 173 MT=758 ANGULAR DISTRIBUTION OF TRITONS FROM (N,T) REACTION 728 1451 174 ASSUMED ISOTROPIC IN THE LAB 728 1451 175 MT=798 ANGULAR DISTRIBUTION OF ALPHA S FROM (N,ALPHA) REACTION 728 1451 176 ASSUMED ISOTROPIC IN THE LAB SYSTEM 728 1451 177 MT=799 ANGULAR DISTRIBUTION OF ALPHAS FROM (N,N ALPHA) REACTION 728 1451 178 ASSUMED ISOTROPIC IN THE LAB 728 1451 179 MF=5---ENERGY DISTRIBUTION OF SECONDARY NEUTRONS AND CHARGED 728 1451 180 PARTICLES--- 728 1451 181 MT=16,22,28,91,718,758,AND 798 CALCULATED WITH STATISTICAL 728 1451 182 MODEL CODE 728 1451 183 MT=719 USED FOR PROTON SPECTRA FROM (N,NP) REACTION 728 1451 184 MT=799 USED FOR ALPHA SPECTRA FROM (N,N ALPHA) REACTION 728 1451 185 MF=13 --- PHOTON PRODUCTION CROSS SECTIONS--- 728 1451 186 MT=4,16,103,104,105,AND 107 INCLUDE BOTH DISCRETE AND 728 1451 187 CONTINUUM CONTRIBUTIONS AND WERE GENERATED WITH THE 728 1451 188 STATISTICAL MODEL CALCULATION 728 1451 189 MF=14--- PHOTON ANGULAR DISTRIBUTIONS--- 728 1451 190 MT= 4 (N,N) TO N15, ALL ISOTROPIC 728 1451 191 MT=103 (N,P) TO C15 ALL ISOTROPIC 728 1451 192 MT=104 (N,D) TO C14, ALL ISOTROPIC 728 1451 193 MT=105 (N,T) TO C13, ALL ISOTROPIC 728 1451 194 MT=107 (N,ALPHA) TO B12, ALL ISOTROPIC 728 1451 195 MT=16 (N,2N GAMMA) TO N14, ALL ISOTROPIC 728 1451 196 MF=15 --- ENERGY DISTRIBUTION OF SECOND PHOTON --- 728 1451 197 MT=4,16,103,104,105,107 GENERATED USING STATISTICAL MODEL 728 1451 198 -----REFERENCES----- 728 1451 199 AJ70 F.AJZENBERG-SELOVE, NUCL.PHYS.A152,1 (1973) 728 1451 200 AJ71 F.AJZENBERG-SELOVE,NUCL.PHYS. A166,1 (1971) 728 1451 201 AX62 L.P.AXEL, PHYS.REV. 126,671 (1972) 728 1451 202 CL71 C.K.CLINE AND M.BLANN,NUCL.PHYS.A172,225 (1971) 728 1451 203 FE67 P.FESSENDEN AND D.R.MAXSON,PHYS.REV.158,948 (1967) 728 1451 204 GI65 A.GILBERT AND A.G.L.CAMERON,CAN.J. OF PHYS.43,1446 (1965) 728 1451 205 PE74 C.M.PEREY AND F.G.PEREY,ATOMIC AND NUCL. DATA TABLES 13,293 728 1451 206 (1974) 728 1451 207 SI62 C.P.SIKKEMA NUCL.PHYS. 32,470 (1962) 728 1451 208 U71 M.UHL ACTA PHYSICA AUSTRIA 31,245 (1971) 728 1451 209 ZE71 B.ZEITNITZ ET AL.,NUCL.PHYS.A166,443 (1971) 728 1451 210 728 1451 211 1 451 216 1 728 1451 212 3 102 13 0 728 1451 213 3 103 15 1 728 1451 214 3 104 16 1 728 1451 215 3 107 17 1 728 1451 216 728 1 0 217 728 0 0 218 7.015000+3 1.487100+1 0 99 0 0 728 3102 219 2.490000+6 2.490000+6 0 0 3 29 728 3102 220 3 5 10 3 29 2 728 3102 221 1.000000-5 1.210000-3 2.530000-2 2.400000-5 1.500000+1 1.000000-6 728 3102 222 3.000000+1 8.000000-7 6.000000+1 7.500000-7 2.000000+2 8.300000-7 728 3102 223 1.000000+3 1.200000-6 1.000000+4 2.600000-6 1.000000+5 1.050000-5 728 3102 224 1.000000+6 2.040000-5 2.000000+6 2.050000-5 2.980000+6 1.950000-5 728 3102 225 4.000000+6 1.850000-5 5.000000+6 1.750000-5 6.000000+6 1.650000-5 728 3102 226 7.000000+6 1.500000-5 8.000000+6 1.400000-5 9.000000+6 1.300000-5 728 3102 227 1.000000+7 1.200000-5 1.100000+7 1.100000-5 1.200000+7 1.000000-5 728 3102 228 1.300000+7 9.200000-6 1.400000+7 8.600000-6 1.500000+7 8.200000-6 728 3102 229 1.600000+7 8.000000-6 1.700000+7 7.800000-6 1.800000+7 7.750000-6 728 3102 230 1.900000+7 7.600000-6 2.000000+7 7.500000-6 0.000000+0 0.000000+0 728 3102 231 728 3 0 232 7.015000+3 1.487100+1 0 99 0 0 728 3103 233 -8.989300+6-8.989300+6 0 0 1 35 728 3103 234 35 2 0 0 0 0 728 3103 235 9.593800+6 0.000000+0 9.750000+6 2.150700-6 1.000000+7 2.044300-4 728 3103 236 1.025000+7 1.065900-3 1.050000+7 2.463000-3 1.075000+7 4.509300-3 728 3103 237 1.100000+7 7.111900-3 1.125000+7 1.098400-2 1.150000+7 1.431600-2 728 3103 238 1.175000+7 1.579100-2 1.200000+7 1.702000-2 1.225000+7 1.835600-2 728 3103 239 1.250000+7 1.928000-2 1.275000+7 1.956600-2 1.300000+7 1.981000-2 728 3103 240 1.325000+7 2.011100-2 1.350000+7 2.040000-2 1.375000+7 2.033100-2 728 3103 241 1.400000+7 1.985000-2 1.425000+7 1.922800-2 1.450000+7 1.844000-2 728 3103 242 1.475000+7 1.744400-2 1.500000+7 1.648000-2 1.525000+7 1.569200-2 728 3103 243 1.550000+7 1.490000-2 1.575000+7 1.403400-2 1.600000+7 1.317000-2 728 3103 244 1.650000+7 1.156200-2 1.700000+7 1.014000-2 1.750000+7 8.943700-3 728 3103 245 1.800000+7 7.892000-3 1.850000+7 6.903600-3 1.900000+7 5.993000-3 728 3103 246 1.950000+7 5.197200-3 2.000000+7 4.510000-3 0.000000+0 0.000000+0 728 3103 247 728 3 0 248 7.015000+3 1.487100+1 0 99 0 0 728 3104 249 -7.982800+6-7.982800+6 0 0 1 39 728 3104 250 39 2 0 0 0 0 728 3104 251 8.519600+6 0.000000+0 8.750000+6 3.043700-7 9.000000+6 5.936600-4 728 3104 252 9.250000+6 4.963800-3 9.500000+6 1.064500-2 9.750000+6 1.637300-2 728 3104 253 1.000000+7 2.088500-2 1.025000+7 2.447300-2 1.050000+7 2.771500-2 728 3104 254 1.075000+7 2.977500-2 1.100000+7 2.981800-2 1.125000+7 2.842100-2 728 3104 255 1.150000+7 2.683100-2 1.175000+7 2.522300-2 1.200000+7 2.377000-2 728 3104 256 1.225000+7 2.240600-2 1.250000+7 2.101800-2 1.275000+7 1.971400-2 728 3104 257 1.300000+7 1.860000-2 1.325000+7 1.769600-2 1.350000+7 1.689500-2 728 3104 258 1.375000+7 1.612000-2 1.400000+7 1.529000-2 1.425000+7 1.437900-2 728 3104 259 1.450000+7 1.343200-2 1.475000+7 1.247600-2 1.500000+7 1.154000-2 728 3104 260 1.525000+7 1.073000-2 1.550000+7 1.013700-2 1.575000+7 9.768400-3 728 3104 261 1.600000+7 9.630000-3 1.650000+7 1.156600-2 1.700000+7 1.603800-2 728 3104 262 1.750000+7 2.091400-2 1.800000+7 2.406000-2 1.850000+7 2.525800-2 728 3104 263 1.900000+7 2.566000-2 1.950000+7 2.519200-2 2.000000+7 2.378000-2 728 3104 264 728 3 0 265 7.015000+3 1.487100+1 0 99 0 0 728 3107 266 -7.621500+6-7.621500+6 0 0 1 41 728 3107 267 41 2 0 0 0 0 728 3107 268 8.134000+6 0.000000+0 8.250000+6 2.813500-8 8.500000+6 8.877100-8 728 3107 269 8.750000+6 4.646300-5 9.000000+6 1.450100-4 9.250000+6 9.294800-4 728 3107 270 9.500000+6 3.710100-3 9.750000+6 8.520600-3 1.000000+7 1.422800-2 728 3107 271 1.025000+7 2.014700-2 1.050000+7 2.645700-2 1.075000+7 3.366700-2 728 3107 272 1.100000+7 4.111300-2 1.125000+7 4.835400-2 1.150000+7 5.378600-2 728 3107 273 1.175000+7 5.514500-2 1.200000+7 5.559000-2 1.225000+7 5.747300-2 728 3107 274 1.250000+7 5.925000-2 1.275000+7 6.017500-2 1.300000+7 6.115000-2 728 3107 275 1.325000+7 6.358100-2 1.350000+7 6.599000-2 1.375000+7 6.722600-2 728 3107 276 1.400000+7 6.855000-2 1.425000+7 7.027400-2 1.450000+7 7.200000-2 728 3107 277 1.475000+7 7.372500-2 1.500000+7 7.543000-2 1.525000+7 7.480000-2 728 3107 278 1.550000+7 7.199000-2 1.575000+7 6.912600-2 1.600000+7 6.630000-2 728 3107 279 1.650000+7 6.189700-2 1.700000+7 5.736000-2 1.750000+7 4.958500-2 728 3107 280 1.800000+7 4.178000-2 1.850000+7 3.652600-2 1.900000+7 3.189000-2 728 3107 281 1.950000+7 2.764000-2 2.000000+7 2.370000-2 0.000000+0 0.000000+0 728 3107 282 728 3 0 283 728 0 0 284 0 0 0 285 8.016000+3 1.585316+1 -1 0 0 1 825 1451 1 0.000000+0 0.000000+0 0 0 0 6 825 1451 2 1.000000+0 0.000000+0 0 0 10 6 825 1451 3 0.000000+0 0.000000+0 0 0 303 2 825 1451 4 8-O - 16 LANL EVAL-JAN90 G.HALE, Z.CHEN, P.YOUNG 825 1451 5 DIST-JUN90 900524 825 1451 6 ----ENDF/B-VI MATERIAL 825 825 1451 7 -----INCIDENT NEUTRON DATA 825 1451 8 ------ENDF-6 FORMAT 825 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 825 1451 10 ACTIVATION I 825 1451 11 ****************************************************************** 825 1451 12 825 1451 13 ---------------------------------------------------------------- 825 1451 14 0-16 FREE ATOM EVALUATION 825 1451 15 ---------------------------------------------------------------- 825 1451 16 825 1451 17 GENERAL INFORMATION: 825 1451 18 825 1451 19 THE ENDF/B-VI EVALUATION IS A COMPLETE REVISION OF THE EARLIER 825 1451 20 ENDF/B-V EVALUATION, WHICH DATES TO THE MID 1970'S. THE NEW 825 1451 21 EVALUATION INCLUDES EXTENSIVE NEW EXPERIMENTAL DATA, A 825 1451 22 COMPLETE NEW R-MATRIX ANALYSIS BELOW 6.2 MEV, A COVARIANCE 825 1451 23 ANALYSIS OF THE TOTAL CROSS SECTION ABOVE 6.2 MEV, AND NEW 825 1451 24 HAUSER-FESHBACH STATISTICAL AND DWBA CALCULATIONS FOR THE 825 1451 25 HIGHER ENERGY REGIONS. ESPECIALLY IMPORTANT NEW EXP. DATA 825 1451 26 INCLUDE THE TOTAL CROSS SECTIONS OF LA80,OH84,CI80, THE DIFFER- 825 1451 27 ENTIAL ELASTIC AND INELASTIC DATA OF GL82, BO89, PE85 AND BA85, 825 1451 28 THE NEUTRON EMISS. MEASUREMENTS OF TA83 AND BA85, AND THE 825 1451 29 GAMMA-RAY PRODUCTION DATA OF NO78, MO79, AND NE90. 825 1451 30 825 1451 31 ******************************** MF=2 ************************* 825 1451 32 825 1451 33 MT=2 EFFECTIVE SCATTERING RADIUS = 5.56256E-13 CM 825 1451 34 825 1451 35 ******************************** MF=3 ************************* 825 1451 36 825 1451 37 THERMAL (2200 M/S) CROSS SECTIONS 825 1451 38 825 1451 39 TOTAL 3.88849 B RADIATIVE CAPTURE 0.1900 MB 825 1451 40 ELASTIC 3.88830 B 825 1451 41 825 1451 42 MT=1 TOTAL CROSS SECTION 825 1451 43 0.0 TO 6.2 MEV, ESSENTIALLY CALCULATED FROM R-MATRIX 825 1451 44 PARAMETERS OBTAINED BY FITTING SIMULTANEOUSLY ALMOST 825 1451 45 ALL AVAILABLE DATA FOR REACTIONS 16O(N,N)16O, 825 1451 46 16O(N,ALPHA0)13C, 13C(ALPHA0,ALPHA0)13C AT ENERGIES 825 1451 47 BELOW EN = 6.2 MEV. EXP. TOTAL CROSS SECTION DATA FOR THE 825 1451 48 ANALYSIS WERE THE LA80 RESULTS BELOW EN= 3 MEV, AND THE 825 1451 49 CI80 MEASUREMENTS AT HIGHER ENERGIES, WITH INSERTS OF THE 825 1451 50 HIGH-RESOLUTION DATA OF JO79. 825 1451 51 6.2 TO 20.0 MEV, BASED ON A COVARIANCE ANALYSIS WITH THE GLUCS 825 1451 52 BAYES CODE (HE80) OF ALL THE MAJOR TOTAL CROSS SECTION MEA- 825 1451 53 SUREMENTS (FO71,PE72,SC72A,LA80,CI68,CI80), WITH STRUCTURE 825 1451 54 INSERTED FROM THE HIGH-RESOLUTION CI80 MEASUREMENT. 825 1451 55 825 1451 56 MT=2 ELASTIC SCATTERING CROSS SECTION 825 1451 57 0.0 TO 6.2 MEV, R-MATRIX ANALYSIS THAT INCLUDES ALL AVAIL- 825 1451 58 ABLE EXP. DATA, AS DESCRIBED ABOVE. ELASTIC ANGULAR DIST. 825 1451 59 DATA USED IN THE ANALYSIS INCLUDES LA60, OK55, FO58, MA62, 825 1451 60 FO70, HU62, PH61, JO67, KI72, CH61, DR76 AND FO64. 825 1451 61 6.2 TO 20 MEV, OBTAINED BY SUBTRACTING THE SUM OF MT=4,102, 825 1451 62 103,104,107 FROM MT=1. HOWEVER, ADJUSTMENTS WERE MADE TO 825 1451 63 THE (N,N') AND (N,ALPHA) REACTION CROSS SECTS. TO ENHANCE 825 1451 64 AGREEMENT WITH THE ELASTIC MEASUREMENTS OF PH61,CH61,BU73, 825 1451 65 BA63,MC66,BE67,NE72,KI72,BO89,GL82,PE85 AND BA85. THE MAG- 825 1451 66 NITUDE OF THESE ADJUSTMENTS WAS GENERALLY SMALL AND WAS 825 1451 67 GREATEST NEAR STRUCTURE AND NEAR 18 MEV (~15 %). 825 1451 68 825 1451 69 MT=4 INELASTIC CROSS SECTION 825 1451 70 THRES. TO 20 MEV, SUM OF MT=51-88. NOTE THAT MT=4 IS ACTUALLY 825 1451 71 THE SUM OF THE (N,N'), (N,NP), (N,NALPHA), AND (N,2N) 825 1451 72 CROSS SECTIONS BECAUSE OF THE USE OF THE EXCITATION 825 1451 73 ENERGY BINNING TECHNIQUE TO REPRESENT MT=51-88. 825 1451 74 825 1451 75 MT=51-69 INELASTIC CROSS SECTION TO DISCRETE STATES 825 1451 76 THRES. TO 20 MEV, MT=52-55,59,60 ARE BASED MAINLY ON (N,NG) 825 1451 77 DATA OF NE90,NO78,DR70,DI70,NY69,CL69,OR70,BU71,HA59, AND 825 1451 78 THE (N,N') DATA OF BO89, KI72, NE72, BA63, MC66, BA85 AND 825 1451 79 ME69. THE CROSS SECTIONS FOR THE REMAINING MT NUMBERS 825 1451 80 ARE BASED ON COMPD. NUC. CALCULATIONS WITH THE COMNUC AND 825 1451 81 GNASH HAUSER-FESHBACH STATISTICAL CODES (DU70,YO77), & DWBA 825 1451 82 DIRECT COMPONENTS CALCULATED WITH DWUCK (KU76) USING THE 825 1451 83 DATA AND PARAMETERS FROM REFERENCES OL90 AND IS87. BECAUSE 825 1451 84 ONLY VERY LIMITED GAMMA RAY ANG. DIST. DATA IS 825 1451 85 AVAILABLE, INELASTIC CROSS SECTIONS WERE OBTAINED FROM 825 1451 86 GAMMA DATA BY MULTIPLYING 55 OR 125 DEG. DATA BY 4*PI. THIS 825 1451 87 LEADS TO INCREASED UNCERTAINTY, PARTICULARLY FOR THE MT=52, 825 1451 88 J,PI=3- STATE. ACCORDINGLY, SMALL ADJUSTMENTS WERE MADE IN 825 1451 89 THE INTEGRATED CROSS SECTIONS TO ENHANCE AGREEMENT WITH THE 825 1451 90 ELASTIC AND TOTAL CROSS SECTION DATA LISTED ABOVE. 825 1451 91 NOTE THAT MT= 51 DECAYS BY PAIR PRODUCTION. 825 1451 92 825 1451 93 MT=70-88 INELASTIC CROSS SECTION TO 0.3-MEV BANDS CENTERED 825 1451 94 ABOUT THE GIVEN EXCITATION ENERGIES, USED IN LIEU OF 825 1451 95 MT=91 AND MF=5. 825 1451 96 THRES. TO 20 MEV, INTEGRATED CROSS SECTION ADJUSTED TO GIVE 825 1451 97 A NONELASTIC X/S IN AGREEMENT WITH THE EVALUATED TOTAL 825 1451 98 AND ELASTIC. THE X/S WAS DIVIDED AMONG BANDS ACCORDING 825 1451 99 TO A NUCLEAR TEMPERATURE CALCULATION USING T=2 MEV. 825 1451 100 825 1451 101 ****PLEASE NOTE THAT MUCH OF THE CROSS SECTION TO LEVELS ABOVE 825 1451 102 ****9 MEV SUBSEQUENTLY RESULTS IN CHARGED PARTICLE EMISSION. 825 1451 103 ****MT=56-58,61-66,68-70,72-73,75,77-78,80,82-83,85,87,89, ARE 825 1451 104 ****FLAGGED AS DECAYING BY ALPHA EMISSION. THIS CHOICE LEADS TO 825 1451 105 ****A TOTAL ALPHA EMISSION X/S SIMILAR TO DATA OF LI52,DA68,BO66 825 1451 106 ****BELOW 17 MEV. THE REMAINING MT NUMBERS ABOVE MT=66 ARE 825 1451 107 ****FLAGGED AS BEING PROTON EMITTERS. 825 1451 108 825 1451 109 MT=102 (N,GAMMA) CROSS SECTION 825 1451 110 1/V VARIATION FROM 190 MICROBARNS AT 2200 M/S, TAKEN FROM THE 825 1451 111 COMPILATION OF MU81. 825 1451 112 825 1451 113 MT=103 (N,P) CROSS SECTION 825 1451 114 THRES. TO 20 MEV, BASED ON A REVISION OF THE EVALUATION OF 825 1451 115 SL65, USING THE EXPERIMENTAL DATA OF BO66, SE62, DE62, 825 1451 116 SC72B, AND MA54. 825 1451 117 825 1451 118 MT=104 (N,D) CROSS SECTION 825 1451 119 THRES. TO 20 MEV, COMPD. NUC. REACT. THEORY CALC. NORM. TO 825 1451 120 SINGLE DATUM POINT OF LI52 AT 14 MEV. TAKEN OVER INTACT 825 1451 121 FROM ENDF/B-V. 825 1451 122 825 1451 123 MT=107 (N,ALPHA) CROSS SECTION 825 1451 124 THRES. TO 20 MEV, SUM OF MT=780-783. 825 1451 125 825 1451 126 MT=800 (N,ALPHA) INTEGRATED CROSS SECTION TO 13C GROUND STATE 825 1451 127 0.0 TO 6.2 MEV, BASED ON R-MATRIX ANALYSIS DESCRIBED ABOVE 825 1451 128 UNDER MT=1. ENERGY SCALE OF BA72 ADJUSTED TO 825 1451 129 MATCH TOTAL CROSS SECT AND RESOLUTION CORRECTIONS APPLI- 825 1451 130 ED TO GIVE WIDTH AND HEIGHT OF PEAKS CONSISTENT WITH 825 1451 131 TOTAL. NORMALIZATION OF 0.808 FOR BA72 DETERMINED FROM 825 1451 132 R-MATRIX FIT AND APPLIED. LEVEL SCHEME DETERMINED FROM 825 1451 133 R-MATRIX ANALYSIS AND SE86. 825 1451 134 6.2 TO 20 MEV, BASED ON DATA OF DA63, DA68, SI68, BA73, AND 825 1451 135 COMPOSITE OF MC66A, MA68, AND LE68 AT 14 MEV. NOTE THAT 825 1451 136 THE DA63 DATA WERE RENORMALIZED BY FACTOR OF 1.7 TO 825 1451 137 BRING THEM INTO ROUGH AGREEMENT WITH THE R-MATRIX ANALYSIS 825 1451 138 OF THE BA73 (N,A0) DATA, TOGETHER WITH THE TOTAL AND 825 1451 139 ELASTIC DATA IN THE ANALYSIS. BECAUSE THE DA68 EXP. DATA 825 1451 140 WERE NORMALIZED TO DA63, THE FORMER WERE ALSO RE- 825 1451 141 NORMALIZED BY THE FACTOR OF 1.7. 825 1451 142 825 1451 143 MT=801-803 (N,A) CROSS SECTION TO EXCITED LEVELS OF C13. 825 1451 144 THRES. TO 15 MEV, USED (N,A) DATA OF DA63 AND SI68, AND THE 825 1451 145 (N,AG) DATA OF NE90, NO78, DI70, OR70, CL69, NY69, EN64, 825 1451 146 AND BU71. 825 1451 147 825 1451 148 ****************************** MF=4 *************************** 825 1451 149 825 1451 150 MT=2 ELASTIC ANGULAR DISTRIBUTIONS 825 1451 151 0.0 TO 6.2 MEV, CALCULATED FROM R-MATRIX FIT (SEE MF=3,MT=1). 825 1451 152 MEASURED ANGULAR DISTRIBUTIONS INPUT TO THE FIT WERE 825 1451 153 THOSE OF CH61, FO58, FO70, HI58, HU62, JO67, KI72, 825 1451 154 LA60, LI66, MA62, PH61, AND JO79. FITS WERE ATTEMPTED 825 1451 155 USING NEW DATA OF SC77 BUT THOSE MEASUREMENTS WERE FOUND 825 1451 156 TO HAVE SIGNIFICANT UNCERTAINTIES AND SOME DISCREPANCIES 825 1451 157 WITH OTHER DATA WERE NOTED. 825 1451 158 6.2 TO 20 MEV, SMOOTH CURVE THROUGH COEFFICIENTS DERIVED 825 1451 159 FROM FITS TO ELASTIC DATA OF PH61, NE72, CH61, BA63, 825 1451 160 BE67, MC66, KI72, BU73, NE72, GL82, BA85, BO89, & PE85. 825 1451 161 825 1451 162 MT=51-55 INELASTIC ANGULAR DISTRIBUTIONS ANISOTROPIC 825 1451 163 ABOVE 10 MEV, BASED ON FITS OF THE 14-MEV DATA OF KI72, NE72, 825 1451 164 BA63, MC66, BA85, ME69, AND ESPECIALLY BO89. 825 1451 165 825 1451 166 MT=56-88 INELASTIC ANGULAR DISTRIBUTIONS 825 1451 167 THRESHOLD TO 20 MEV. ASSUMED ISOTROPIC IN CM SYSTEM 825 1451 168 825 1451 169 ****************************** MF=12 ************************** 825 1451 170 825 1451 171 MT=102 CAPTURE GAMMAS, PRIVATE COMMUNICATION FROM Ju64 825 1451 172 825 1451 173 ANISOTROPIC SECONDARY GAMMA RAY ANGULAR DISTRIBUTIONS WERE 825 1451 174 ADDED FOR THE 6.131 AND 6.917 MEV GAMMAS. 825 1451 175 THESE RESULTS TAKEN DIRECTLY FROM ENDF/B-V. 825 1451 176 825 1451 177 ******************************* MF=13 ************************** 825 1451 178 825 1451 179 MT=4 (N,NG) CROSS SECTIONS 825 1451 180 THRES. TO 15 MEV, BASED MAINLY ON DATA OF NE90, NO78, HA59, 825 1451 181 DI70, OR70, DR70, CL69, LU70, BU71, NY69, OBTAINED FROM 825 1451 182 MF=3,MT=51-60 USING AN O-16 DECAY SCHEME FROM AJ86A. 825 1451 183 ****NOTE THAT THE FIRST EXCITED LEVEL OF O16 AT 6.052 MEV IS 825 1451 184 ****ASSUMED TO DECAY WITH EMISSION OF TWO 0.51 MEV GAMMA RAYS 825 1451 185 825 1451 186 MT=22 (N,NAG) CROSS SECTIONS 825 1451 187 THRES. TO 20 MEV, SMOOTH CURVE BASED CRUDELY ON (N,NA) CROSS 825 1451 188 SECTION AND KNOWN LEVELS IN C12, ADJUSTED TO AGREE WITH 825 1451 189 COMPOSITE OF 14 MEV DATA OF CL69, OR70, AND DATA OF NE90. 825 1451 190 825 1451 191 MT=103 (N,PG) CROSS SECTIONS 825 1451 192 THRES. TO 20 MEV, BASED ON CRUDE DIVISION OF MF=3, MT=103 X/S 825 1451 193 AMONG AVAILABLE LEVELS ACCORDING TO (2*J+1). 825 1451 194 THESE RESULTS WERE TAKEN FROM ENDF/B/V. 825 1451 195 825 1451 196 MT=107 (N,AG) CROSS SECTIONS 825 1451 197 THRES. TO 20 MEV, BASED MAINLY ON (N,AG) DATA OF NE90, NO78, 825 1451 198 DI70, OR70, CL69, NY69, EN64, BU71, AND (N,A) DATA OF DA63 825 1451 199 AND SI68. 825 1451 200 825 1451 201 ******************************* MF=14 ************************** 825 1451 202 825 1451 203 ASSUMED ISOTROPIC EXCEPT FOR THE 6.131-MEV GAMMA, WHICH IS 825 1451 204 BASED ON THE ANGULAR DIST. MEASUREMENT OF DR70, LU70, 825 1451 205 BU71, AND DI70, AND THE 6.917-MEV GAMMA, WHICH IS BASED 825 1451 206 ON THE TWO-ANGLE MEASUREMENTS OF DI70. THESE RESULTS 825 1451 207 WERE CARRIED OVER FROM ENDF/B/V. 825 1451 208 825 1451 209 MT=22 (N,NAG) ANGULAR DISTRIBUTIONS 825 1451 210 ASSUMED ISOTROPIC. 825 1451 211 825 1451 212 MT=103 (N,PG) ANGULAR DISTRIBUTIONS 825 1451 213 ASSUMED ISOTROPIC. 825 1451 214 825 1451 215 MT=107 (N,AG) ANGULAR DISTRIBUTIONS 825 1451 216 ASSUMED ISOTROPIC. 825 1451 217 825 1451 218 ****************************** MF=33 ************************** 825 1451 219 825 1451 220 TO BE PROVIDED AT A LATER DATE. 825 1451 221 825 1451 222 --------------------------- REFERENCES -------------------------- 825 1451 223 825 1451 224 AD49 R.K.ADAIR ET AL., PHYS. REV. 75, 1124 (1949) 825 1451 225 AJ86A F.AJZENBERG-SELOVE, NUCL. PHYS. A460,1 (1986) 825 1451 226 AJ86B F.AJZENBERG-SELOVE, NUCL. PHYS. A449,1 (1986) 825 1451 227 BA63 R.W.BAUER ET AL., NUCL. PHYS. 47, 241 (1963) 825 1451 228 BA73 J.K.BAIR AND F.X.HAAS, PHYS.REV.C7,1356 (1973) 825 1451 229 (N,A0) XSECT. OBTAINED BY DETAILED BALANCE FROM THIS REF. 825 1451 230 BA85 M.BABA ET AL., 1985 SANTA FE NUC.DATA CONF. 1, P223 825 1451 231 BE67 P.L.BEACH ET AL., PHYS. REV. 156, 1201 (1967) 825 1451 232 BO66 M.BORMANN ET AL., PROC. IAEA CONF. NUCL. DATA, 825 1451 233 PARIS (1966), P.225 825 1451 234 BO73 M.BORMANN, ZEIT.PHYS. 258, 285 (1973) 825 1451 235 BO89 G.BORKER, W.MANNHART ET AL., PTB-N-1 (1989) AND 825 1451 236 PERSONAL COMMUNICATION 825 1451 237 BU71 P.S.BUCHANAN ET AL., ORO-2791-32 (1971) 825 1451 238 BU73 W.P.BUCHER ET AL., BRL-R-1652 (1973) 825 1451 239 CH61 L.F.CHASE ET AL., AFSWC-TR-61-15 (1961) 825 1451 240 CI68 S.CIERJACKS ET AL., KFK-1000 (1968) 825 1451 241 CI80 S.CIERJACKS ET AL., NUC.INST.METH. 169, 185 (1980) 825 1451 242 CL69 G.CLAYEUX+G.GRENIER, CEA-R-3807 (1969) 825 1451 243 DA63 E.A.DAVIS ET AL., NUCL. PHYS. 48, 169 (1963) 825 1451 244 DA68 D.DANDY ET AL., AWRE O60/68 (1968) 825 1451 245 DE62 J.A.DEJUREN ET AL., PHYS. REV. 127, 1229 (1962) 825 1451 246 DI70 J.K.DICKENS+F.G.PEREY, NUCL. SCI. ENG. 40, 283 (1970) 825 1451 247 DR70 D.M.DRAKE ET AL., NUCL. SCI. ENG. 40, 294 (1970) 825 1451 248 DR76 L.DRIGO ET AL., NC/A 31,(1), (1976). 825 1451 249 DU70 C.DUNFORD, AI-AEC-12931 (1970). 825 1451 250 EN64 F.C.ENGESSER+W.E.THOMPSON, J. NUCL. ENG. 21, 487 (1967) 825 1451 251 FO58 J.L.FOWLER AND H.O.COHN, PHYS.REV. 109,89 (1958) 825 1451 252 FO64 J.L.FOWLER AND C.H.JOHNSON, ORNL-3582, P.90 (1964). 825 1451 253 FO70 J.L.FOWLER AND C.H.JOHNSON, PHYS.REV.C2,124 (1970) 825 1451 254 FO71 D.FOSTER & D.GLASGOW, PHYS.REV.C3, 576 (1971). 825 1451 255 FO73 J.L.FOWLER ET.AL., PHYS.REV. C8,545 (1973) 825 1451 256 GL82 S.GLENDINNING ET AL., NUC.SCI.ENG. 82, 393 (1982) 825 1451 257 HA59 H.HALL ET AL., NUC.PHYS.14, 295 (1959). 825 1451 258 HE80 D.HETRICK & C.Y.FU, ORNL/TM-7341 (1980). 825 1451 259 HI58 R.W.HILL, PHYS.REV. 109,2105 (1958) 825 1451 260 HU62 W.HUNZINGER AND P.HUBER, HELV.PHYS.ACTA 35,351 (1962) 825 1451 261 IS87 M.ISLAM ET AL., NUC.PHYS. A464, 395 (1987) 825 1451 262 JO48 W.B.JONES,JR., PHYS. REV. 74, 364 (1948) 825 1451 263 JO67 C.H.JOHNSON AND J.L.FOWLER, PHYS.REV. 162,890 (1967) 825 1451 264 JO73 C.H.JOHNSON, PHYS.REV. C7,561 (1973) 825 1451 265 JO79 C.JOHSON & J.FOWLER, 1979 KNOXVILLE NUC.DATA CONF. 825 1451 266 JU64 E.T.JURNEY AND H.T.MOTZ, BULL.AM.PHYS.SOC. 9, 176 (1964) 825 1451 267 KI72 W.E.KINNEY AND F.G.PEREY, ORNL-4780 (1972) 825 1451 268 KU76 P.D.KUNZ, UNPUBLISHED REPORT (1976). 825 1451 269 LA60 R.O.LANE ET.AL., ANL-6172 (1960) 825 1451 270 LA80 D.LARSON ET AL., 1980 BNL CONF. ON 10-50 MEV DATA & 825 1451 271 PERSONAL COMMUNICATION (1989) 825 1451 272 LE68 B.LEROUX ET AL., NUCL. PHYS. A116, 196 (1968) 825 1451 273 LI52 A.B.LILLIE, PHYS. REV. 87, 716 (1952) 825 1451 274 LI66 D.LISTER AND A.SAYRES, PHYS.REV. 143,745 (1966) 825 1451 275 LU70 B.LUNDBERG ET AL., PHYSICA SCRIPTA 2, 273 (1970) 825 1451 276 MA54 H.C.MARTIN, PHYS. REV. 93, 498 (1954) 825 1451 277 MA62 J.P.MARTIN AND M.S.ZUCKER, BULL.AM.PHYS.SOC. 7,72 (1962) 825 1451 278 MA68 D.R.MAXSON + R.D.MURPHY, NUCL. PHYS. A110, 555 (1968) 825 1451 279 MC66 W.J.MCDONALD ET AL., NUCL. PHYS. 75, 353 (1966) 825 1451 280 MC66A W.N.MCDICKEN + W.JACK, NUCL. PHYS. 88, 457 (1966) 825 1451 281 ME49 E.MELKONIAN, PHYS. REV. 76, 1750 (1949) 825 1451 282 MO79 G.MORGAN ET AL., ORNL-5575 (1979) 825 1451 283 MU81 S.MUGHABGHAB ET AL., NEUT.CROSS SECT.,VOL.1, NEUT.RESON. 825 1451 284 PARA. AND THER. CROSS SECT., ACADEMIC PRESS (1981). 825 1451 285 NE72 D.O.NELLIS AND P.S. BUCHANAN, DNA-2716 (1972) 825 1451 286 NE90 R.NELSON ET AL., LANL (WNR), PERS. COMMUNICATION,3/1990. 825 1451 287 NO78 C.NORDBORG ET AL., NUC.SCI.ENG. 66, 75 (1978) 825 1451 288 NY71 K.NYBERG, P.S. 4, 165 (1971) 825 1451 289 OH84 M.OHKUBO ET AL., PERS.COMMUNICATION TO NNDC, BNL 825 1451 290 OL90 N. OLSSON ET AL., NUC. PHYS. A509, 161 (1990) 825 1451 291 OK55 A.OKAZAKI, PHYS. REV. 99, 55 (1955) 825 1451 292 OR70 V.J.ORPHAN ET AL., NUCL. SCI. ENG. 42, 352 (1970) 825 1451 293 PE72 F.PEREY ET AL., ORNL-4823 (1972). 825 1451 294 PE85 J.PETLER ET AL., PHYS.REV. C32, 673 (1985) 825 1451 295 PH61 D.D.PHILLIPS, PRIVATE COMMUNICATION TO BNL (1961) 825 1451 296 SC72A R.SCHRACK, BAPS 17, 555 (1972) 825 1451 297 SC72B M.SCHMIDT-HOENOW, RCA 17, 142 (1972) 825 1451 298 SC77 I.SCHOUKY ET AL., KFK-2503 825 1451 299 SE62 K.W.SEEMANN+W.E.MOORE, KAPL-2214 (1962) 825 1451 300 SE86 F.SELOVE, NUC.PHYS.A000, XXX (1986). 825 1451 301 SI68 VON I. SICK ET AL., HELV. PHYS. ACTA 41, 573 (1968) 825 1451 302 SL65 E.L.SLAGGIE+J.T.REYNOLDS, KAPL-M-6452 (1965) 825 1451 303 TA83 A.TAKAHASHI ET AL., OKTAV-A-83-01 825 1451 304 YA78 T.YAMAMOTO ET AL., NST 15, 797 (1978) 825 1451 305 YO77 P.YOUNG & E.ARTHUR, LA-6947 (1977). 825 1451 306 825 1451 307 1 451 309 1 825 1451 308 3 103 27 1 825 1451 309 825 1 0 310 825 0 0 311 8.016000+3 1.585316+1 0 0 0 0 825 3103 312 -9.636786+6-9.636786+6 0 0 1 72 825 3103 313 72 2 0 0 0 0 825 3103 314 1.024466+7 0.000000+0 1.040000+7 2.401300-4 1.050000+7 5.000000-4 825 3103 315 1.060000+7 1.058100-4 1.070000+7 2.500000-4 1.080000+7 2.604100-3 825 3103 316 1.090000+7 5.333300-3 1.100000+7 7.000000-3 1.110000+7 9.000000-3 825 3103 317 1.120000+7 1.500000-2 1.130000+7 2.000000-2 1.150000+7 3.500000-2 825 3103 318 1.160000+7 5.000000-2 1.170000+7 7.000000-2 1.180000+7 8.543890-2 825 3103 319 1.190000+7 6.938207-2 1.200000+7 4.669714-2 1.210000+7 3.035838-2 825 3103 320 1.220000+7 2.365615-2 1.230000+7 2.075648-2 1.240000+7 2.056038-2 825 3103 321 1.250000+7 2.168366-2 1.260000+7 2.308315-2 1.270000+7 2.488499-2 825 3103 322 1.280000+7 2.725277-2 1.290000+7 3.021781-2 1.300000+7 3.354743-2 825 3103 323 1.310000+7 3.709179-2 1.320000+7 4.143062-2 1.330000+7 4.555740-2 825 3103 324 1.340000+7 4.726000-2 1.350000+7 4.674878-2 1.360000+7 4.595329-2 825 3103 325 1.370000+7 4.509407-2 1.380000+7 4.432629-2 1.390000+7 4.358945-2 825 3103 326 1.400000+7 4.279723-2 1.410000+7 4.182953-2 1.420000+7 4.068439-2 825 3103 327 1.430000+7 3.950085-2 1.440000+7 3.838027-2 1.450000+7 3.715740-2 825 3103 328 1.460000+7 3.593394-2 1.470000+7 3.493238-2 1.480000+7 3.521347-2 825 3103 329 1.490000+7 3.650241-2 1.500000+7 3.785617-2 1.510000+7 3.825563-2 825 3103 330 1.520000+7 3.736526-2 1.530000+7 3.605877-2 1.540000+7 3.455737-2 825 3103 331 1.550000+7 3.255589-2 1.560000+7 3.157099-2 1.570000+7 3.212100-2 825 3103 332 1.580000+7 3.302726-2 1.590000+7 3.408018-2 1.600000+7 3.465000-2 825 3103 333 1.610000+7 3.429268-2 1.620000+7 3.339000-2 1.630000+7 3.231482-2 825 3103 334 1.640000+7 3.121989-2 1.650000+7 3.031900-2 1.660000+7 2.959827-2 825 3103 335 1.670000+7 2.893049-2 1.680000+7 2.833260-2 1.700000+7 2.740500-2 825 3103 336 1.750000+7 2.572500-2 1.800000+7 2.425500-2 1.850000+7 2.352000-2 825 3103 337 1.900000+7 2.289000-2 1.950000+7 2.241700-2 2.000000+7 2.194500-2 825 3103 338 825 3 0 339 825 0 0 340 0 0 0 341 8.017000+3 1.685310+1 -1 0 0 0 828 1451 1 0.000000+0 0.000000+0 0 0 0 6 828 1451 2 1.000000+0 0.000000+0 0 0 10 6 828 1451 3 0.000000+0 0.000000+0 0 0 106 3 828 1451 4 8-O - 17 BNL EVAL-JAN78 B.A.MAGURNO 828 1451 5 DIST-JAN90 900123 828 1451 6 ----ENDF/B-VI MATERIAL 828 828 1451 7 -----INCIDENT NEUTRON DATA 828 1451 8 ------ENDF-6 FORMAT 828 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 828 1451 10 ACTIVATION I 828 1451 11 ****************************************************************** 828 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 828 1451 13 * * * * * * * 828 1451 14 **************************************************************** 828 1451 15 DOCUMENTATION INCLUDED IN EPRI-NP-973 1978 ALAPOUR ET.AL. 828 1451 16 **************************************************************** 828 1451 17 THERMAL CROSS SECTIONS 828 1451 18 N,GAMMA=3.8 MB+/-20PC CALCULATED BY S.F.MUGHABGHAB 828 1451 19 (MU78) USING METHOD OF LANE + LYNN (SEE DOCUMENT) 828 1451 20 N,ALPHA=235 MILLIBARNS WEIGHTED AVERAGE OF(HA61), 828 1451 21 (SE56),(MA47). 828 1451 22 N,ABSORPTION=238.8 MB. TOTAL OF ABOVE. 828 1451 23 THESE CROSS SECTIONS ASSUMED TO BE I/V TO APPROX 100KEV. 828 1451 24 **************************************************************** 828 1451 25 SINCE VIRTUALLY NO EXPERIMENTAL DATA AVAILABLE,THIS EVALUATION 828 1451 26 IS ALMOST TOTALLY CALCULATED WITH NUCLEAR MODEL CODES. 828 1451 27 **************************************************************** 828 1451 28 MF=2 MT=151 NO RESONANCE PARAMETER DATA AVAILABLE.SMOOTH CROSS 828 1451 29 SECTIONS CALCULATED IN THE RESONANCE REGION CONSTRUED AS 828 1451 30 "AVERAGE"CROSS SECTIONS. 828 1451 31 **************************************************************** 828 1451 32 MF=3 MT=1 TOTAL CROSS SECTION IS CALCULATED AS SUM OF THE CROSS 828 1451 33 SECTIONS LISTED BELOW.IN GOOD AGREEMENT WITH PRELIMINARY 828 1451 34 MEASUREMENTS BY AUCHAMPAUGH(AU77). 828 1451 35 **** MT=2 TOTAL ELASTIC CROSS AT LOW ENERGY DERIVED FROM 828 1451 36 EXP.MEASURED COHERENT SCATTERING AMPLITUDE. (VA68) HIGH 828 1451 37 ENERGY CROSS SECTION CALCULATED WITH NUBAK (AN IN-HOUSE 828 1451 38 VERSION OF"ABACUS")(AU64) 828 1451 39 **** MT=4 DERIVED FROM THE SUMMATION OF MT=51-62 AND MT=91 828 1451 40 **** MT=51-62,91 THESE LEVELS CALCULATED WITH NUCLEAR MODEL 828 1451 41 CODES "MODNEW"(AN IN-HOUSE VERSION OF UHL'S CODE)(UH72) 828 1451 42 MODIFIED FOR GILBERT AND CAMERON PARAMETERS(SEE DOCUMENT 828 1451 43 ABOVE) AND"COMNUC" (DU70). COMNUC RESULTS NORMALIZED TO 828 1451 44 HIGH ENERGY MODNEW RESULTS TO ALLOW FOR COMPETING REACTIONS 828 1451 45 **** MT=16 CALCULATED WITH"MODNEW"(UH72) NO NORMALIZATION 828 1451 46 AVAILABLE. 828 1451 47 **** MT=22 CALCULATED WITH"MODNEW"(UH72) NO NORMALIZATION 828 1451 48 AVAILABLE. 828 1451 49 **** MT=28 CALCULATED WITH"MODNEW"(UH72) NO NORMALIZATION 828 1451 50 AVAILABLE. 828 1451 51 **** MT=102 CALCULATED WITH"COMNUC"(DU70).LEVEL SPACING ASSUMED 828 1451 52 AND GAMMA GAMMA ASSUMED.2PI GAMMA GAMMA OVER D =0.000063. 828 1451 53 CROSS SECTION AT 14.0 MEV=0.1MILLIBARN. 828 1451 54 **** MT=103 CALCULATED WITH"MODNEW"(UH72).NEUTRON YIELD 828 1451 55 ACTIVATION MEASUREMENT AT 14.1 MEV=21.5+-1.7 MILLIBARNS BY 828 1451 56 MENLOVE (ME70) SUPPORTS CALCULATION VALUE 14.1MEV=40 MILLI- 828 1451 57 BARNS. 828 1451 58 **** MT=104 CALCULATED WITH"MODNEW(UH72) NO NORMALIZATION 828 1451 59 AVAILABLE. 828 1451 60 **** MT=107 N,ALPHA CROSS SECTION EXOERGIC.CALCULATED WITH 828 1451 61 "MODNEW"(UH72).NO NORMALIZATION AVAILABLE.CALCULATIONS BY 828 1451 62 ARTHUR(AR77) WITH LASL VERSION OF"COMNUC" SHOW SIMILAR 828 1451 63 SHAPE AND MAGNITUDE. 828 1451 64 **************************************************************** 828 1451 65 MF=4 MT=2 ELASTIC ANGULAR DISTRIBUTIONS CALCULATED WITH"NUBAK" 828 1451 66 AS A KLASS 3 PROBLEM(AU64) 828 1451 67 **** MT=16,22,28,91 GIVEN AS ISOTROPIC IN LAB SYSTEM 828 1451 68 **** M=51-62 GIVEN AS ISOTROPIC IN THE C.O.M. SYSTEM 828 1451 69 **************************************************************** 828 1451 70 MF=5 MT=16,22,28,91 TEMPERATURE DISTRIBUTIONS AS A FUNCTION OF 828 1451 71 ENERGY CALCULATED PER PRESCRIPTION OF GILBERT AND CAMERON 828 1451 72 (GI65) 828 1451 73 **************************************************************** 828 1451 74 AJ77 F.AJZENBERG-SELOVE ENERGY LEVELS OF LIGHT NUCLEI 828 1451 75 A=18 PPP1-77 FEB.1977 828 1451 76 A=16-17 NUC.PHYS.A281,1,1977 828 1451 77 A=13-15 NUC.PHYS.A268,1,1976 828 1451 78 A=11-12 NUC.PHYS.A248,1,1975 828 1451 79 A= 5-10 NUC.PHYS.A227,1,1974 828 1451 80 AR77 E.ARTHUR LASL PRIVATE COMM. 1977 828 1451 81 AU77 G.AUCHAMPAUGH LASL PRIVATE COMM. 1977 828 1451 82 AU64 E.H.AUERBACH,ABACUS-2 BNL 6562 1964 828 1451 83 BA70 H.BABA NUC.PHYS.A159,625,1970 828 1451 84 BA66 J.K.BAIR ET.AL. PHYS.REV.144,799,1966 828 1451 85 BE74 I.BERGQVIST PROC.2ND INT SYMP ON NEUTRON CAPTURE GAMMA 828 1451 86 RAY SPECTROSCOPY AND RELATED TOPICS,199,1974 828 1451 87 DU70 C.L.DUNFORD,COMNUC AI-AEC-12931,1970 828 1451 88 FE E.FERMI NUCLEAR PHYSICS U.OF CHI PRESS PP-145-146 REV. 828 1451 89 EDITION 828 1451 90 GI65 A.GILBERT AND A.G.W.CAMERON,CAN.J.PHYS.43,1446,1965 828 1451 91 GR50 A.E.S.GREEN AND D.F.EDWARDS PHYS.REV.91,49,1952 828 1451 92 HA61 G.C.HANNA ET.AL.CAN.J.PHYS.39,1784,1961 828 1451 93 HO72 N.E.HOLDEN AND W.F.WALKER,G.E.CHART OF NUCLIDES 11TH 828 1451 94 ED.REVISED TO 1972 828 1451 95 MA47 A.N.MAY AND E.P.HINCKS CAN.J.RES.A25,77,1947 828 1451 96 MA50 M.G.MAYER PHYS.REV.78,77,1960 828 1451 97 MC77 A.B.MCDONALD ET.AL.NUC.PHYS.A281,325,1977 828 1451 98 ME70 H.O.MENLOVE ET.AL. NSE 40,136,1970 828 1451 99 MO70 G.L.MORGAN ET.AL. NUC.PHYS.148,480,1970 828 1451 100 MU78 S.F.MUGHABGHAB PC-78 METHOD BNL-NCS25086R(TBP PHY.LET) 828 1451 101 MU73 S.F.MUGHABGHAB AND D.I.GARBER BNL-325 3RD ED.VOLI 1973 828 1451 102 PE74 C.M.PEREY AND F.G.PEREY AT.DATA TABLES 13,293,1974 828 1451 103 RO77 P.ROSE BNL PRIV.COMM. 1977 828 1451 104 SE56 E.J.SEPPI HANFORD PRIV.COMM TO SIGMA CNTR 1956 828 1451 105 UH72 M.UHL NUC.PHYS.A184,253,1972 828 1451 106 VA68 T.M.VALENTINE AERE-R5770,1968 828 1451 107 VO69 H.K.VONACH AND M.HILLE NUC.PHYS.A127,289,1969 828 1451 108 WI64 D.WILMORE AND P.E.HODGSON NUC.PHYS.55,673,1964 828 1451 109 **************************************************************** 828 1451 110 1 451 113 0 828 1451 111 3 103 8 0 828 1451 112 3 107 17 0 828 1451 113 828 1 0 114 828 0 0 115 8.017000+3 1.685310+1 0 0 0 0 828 3103 116 -7.896000+6-7.896000+6 0 0 1 14 828 3103 117 14 2 0 0 0 0 828 3103 118 8.364520+6 0.000000+0 9.340000+6 2.000000-4 1.014000+7 1.200000-3 828 3103 119 1.093000+7 3.300000-3 1.173000+7 9.500000-3 1.331000+7 2.900000-2 828 3103 120 1.411000+7 4.200000-2 1.490000+7 5.458000-2 1.570000+7 6.441000-2 828 3103 121 1.729000+7 7.313000-2 1.808000+7 7.260000-2 1.878000+7 7.006000-2 828 3103 122 1.967000+7 6.584000-2 2.000000+7 6.400000-2 0.000000+0 0.000000+0 828 3103 123 828 3 0 124 8.017000+3 1.685310+1 0 0 0 0 828 3107 125 1.819400+6 1.819400+6 0 0 2 40 828 3107 126 3 5 40 2 0 0 828 3107 127 1.000000-5 1.182030+1 2.530000-2 2.350000-1 1.000000+4 3.737900-4 828 3107 128 2.000000+4 3.000000-4 4.000000+4 2.500000-4 7.000000+4 3.000000-4 828 3107 129 1.000000+5 1.000000-3 1.500000+5 2.750000-3 2.000000+5 5.250000-3 828 3107 130 2.500000+5 9.000000-3 3.000000+5 1.575000-2 3.500000+5 3.000000-2 828 3107 131 4.000000+5 4.375000-2 4.500000+5 5.750000-2 4.750000+5 6.375000-2 828 3107 132 5.000000+5 7.000000-2 6.250000+5 8.650000-2 7.500000+5 9.350000-2 828 3107 133 9.000000+5 9.950000-2 1.000000+6 1.030000-1 2.200000+6 1.170000-1 828 3107 134 2.990000+6 1.180000-1 3.790000+6 1.120000-1 5.370000+6 8.300000-2 828 3107 135 6.170000+6 7.000000-2 6.960000+6 7.996000-2 7.760000+6 1.120300-1 828 3107 136 9.340000+6 2.108000-1 1.014000+7 2.412500-1 1.093000+7 2.571600-1 828 3107 137 1.173000+7 2.664800-1 1.331000+7 2.733500-1 1.411000+7 2.606500-1 828 3107 138 1.490000+7 2.427600-1 1.570000+7 2.240900-1 1.729000+7 1.904200-1 828 3107 139 1.808000+7 1.754200-1 1.878000+7 1.606100-1 1.967000+7 1.437600-1 828 3107 140 2.000000+7 1.300000-1 0.000000+0 0.000000+0 0.000000+0 0.000000+0 828 3107 141 828 3 0 142 828 0 0 143 0 0 0 144 9.019000+3 1.883500+1 0 0 0 1 925 1451 1 0.000000+0 0.000000+0 0 0 0 6 925 1451 2 1.000000+0 0.000000+0 0 0 10 6 925 1451 3 0.000000+0 0.000000+0 0 0 151 6 925 1451 4 9-F - 19 CNDC,ORNL EVAL-JUN90 Z.X.ZHAO,C.Y.FU,D.C.LARSON 925 1451 5 DIST-JUN90 900607 925 1451 6 ----ENDF/B-VI MATERIAL 925 925 1451 7 -----INCIDENT NEUTRON DATA 925 1451 8 ------ENDF-6 FORMAT 925 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE***************** 925 1451 10 ACTIVATION I 925 1451 11 ****************************************************************** 925 1451 12 * * * * * * * 925 1451 13 925 1451 14 **************************************************************** 925 1451 15 THIS EVALUATION IS BASED ON MEASURED DATA AVAILABLE ON CSISRS 925 1451 16 DATA TAPE (CS90) AND A THEORETICAL CALCULATION BY TNG CODE 925 1451 17 ( STATISTICAL AND PRECOMPOUND THEORY CODE, SH86,FU88). 925 1451 18 FILE 2. RESONANCE PARAMETERS 925 1451 19 SECTION 151--ONLY SCATTERING LENGTH(KO79) IS GIVEN. 925 1451 20 FILE 3. NEUTRON CROSS SECTION 925 1451 21 SECTION 1. TOTAL INTERACTION 925 1451 22 1.0E-05 TO 10 EV--SUM OF FREE ATOM SCATTERING CROSS 925 1451 23 SECTION AND THE CAPTURE CROSS SECTION. 925 1451 24 10 EV TO 2.0 MEV--CALCULATED FROM A SET OF RESONANCE 925 1451 25 PARAMETERS WHICH WERE ADJUSTED TO FIT THE HIGH 925 1451 26 RESOLUTION MEASURED TOTAL CROSS SECTIOS(LA76) BY 925 1451 27 USING SAMMY CODE(MULTI-LEVEL R-MATRIX ANALYSIS CODE, 925 1451 28 LA87). 925 1451 29 2.0 MEV TO 20 MEV--THE VALUES OF ENDF/B-V ARE USED. 925 1451 30 SECTION 2. ELASTIC SCATTERING 925 1451 31 OBTAINED BY SUBTRACTING THE NON-ELASTIC CROSS SECTION 925 1451 32 FROM TOTAL CROSS SECTION. 925 1451 33 SECTION 3. NON-ELASTIC SCATTERING 925 1451 34 OBTAINED BY 925 1451 35 MT3=MT4+MT16+MT22+MT28+MT102+MT103+MT104+MT105+MT107 925 1451 36 SECTION 4. TOTAL INELASTIC SCATTERING 925 1451 37 OBTAINED BY SUMMING MT=51-71 AND 91. 925 1451 38 SECTION 16. (N,2N) REACTION 925 1451 39 CALCULATED BY TNG CODE. 925 1451 40 SECTION 22. (N,NA)+(N,AN) REACTION 925 1451 41 CALCULATED BY TNG CODE. 925 1451 42 SECTION 28. (N,NP)+N,PN) REACTION 925 1451 43 CALCULATED BY TNG CODE. 925 1451 44 SECTIONS 51 AND 52. INELASTIC SCATTERING FOR 925 1451 45 FIRST AND SECOND LEVELS 925 1451 46 OBTAINED BY CS(EX)/MG(TNG). CS(EX) DENOTES MEASURED 925 1451 47 110 KEV AND 197 KEV G-RAY PRODUCTION CROSS SECTION 925 1451 48 (MO74), MG(TNG) ARE MULTIPLICITIES FOR 110 KEV AND 925 1451 49 197 KEV CALCULATED BY TNG. 925 1451 50 SECTIONS 53 - 71. INELASTIC SCATTERING FOR OTHER LEVELS 925 1451 51 CALCULATED BY TNG AND DWUCK(KU72). 925 1451 52 SECTION 91. CONTINUUM INELASTIC SCATTERING 925 1451 53 CALCULATED BY TNG. 925 1451 54 SECTION 102. (N,GAMMA) REACTION 925 1451 55 1.0E-05 EV TO 2.0 MEV--CALCULATED BY SAMMY CODE BY 925 1451 56 USING A SET OF RESONANCE PARAMETERS USED IN THE 925 1451 57 CALCULATION FOR TOTAL CROSS SECTIONS BUT G-WIDTHS 925 1451 58 WERE ADJUSTED TO FIT MEASURED DATA(MA63,GA59). ABOVE 925 1451 59 2.0 MEV, CAPTURE CROSS SECTIONS ARE VERY SMALL SO 925 1451 60 WE USE 1/E TO EXTRAPOLATE TO 20 MEV. 925 1451 61 SECTION 103. (N,P) REACTION 925 1451 62 EN < 8.0 MEV, ENDF/B-V REMAIN UNCHANGED. ABOVE 8.0 MEV 925 1451 63 CALCULATED BY TNG CODE. 925 1451 64 SECTION 104. (N,D) REACTION 925 1451 65 CALCULATED FROM SYSTEMATICS(ZH88). 925 1451 66 THE EXCITATION FUNCTION WAS NORMALIZED TO 22 MB GIVEN 925 1451 67 BY INTEGRATING EARLY ANGULAR DISTRIBUTION DATA(FA68, 925 1451 68 RE68) AT EN=14 MEV. 925 1451 69 SECTION 105. (N,T) REACTION 925 1451 70 CALCULATED FROM SYSTEMATICS(ZH88). THE EXCITATION 925 1451 71 FUNCTION WAS NORMALIZED TO SPECTRUM AVERAGED MEASURED 925 1451 72 DATA(QA78). 925 1451 73 SECTION 107. (N,A) REACTION 925 1451 74 EN < 9.0 MEV, ENDF/B-V REMAIN UNCHANGED. ABOVE 9.0 MEV 925 1451 75 CALCULATED BY TNG CODE. 925 1451 76 FILE 4. ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 925 1451 77 SECTION 2. ELASTIC SCATTERING 925 1451 78 THE LEGENDRE COEFFICIENTS ARE CALCULATED BY GENOA CODE 925 1451 79 (OPTICAL MODEL CODE, PE67) WITH COMPOUND CROSS 925 1451 80 SECTIONS AND LEGENDRE COEFFICIENTS CALCULATED BY TNG 925 1451 81 AS INPUT. BEFORE CALCULATION, OPTICAL MODEL 925 1451 82 PARAMETERS WERE ADJUSTED TO FIT MEASURED ANGULAR 925 1451 83 DISTRIBUTIONS(BA85 AND CL70). SAME OPTICAL 925 1451 84 MODEL PARAMETERS WERE USED IN TNG,DWUCK AND GENOA 925 1451 85 CALCULATIONS. 925 1451 86 SECTIONS 51-71. INELASTIC SCATTERING 925 1451 87 THE CROSS SECTIONS CS(D), LEGENDRE COEFFICIENTS FL(D) 925 1451 88 CONTRIBUTED FROM DIRECT INTERACTION WERE 925 1451 89 CALCULATED BY DWUCK AND CS(S),FL(S) FROM STATISTICAL 925 1451 90 BY TNG. USING 925 1451 91 CS(D)*FL(D) + CS(S)*FL(S) 925 1451 92 FL = ------------------------------ 925 1451 93 CS(D) + CS(S) 925 1451 94 FILE 6. DOUBLE DIFFERENTIAL CROSS SECTIONS(DDCS) 925 1451 95 THE DDCS FOR ALL SECTIONS WERE OBTAINED BASED ON TNG 925 1451 96 CALCULATIONS FOR THE FIRST OUTGOING NEUTRONS ONLY. FOR 925 1451 97 THE SECOND OUTGOING NEUTRONS AND BOTH THE FIRST AND 925 1451 98 SECOND OUTGOING CHARGED PARTICLES, THE ANGULAR 925 1451 99 DISTRIBUTIONS WERE ASSUMED ISOTROPIC. RECOIL SPECTRA 925 1451 100 WERE GENERATED AS THE CALCULATED PARTICLE SPECTRA WERE 925 1451 101 CONVERTED TO THE LAB. SYSTEM. 925 1451 102 FILE 8. RADIOACTIVE DECAY DATA 925 1451 103 FILE 9. MULTIPLICITIES FOR PRODUCTION OF RADIOACTIVE 925 1451 104 NUCLIDES 925 1451 105 FILE 12. TRANSITION PROBABILITY ARRAYS 925 1451 106 SECTIONS 51-71. 925 1451 107 BASED ON (AJ87) 925 1451 108 FILE 14. PHOTON ANGULAR DISTRIBUTION 925 1451 109 SECTIONS 51-71. INELASTIC SCATTERING 925 1451 110 ISOTROPIC. 925 1451 111 FILE 33. UNCERTANTIES OF FILE 3 925 1451 112 SECTIONS 1,51,52,102,103 AND 107: 925 1451 113 SAME AS ENDF/B-V BUT SUPPLEMENTED A SUB-SUBSECTION 925 1451 114 OF LB=8 FOR EVERY SECTION. 925 1451 115 SECTION 2 AND 3: 925 1451 116 USING "NC-TYPE" SUB-SUBSECTION FOR THESE TWO DERIVED 925 1451 117 CROSS SECTIONS. 925 1451 118 SECTIONS 4,16,22 AND 28: 925 1451 119 CALCULATED FROM A COVARIANCE MATRIX OF THEORETICAL 925 1451 120 PARAMETERS (SEVERAL MOST SENSITIVE PARAMETERS WERE 925 1451 121 CHOSEN AS FOLLOWS: ENERGY LEVEL DENSITY PARAMETERS 925 1451 122 FOR F-19, O-19 AND N-16; OPTICAL MODEL PARAMETERS FOR 925 1451 123 F-19: V0 AND W FOR REAL AND IMAGINARY WELL DEPTHS, RU 925 1451 124 AND RW FOR THE RADIUS OF REAL AND IMAGINARY POTENTIAL). 925 1451 125 THE COVARIANCE MATRIX FOR THEORETICAL PARAMETERS 925 1451 126 WERE ESTIMATED BASED ON SCATTER OF MEASURED DATA 925 1451 127 AVAILABLE AROUND THEORETICAL VALUES AND SYSTEMATIC 925 1451 128 ERROR OF MEASURED DATA. A SUB-SUBSECTION OF LB=8 925 1451 129 ARE ALSO GIVEN FOR EVERY SECTION. 925 1451 130 SECTIONS 104 AND 105: 925 1451 131 CALCULATED FROM COVARIANCE MATRIX OF SYSTEMATICS 925 1451 132 PARAMETERS (ZH88). A SUB-SUBSECTION OF LB=8 925 1451 133 ARE ALSO GIVEN FOR EVERY SECTION. 925 1451 134 REFFERENCES 925 1451 135 AJ88 F.AJZENBERG-SELOVE, A475,1(1987) 925 1451 136 BA85 M.BABA ET AL., PROC. OF CONF. ON NUCL.DATA FOR BASIC 925 1451 137 AND APPLIED SCIENCE, SANTA FE, MAY 1985 925 1451 138 CL70 W.CLARKE ET AL., NUCL.PHYS.,A147,174(1970) 925 1451 139 CS90 EXFOR DATA ON CSISRS TAPE OF NNDC,BNL(1990) 925 1451 140 FA68 M.FAZIO ET AL., NUCL.PHYS.,A111,255 925 1451 141 FU88 C.Y.FU, NUCL.SCI. AND ENG., 100,61(1988) 925 1451 142 GA59 F.GABBARD ET AL., PHYS.REV.,114,201,1959 925 1451 143 KO79 L.KOESTER ET AL., Z.PHYSIK,A292,95(1979) 925 1451 144 KU72 P.D.KUNZ, "DISTORED WAVE CODE DWUCK72",UNIVERSITY OF 925 1451 145 COLORADO(1972) 925 1451 146 LA76 D.C.LARSON ET AL., ORNL-TM-5612(1976) 925 1451 147 LA87 N.M.LARSON, ORNL/TM-9179(1987) 925 1451 148 MA63 R.L.MACKLIN ET AL., PHYS.REV.,C7,1766(1963) 925 1451 149 M074 G.L.MORGAN AND J.K.DICKENS,ORNL/TM-4823(1974) 925 1451 150 PE67 F.G.PEREY, COMPUTER CODE GENOA,ORNL,UNPUBLISHED(1967) 925 1451 151 QA78 S.M.QAIM ET AL.,NUCL.PHYS.,A295,150,1978 925 1451 152 SH86 K. SHIBATA AND C.Y.FU, ORNL/TM-10093(1986) 925 1451 153 ZH88 Z.ZHAO AND Z.ZHOU, NUCL.SCI.AND ENG.,99,367(1988) 925 1451 154 ***************************************************************** 925 1451 155 1 451 161 1 925 1451 156 2 151 4 1 925 1451 157 3 16 8 1 925 1451 158 3 102 291 1 925 1451 159 33 16 32 1 925 1451 160 33 102 8 1 925 1451 161 925 1 0 162 925 0 0 163 9.019000+3 1.883500+1 0 0 1 0 925 2151 164 9.019000+3 1.000000+0 0 0 1 0 925 2151 165 1.000000-5 2.000000+7 0 0 0 0 925 2151 166 5.000000-1 5.360000-1 0 0 0 0 925 2151 167 925 2 0 168 925 0 0 169 9.019000+3 1.883500+1 0 0 0 0 925 3 16 170 -1.043100+7-1.043100+7 0 0 2 14 925 3 16 171 2 1 14 2 0 0 925 3 16 172 1.098700+7 0.000000+0 1.100000+7 0.000000+0 1.150000+7 1.500000-3 925 3 16 173 1.200000+7 4.545000-3 1.250000+7 1.400000-2 1.300000+7 2.400000-2 925 3 16 174 1.350000+7 3.500000-2 1.410000+7 4.162000-2 1.500000+7 5.726000-2 925 3 16 175 1.600000+7 7.329000-2 1.700000+7 7.975000-2 1.800000+7 8.624000-2 925 3 16 176 1.900000+7 9.682000-2 2.000000+7 1.026000-1 0.000000+0 0.000000+0 925 3 16 177 925 3 0 178 9.019000+3 1.883500+1 0 0 0 0 925 3102 179 6.601300+6 6.601300+6 0 0 3 862 925 3102 180 20 5 861 2 862 5 925 3102 181 1.000000-5 4.800000-1 1.000000-3 4.800000-2 2.530000-2 9.550000-3 925 3102 182 1.000000-1 4.803040-3 1.000000+0 1.519134-3 4.500000+0 7.166380-4 925 3102 183 1.000000+1 4.814107-4 2.400000+1 3.133841-4 1.000000+2 1.549994-4 925 3102 184 1.530000+2 1.266726-4 1.000000+3 5.842763-5 1.266000+3 5.458190-5 925 3102 185 2.000000+3 4.960634-5 3.000000+3 4.817222-5 4.000000+3 4.927807-5 925 3102 186 5.000000+3 5.181380-5 6.000000+3 5.543169-5 7.000000+3 6.004497-5 925 3102 187 8.000000+3 6.569452-5 8.392000+3 6.821586-5 9.000000+3 7.250895-5 925 3102 188 1.000000+4 8.069860-5 1.100000+4 9.056777-5 1.600900+4 1.882760-4 925 3102 189 1.900000+4 3.528786-4 2.100000+4 6.255006-4 2.190200+4 8.655346-4 925 3102 190 2.300000+4 1.403543-3 2.335900+4 1.692361-3 2.457200+4 3.775089-3 925 3102 191 2.500000+4 5.522984-3 2.514600+4 6.284604-3 2.555600+4 1.049569-2 925 3102 192 2.588900+4 1.730403-2 2.620800+4 3.488576-2 2.640000+4 5.705982-2 925 3102 193 2.643600+4 6.469931-2 2.645000+4 6.804158-2 2.650000+4 8.204548-2 925 3102 194 2.655000+4 1.002110-1 2.660000+4 1.240730-1 2.664000+4 1.485390-1 925 3102 195 2.665000+4 1.555460-1 2.670000+4 1.967850-1 2.675000+4 2.495870-1 925 3102 196 2.675400+4 2.543320-1 2.680000+4 3.141800-1 2.683000+4 3.575910-1 925 3102 197 2.685000+4 3.877610-1 2.690000+4 4.635130-1 2.690600+4 4.722780-1 925 3102 198 2.695000+4 5.310090-1 2.695900+4 5.413650-1 2.700000+4 5.785680-1 925 3102 199 2.700400+4 5.811990-1 2.703500+4 5.947970-1 2.705000+4 5.968630-1 925 3102 200 2.708000+4 5.919950-1 2.710000+4 5.822830-1 2.710300+4 5.804010-1 925 3102 201 2.714800+4 5.404440-1 2.715000+4 5.382160-1 2.720000+4 4.736290-1 925 3102 202 2.721700+4 4.490060-1 2.725000+4 3.998040-1 2.730000+4 3.268820-1 925 3102 203 2.733000+4 2.865940-1 2.735000+4 2.617610-1 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4.878200+5 2.409659-4 925 3102 330 4.881700+5 2.420171-4 4.890000+5 2.439329-4 4.899200+5 2.450834-4 925 3102 331 4.905000+5 2.452745-4 4.909400+5 2.451433-4 4.920000+5 2.438557-4 925 3102 332 4.927500+5 2.421321-4 4.940000+5 2.378318-4 4.940600+5 2.375824-4 925 3102 333 4.948000+5 2.342010-4 4.960000+5 2.275918-4 4.961600+5 2.266138-4 925 3102 334 4.973300+5 2.188455-4 4.975700+5 2.171289-4 4.980500+5 2.135848-4 925 3102 335 4.988000+5 2.077793-4 5.000000+5 1.979364-4 5.010800+5 1.886578-4 925 3102 336 5.050000+5 1.540804-4 5.051400+5 1.528712-4 5.077100+5 1.316157-4 925 3102 337 5.095200+5 1.180511-4 5.100000+5 1.146832-4 5.112700+5 1.062652-4 925 3102 338 5.140100+5 9.058523-5 5.178500+5 7.403763-5 5.184000+5 7.213317-5 925 3102 339 5.200000+5 6.717458-5 5.239500+5 5.808101-5 5.287800+5 5.140921-5 925 3102 340 5.295100+5 5.070847-5 5.300000+5 5.027478-5 5.400000+5 4.618311-5 925 3102 341 5.419700+5 4.621231-5 5.500000+5 4.938361-5 5.560600+5 5.751017-5 925 3102 342 5.564700+5 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1.353053-4 1.113100+6 1.359816-4 1.116900+6 1.371350-4 925 3102 406 1.118000+6 1.373252-4 1.120000+6 1.375175-4 1.122200+6 1.375112-4 925 3102 407 1.130000+6 1.359744-4 1.131300+6 1.355389-4 1.132200+6 1.352152-4 925 3102 408 1.132700+6 1.350284-4 1.140000+6 1.319339-4 1.143100+6 1.305544-4 925 3102 409 1.150000+6 1.277991-4 1.150200+6 1.277307-4 1.152900+6 1.268948-4 925 3102 410 1.160000+6 1.256640-4 1.166300+6 1.260629-4 1.169200+6 1.268022-4 925 3102 411 1.170000+6 1.270726-4 1.179800+6 1.329126-4 1.180000+6 1.330832-4 925 3102 412 1.188500+6 1.423642-4 1.190000+6 1.444273-4 1.191200+6 1.461718-4 925 3102 413 1.200000+6 1.615465-4 1.203000+6 1.678208-4 1.208700+6 1.811270-4 925 3102 414 1.210000+6 1.844025-4 1.213100+6 1.925474-4 1.216600+6 2.022597-4 925 3102 415 1.220000+6 2.121442-4 1.224600+6 2.260568-4 1.224800+6 2.266722-4 925 3102 416 1.230000+6 2.428420-4 1.231400+6 2.472169-4 1.234500+6 2.568557-4 925 3102 417 1.237500+6 2.660394-4 1.238000+6 2.675487-4 1.239800+6 2.729195-4 925 3102 418 1.240000+6 2.735096-4 1.247000+6 2.930148-4 1.250000+6 3.005042-4 925 3102 419 1.251100+6 3.030900-4 1.256300+6 3.139796-4 1.260000+6 3.202281-4 925 3102 420 1.264800+6 3.262473-4 1.265800+6 3.271870-4 1.270000+6 3.299000-4 925 3102 421 1.271800+6 3.304417-4 1.273500+6 3.306066-4 1.274300+6 3.305680-4 925 3102 422 1.275000+6 3.304728-4 1.276200+6 3.301767-4 1.277500+6 3.296676-4 925 3102 423 1.277800+6 3.295223-4 1.279000+6 3.288385-4 1.279400+6 3.285737-4 925 3102 424 1.280000+6 3.281428-4 1.281400+6 3.269795-4 1.283300+6 3.250518-4 925 3102 425 1.284900+6 3.231236-4 1.287600+6 3.192580-4 1.290000+6 3.152028-4 925 3102 426 1.292000+6 3.114012-4 1.292500+6 3.103934-4 1.294900+6 3.052494-4 925 3102 427 1.298000+6 2.979016-4 1.300000+6 2.927767-4 1.301100+6 2.898402-4 925 3102 428 1.308800+6 2.673124-4 1.310000+6 2.635467-4 1.317700+6 2.383384-4 925 3102 429 1.318500+6 2.356488-4 1.320000+6 2.305863-4 1.321300+6 2.261850-4 925 3102 430 1.329100+6 1.998278-4 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7.987500-3 92533 16 499 7.852200-3 0.000000+0 1.159900-2 9.511800-3 9.102500-3 9.561900-3 92533 16 500 9.963400-3 0.000000+0 9.938600-3 8.743600-3 9.641700-3 1.087600-2 92533 16 501 1.148800-2 0.000000+0 9.461100-3 9.831400-3 1.153000-2 1.324900-2 92533 16 502 1.401400-2 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 503 92533 0 504 9.019000+3 1.883500+1 0 0 0 1 92533102 505 0.000000+0 0.000000+0 0 102 0 2 92533102 506 0.000000+0 0.000000+0 0 1 10 5 92533102 507 1.000000-5 9.000000-2 1.000000+4 4.000000-2 1.000000+5 9.000000-2 92533102 508 1.500000+6 2.500000-1 2.000000+7 0.000000+0 0.000000+0 0.000000+0 92533102 509 0.000000+0 0.000000+0 0 8 10 5 92533102 510 1.000000-5 2.41620-14 1.000000+4 1.86240-12 1.000000+5 1.63920-13 92533102 511 1.500000+6 6.19290-14 2.000000+7 0.000000+0 0.000000+0 0.000000+0 92533102 512 92533 0 513 925 0 0 514 0 0 0 515 1.102300+4 2.279200+1 1 0 0 01125 1451 1 0.000000+0 0.000000+0 0 0 0 61125 1451 2 1.000000+0 0.000000+0 0 0 10 61125 1451 3 0.000000+0 0.000000+0 0 0 81 101125 1451 4 11-NA- 23 ORNL EVAL-DEC77 D. C. LARSON 1125 1451 5 DIST-JAN90 900123 1125 1451 6 ----ENDF/B-VI MATERIAL 1125 1125 1451 7 -----INCIDENT NEUTRON DATA 1125 1451 8 ------ENDF-6 FORMAT 1125 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1125 1451 10 ACTIVATION I 1125 1451 11 ******************************************************************1125 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1125 1451 13 * * * * * * *1125 1451 14 ** 1125 1451 15 MF=2 1125 1451 16 RESONANCE PARAMETERS ARE USED FROM 600 EV TO 500 KEV. THE 1125 1451 17 THERMAL CAPTURE CROSS SECTION IS GIVEN AS 528 MB, IN AGREE- 1125 1451 18 MENT WITH THE EXPERIMENTAL RESULTS OF 526.9+-4.5 MB(RY71), AS 1125 1451 19 WELL AS EARLIER RESULTS SUMMARIZED IN REF RY71. USING RESON- 1125 1451 20 ANCE PARAMETERS E=2.81 KEV, GN=376 EV, AND GG=0.353 EV FOR THE 1125 1451 21 LARGE 2.81 KEV RESONANCE GIVES THE CORRECT THERMAL CAPTURE VA- 1125 1451 22 LUE USING A BREIT-WIGNER SHAPE, AND THIS FORM IS USED TO CALCUL- 1125 1451 23 ATE THE CAPTURE CRPOSS SECTION FROM 1.0E-5 TO 600 EV. THE CA- 1125 1451 24 PTURE WIDTH GG=0.353 EV IS CONSISTENT WITH A RECENT RESULT BY 1125 1451 25 WILSON, JACKSON, AND THOMAS (WI77) WHERE THEY FIND 0.248MEV 1125 1451 44 BASED ON 2 STEP HAUSER-FESHBACH CALCULATIONS 1125 1451 45 MT=107 TAKEN FROM ENDF4 1125 1451 46 MF=4 1125 1451 47 MT=2 TAKEN MAINLY FROM KI76,ENDF4 AND OPTICAL MODEL CALC 1125 1451 48 ALL OTHER ANGULAR DISTRIBUTIONS ASSUMED ISOTROPIC 1125 1451 49 MF=5 1125 1451 50 MT=16 TAKEN FROM ENDF4 1125 1451 51 MT=91 TEMPERATURES ADJUSTED TO FIT NEUTRON PRODUCTION 1125 1451 52 DATA OF HERMSDORF HE75 1125 1451 53 MF=8 DATA FROM C.REICH AND ENDT AND VANDER LEUN 1125 1451 54 MF=12 1125 1451 55 MT=102 DATA TAKEN FROM ENDF4 1125 1451 56 MF=13 1125 1451 57 MT=3 N,XGAMMA DATA FROM LA77 1125 1451 58 MF=14 1125 1451 59 ALL ANGULAR DISTRIBUTIONS ASSUMED ISOTROPIC 1125 1451 60 MF=15 1125 1451 61 MT=3 N,XG DISTRIBUTIONS FROM LA77 N,XGAMMA MEASUREMENT 1125 1451 62 MF=32 UNCERTAINTY FILES FOR THE RESONANCE PARAMETERS BELOW 32 1125 1451 63 KEV ARE ESTIMATED FROM THE LITERATURE FOR THE 2.81 KEV RESON- 1125 1451 64 ANCE, AND AN AREA ANALYSIS FOR THE 7.6 KEV RESONANCE. RESULTS 1125 1451 65 FROM THE MULTILEVEL ANALYSIS, CAPTURE AREAS, AND AREA ANALYSIS 1125 1451 66 FORM THE BASIS FOR THE REMAINDER OF THE RESONANCE PARAMETER 1125 1451 67 ERRORS. THE UNCERTAINTIES IN THE RESONANCE PARAMETERS ARE MOST 1125 1451 68 USEFUL IN SELF-SHIELDING WORK. 1125 1451 69 1125 1451 70 MF=33 UNCERTAINTY FILES FOR THE CAPTURE CROSS SECTION ARE EST- 1125 1451 71 IMATED FROM THE LITERATURE, AND THE SPREAD IN THE VARIOUS DATA 1125 1451 72 SETS. 1125 1451 73 *************** 1125 1451 74 REFERENCES 1125 1451 75 HE75 HERMSDORF,ET.AL REPORT INDC(GDR)-2/L 1125 1451 76 KI76 WE KINNEY AND FG PEREY PRIVATE COMMUNICATION 1125 1451 77 LA76 LARSON, HARVEY, AND HILL, ORNL-TM-5614 1976 1125 1451 78 LA77 DC LARSON AND GL MORGAN TO BE PUBLISHED 1125 1451 79 MA76 R.L. MACKLIN PRIVATE COMMUNICATION 1976 1125 1451 80 MU77 MUSGROVE, ALLEN, AND MACKLIN, PREPRINT JUNE 1977 1125 1451 81 PI72 PITTERLE & PAIK REPORT WARD 3045T4B-2 APPENDIX A 1972 1125 1451 82 RY71 T.B. RYVES 71 CANTERBURY CONFERENCE P. 139 1125 1451 83 SE74 J SELTZER AND FWK FIRK NSE 53(1974) 415 1125 1451 84 WI77 WILSON, JACKSON, AND THOMAS NSE 63, 55(1977) 1125 1451 85 1 451 95 01125 1451 86 2 151 30 01125 1451 87 3 16 7 01125 1451 88 3 102 16 01125 1451 89 3 103 37 01125 1451 90 3 107 37 01125 1451 91 33 16 8 01125 1451 92 33 102 5 01125 1451 93 33 103 8 01125 1451 94 33 107 8 01125 1451 95 1125 1 0 96 1125 0 0 97 1.102300+4 2.279200+1 0 0 1 01125 2151 98 1.102300+4 1.000000+0 0 0 1 01125 2151 99 6.000000+2 5.000000+5 1 2 0 01125 2151 100 1.500000+0 5.410000-1 0 0 3 01125 2151 101 2.279200+1 0.000000+0 0 0 24 41125 2151 102 2.810000+3 1.000000+0 3.763400+2 3.760000+2 3.530000-1 0.000000+01125 2151 103 2.429700+5 1.000000+0 3.295000+2 3.280000+2 1.500000+0 0.000000+01125 2151 104 2.983200+5 2.000000+0 2.039000+3 2.038000+3 1.020000+0 0.000000+01125 2151 105 5.385700+5 1.000000+0 6.278000+4 6.277000+4 1.014000+1 0.000000+01125 2151 106 2.279200+1 0.000000+0 1 0 72 121125 2151 107 7.617000+3 2.000000+0 6.058000-1 5.800000-3 6.000000-1 0.000000+01125 2151 108 3.539000+4 1.000000+0 3.500000+0 1.600000+0 1.900000+0 0.000000+01125 2151 109 5.322000+4 2.000000+0 1.112800+3 1.112000+3 7.850000-1 0.000000+01125 2151 110 1.174300+5 1.000000+0 3.103000+1 2.680000+1 4.230000+0 0.000000+01125 2151 111 1.431300+5 0.000000+0 2.360000+1 1.650000+1 7.100000+0 0.000000+01125 2151 112 2.011500+5 1.000000+0 4.927900+3 4.925000+3 2.940000+0 0.000000+01125 2151 113 2.143000+5 0.000000+0 1.428500+4 1.428000+4 4.640000+0 0.000000+01125 2151 114 2.390500+5 2.000000+0 5.350200+3 5.349000+3 1.200000+0 0.000000+01125 2151 115 2.994100+5 1.000000+0 1.325600+2 1.300000+2 2.560000+0 0.000000+01125 2151 116 3.923200+5 1.000000+0 2.277000+4 2.276000+4 9.870000+0 0.000000+01125 2151 117 5.980000+5 1.000000+0 2.580000+4 2.580000+4 0.000000+0 0.000000+01125 2151 118 7.270000+5 3.000000+0 4.500000+4 4.500000+4 0.000000+0 0.000000+01125 2151 119 2.279200+1 0.000000+0 2 0 42 71125 2151 120 1.900600+5 0.000000+0 2.750000+1 1.820000+1 9.300000+0 0.000000+01125 2151 121 2.367100+5 2.000000+0 6.679000+1 6.520000+1 1.590000+0 0.000000+01125 2151 122 3.052000+5 0.000000+0 7.800000+1 6.830000+1 9.700000+0 0.000000+01125 2151 123 4.309000+5 0.000000+0 4.005300+3 4.000000+3 5.290000+0 0.000000+01125 2151 124 4.488200+5 2.000000+0 7.029500+3 7.026000+3 3.520000+0 0.000000+01125 2151 125 6.970000+5 4.000000+0 6.000000+4 6.000000+4 0.000000+0 0.000000+01125 2151 126 7.800000+5 4.000000+0 4.400000+4 4.400000+4 0.000000+0 0.000000+01125 2151 127 1125 2 0 128 1125 0 0 129 1.102300+4 2.279200+1 0 0 0 01125 3 16 130 -1.241400+7-1.241400+7 0 0 1 121125 3 16 131 12 2 0 0 0 01125 3 16 132 1.295000+7 0.000000+0 1.300000+7 1.600000-3 1.324000+7 4.000000-31125 3 16 133 1.346000+7 8.000000-3 1.379000+7 1.420000-2 1.400000+7 2.000000-21125 3 16 134 1.440000+7 4.000000-2 1.471000+7 5.600000-2 1.500000+7 6.840000-21125 3 16 135 1.600000+7 1.090000-1 1.800000+7 1.560000-1 2.000000+7 1.940000-11125 3 16 136 1125 3 0 137 1.102300+4 2.279200+1 0 0 0 01125 3102 138 6.961500+6 6.961500+6 0 0 4 341125 3102 139 18 5 21 2 33 51125 3102 140 34 2 0 0 0 01125 3102 141 1.000000-5 2.656000+1 1.000000-3 2.656000+0 1.000000-2 8.398000-11125 3102 142 2.530000-2 5.280000-1 4.000000-2 4.199000-1 1.000000-1 2.656000-11125 3102 143 2.000000-1 1.878000-1 5.000000-1 1.188000-1 1.000000+0 8.400000-21125 3102 144 1.000000+1 2.675000-2 5.000000+1 1.230000-2 1.000000+2 9.030000-31125 3102 145 1.500000+2 7.650000-3 2.000000+2 6.880000-3 3.000000+2 6.070000-31125 3102 146 4.000000+2 5.700000-3 5.000000+2 5.550000-3 6.000000+2 5.530000-31125 3102 147 6.000000+2 0.000000+0 5.000000+5 0.000000+0 5.000000+5 2.780000-41125 3102 148 6.000000+5 3.500000-4 6.600000+5 3.500000-4 7.500000+5 3.200000-41125 3102 149 8.000000+5 2.700000-4 8.800000+5 2.400000-4 1.000000+6 2.300000-41125 3102 150 4.000000+6 1.600000-4 4.500000+6 1.600000-4 8.000000+6 1.700000-41125 3102 151 1.150000+7 1.800000-4 1.330000+7 2.000000-4 1.500000+7 2.300000-41125 3102 152 2.000000+7 2.454100-4 0.000000+0 0.000000+0 0.000000+0 0.000000+01125 3102 153 1125 3 0 154 1.102300+4 2.279200+1 0 0 0 01125 3103 155 -3.597000+6-3.597000+6 0 0 1 1021125 3103 156 102 2 0 0 0 01125 3103 157 3.754800+6 0.000000+0 4.050000+6 1.000000-4 4.500000+6 5.000000-41125 3103 158 4.750000+6 1.000000-3 5.000000+6 2.400000-3 5.130000+6 3.200000-31125 3103 159 5.250000+6 2.800000-3 5.270000+6 3.900000-3 5.300000+6 6.800000-31125 3103 160 5.350000+6 9.000000-3 5.500000+6 8.000000-3 5.630000+6 1.000000-21125 3103 161 5.750000+6 1.500000-2 5.800000+6 1.900000-2 5.850000+6 2.420000-21125 3103 162 5.880000+6 3.550000-2 5.905000+6 3.650000-2 5.930000+6 4.020000-21125 3103 163 5.955000+6 3.850000-2 6.025000+6 2.050000-2 6.050000+6 2.150000-21125 3103 164 6.125000+6 2.950000-2 6.150000+6 2.800000-2 6.175000+6 2.230000-21125 3103 165 6.200000+6 2.850000-2 6.250000+6 5.650000-2 6.300000+6 4.500000-21125 3103 166 6.330000+6 4.540000-2 6.360000+6 3.100000-2 6.380000+6 3.300000-21125 3103 167 6.430000+6 4.860000-2 6.500000+6 3.470000-2 6.530000+6 2.850000-21125 3103 168 6.580000+6 2.700000-2 6.620000+6 2.750000-2 6.650000+6 3.050000-21125 3103 169 6.725000+6 2.550000-2 6.780000+6 4.150000-2 6.820000+6 3.420000-21125 3103 170 6.930000+6 2.300000-2 6.960000+6 2.400000-2 7.025000+6 3.900000-21125 3103 171 7.050000+6 3.600000-2 7.075000+6 4.100000-2 7.100000+6 4.230000-21125 3103 172 7.175000+6 3.640000-2 7.200000+6 3.840000-2 7.230000+6 5.350000-21125 3103 173 7.300000+6 3.840000-2 7.350000+6 5.100000-2 7.440000+6 3.750000-21125 3103 174 7.470000+6 5.050000-2 7.500000+6 5.200000-2 7.550000+6 4.050000-21125 3103 175 7.600000+6 4.730000-2 7.625000+6 4.650000-2 7.700000+6 5.950000-21125 3103 176 7.800000+6 4.430000-2 7.850000+6 5.000000-2 7.900000+6 5.200000-21125 3103 177 7.960000+6 4.630000-2 8.050000+6 5.650000-2 8.125000+6 5.850000-21125 3103 178 8.200000+6 5.800000-2 8.230000+6 5.500000-2 8.270000+6 5.450000-21125 3103 179 8.325000+6 4.870000-2 8.420000+6 5.600000-2 8.500000+6 5.050000-21125 3103 180 8.600000+6 4.120000-2 8.650000+6 5.450000-2 8.700000+6 5.150000-21125 3103 181 8.790000+6 6.140000-2 8.820000+6 6.050000-2 8.860000+6 5.710000-21125 3103 182 8.910000+6 5.610000-2 8.980000+6 6.320000-2 9.070000+6 5.200000-21125 3103 183 9.125000+6 4.600000-2 9.150000+6 4.580000-2 9.200000+6 4.600000-21125 3103 184 9.350000+6 5.200000-2 9.500000+6 6.400000-2 9.580000+6 7.560000-21125 3103 185 9.625000+6 7.600000-2 9.650000+6 7.560000-2 9.750000+6 6.800000-21125 3103 186 9.850000+6 5.660000-2 9.900000+6 5.600000-2 9.950000+6 5.660000-21125 3103 187 1.005000+7 1.120000-1 1.010000+7 1.126000-1 1.015000+7 1.120000-11125 3103 188 1.025000+7 9.300000-2 1.040000+7 8.500000-2 1.075000+7 7.400000-21125 3103 189 1.150000+7 6.400000-2 1.300000+7 6.200000-2 1.400000+7 6.020000-21125 3103 190 1.600000+7 5.780000-2 1.800000+7 5.440000-2 2.000000+7 5.140000-21125 3103 191 1125 3 0 192 1.102300+4 2.279200+1 0 0 0 01125 3107 193 -3.866000+6-3.866000+6 0 0 1 1011125 3107 194 101 2 0 0 0 01125 3107 195 4.035600+6 0.000000+0 6.000000+6 1.000000-3 6.800000+6 3.500000-31125 3107 196 6.825000+6 4.500000-3 6.850000+6 4.500000-3 6.875000+6 5.300000-31125 3107 197 6.900000+6 6.000000-3 6.925000+6 7.200000-3 6.950000+6 8.000000-31125 3107 198 6.975000+6 7.000000-3 7.000000+6 7.500000-3 7.025000+6 9.000000-31125 3107 199 7.050000+6 9.800000-3 7.075000+6 1.050000-2 7.100000+6 1.020000-21125 3107 200 7.125000+6 9.400000-3 7.150000+6 9.400000-3 7.175000+6 1.050000-21125 3107 201 7.200000+6 1.250000-2 7.225000+6 1.380000-2 7.250000+6 1.390000-21125 3107 202 7.275000+6 1.260000-2 7.300000+6 1.230000-2 7.325000+6 1.380000-21125 3107 203 7.350000+6 1.510000-2 7.375000+6 1.730000-2 7.400000+6 1.730000-21125 3107 204 7.425000+6 1.810000-2 7.450000+6 1.850000-2 7.475000+6 1.880000-21125 3107 205 7.500000+6 1.860000-2 7.525000+6 1.890000-2 7.550000+6 1.910000-21125 3107 206 7.575000+6 2.230000-2 7.600000+6 2.260000-2 7.625000+6 2.270000-21125 3107 207 7.650000+6 2.400000-2 7.675000+6 2.360000-2 7.700000+6 2.390000-21125 3107 208 7.725000+6 2.440000-2 7.750000+6 2.670000-2 7.775000+6 2.840000-21125 3107 209 7.800000+6 2.450000-2 7.825000+6 2.620000-2 7.850000+6 3.040000-21125 3107 210 7.875000+6 3.200000-2 7.900000+6 3.150000-2 7.925000+6 3.070000-21125 3107 211 7.950000+6 3.220000-2 7.975000+6 3.410000-2 8.000000+6 3.500000-21125 3107 212 8.025000+6 3.800000-2 8.050000+6 3.900000-2 8.075000+6 4.150000-21125 3107 213 8.100000+6 4.350000-2 8.125000+6 4.420000-2 8.150000+6 4.530000-21125 3107 214 8.175000+6 4.220000-2 8.200000+6 4.190000-2 8.225000+6 3.830000-21125 3107 215 8.250000+6 3.710000-2 8.275000+6 3.640000-2 8.300000+6 3.800000-21125 3107 216 8.325000+6 4.330000-2 8.350000+6 4.530000-2 8.375000+6 4.670000-21125 3107 217 8.400000+6 4.650000-2 8.425000+6 4.850000-2 8.450000+6 4.890000-21125 3107 218 8.475000+6 5.140000-2 8.500000+6 5.420000-2 8.525000+6 5.700000-21125 3107 219 8.550000+6 5.210000-2 8.575000+6 5.240000-2 8.600000+6 5.300000-21125 3107 220 8.625000+6 5.210000-2 8.650000+6 5.450000-2 8.675000+6 5.460000-21125 3107 221 8.700000+6 5.720000-2 8.725000+6 5.800000-2 8.750000+6 5.800000-21125 3107 222 8.775000+6 6.250000-2 8.800000+6 6.170000-2 8.825000+6 6.390000-21125 3107 223 8.850000+6 6.340000-2 8.875000+6 6.460000-2 8.900000+6 6.310000-21125 3107 224 8.925000+6 6.380000-2 8.950000+6 6.470000-2 8.975000+6 6.250000-21125 3107 225 9.050000+6 6.800000-2 1.175000+7 1.580000-1 1.190000+7 1.620000-11125 3107 226 1.200000+7 1.630000-1 1.210000+7 1.635000-1 1.220000+7 1.630000-11125 3107 227 1.230000+7 1.620000-1 1.260000+7 1.590000-1 1.320000+7 1.520000-11125 3107 228 1.500000+7 1.250000-1 2.000000+7 1.333700-1 0.000000+0 0.000000+01125 3107 229 1125 3 0 230 1125 0 0 231 1.102300+4 2.279200+1 0 0 0 1112533 16 232 0.000000+0 0.000000+0 0 16 0 2112533 16 233 0.000000+0 0.000000+0 0 1 14 7112533 16 234 1.000000-5 0.000000+0 1.295000+7 1.600000-1 1.350000+7 4.000000-2112533 16 235 1.450000+7 2.250000-2 1.600000+7 1.000000-2 1.800000+7 2.250000-2112533 16 236 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0112533 16 237 0.000000+0 0.000000+0 0 1 6 3112533 16 238 1.000000-5 0.000000+0 1.295000+7 6.400000-3 2.000000+7 0.000000+0112533 16 239 112533 0 240 1.102300+4 2.279200+1 0 0 0 1112533102 241 0.000000+0 0.000000+0 0 102 0 1112533102 242 0.000000+0 0.000000+0 0 1 12 6112533102 243 1.000000-5 4.000000-4 5.000000+1 2.250000-3 6.000000+2 1.000000-2112533102 244 5.000000+5 4.000000-2 5.000000+6 6.250000-2 2.000000+7 0.000000+0112533102 245 112533 0 246 1.102300+4 2.279200+1 0 0 0 1112533103 247 0.000000+0 0.000000+0 0 103 0 2112533103 248 0.000000+0 0.000000+0 0 1 16 8112533103 249 1.000000-5 0.000000+0 3.754800+6 9.000000-2 4.200000+6 4.000000-2112533103 250 5.800000+6 2.250000-2 9.000000+6 6.250000-2 1.040000+7 4.000000-2112533103 251 1.400000+7 6.250000-2 2.000000+7 0.000000+0 0.000000+0 0.000000+0112533103 252 0.000000+0 0.000000+0 0 1 6 3112533103 253 1.000000-5 0.000000+0 3.754800+6 1.000000-2 2.000000+7 0.000000+0112533103 254 112533 0 255 1.102300+4 2.279200+1 0 0 0 1112533107 256 0.000000+0 0.000000+0 0 107 0 2112533107 257 0.000000+0 0.000000+0 0 1 16 8112533107 258 1.000000-5 0.000000+0 4.035600+6 2.500000-1 6.300000+6 6.250000-2112533107 259 7.000000+6 2.250000-2 9.000000+6 4.000000-2 1.050000+7 1.600000-1112533107 260 1.400000+7 1.225000-1 2.000000+7 0.000000+0 0.000000+0 0.000000+0112533107 261 0.000000+0 0.000000+0 0 1 6 3112533107 262 1.000000-5 0.000000+0 4.035600+6 1.000000-2 2.000000+7 0.000000+0112533107 263 112533 0 264 1125 0 0 265 0 0 0 266 1.202400+4 2.398500+1 -1 0 0 01225 1451 1 0.000000+0 0.000000+0 0 0 0 61225 1451 2 1.000000+0 0.000000+0 0 0 10 61225 1451 3 0.000000+0 0.000000+0 0 0 31 21225 1451 4 12-MG- 24 HEDL,ORNL EVAL-NOV79 MANN,LARSON 1225 1451 5 DIST-JAN90 900123 1225 1451 6 ----ENDF/B-VI MATERIAL 1225 1225 1451 7 -----INCIDENT NEUTRON DATA 1225 1451 8 ------ENDF-6 FORMAT 1225 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1225 1451 10 ACTIVATION I 1225 1451 11 ******************************************************************1225 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1225 1451 13 * * * * * * *1225 1451 14 ******* 24MG(N,P) CROSS SECTION FOR ACTIVATION FILE ****** 1225 1451 15 ***** EVALUATION TAKEN FROM TAGESEN, VONACH AND STROHMAIER BY 1225 1451 16 ***** D.C. LARSON ORNL ******** 1225 1451 17 THE EVALUATION FOR THIS CROSS SECTION WAS TAKEN FROM THE RECENT 1225 1451 18 EVALUATION OF THIS CROSS SECTION FOR AN INTERNATIONAL DOSIMETRY 1225 1451 19 FILE. THIS WORK IS DOCUMENTED IN DETAIL IN REF TA79. THE RESULTS1225 1451 20 OF 17 MEASUREMENTS WERE RE-ANALYZED USING THE LATEST BRANCHING 1225 1451 21 RATIOS, ETC., AND RENORMALIZING WHERE NECESSARY TO UPDATED VALUES 1225 1451 22 OF "STANDARD" CROSS SECTIONS. THIS WAS A VERY CAREFUL EVALUATION 1225 1451 23 WELL DOCUMENTED, AND THE USER IS REFERRED TO THE DOCUMENT TA79 1225 1451 24 FOR ALL THE DETAILS. COMPLETE UNCERTAINTY FILES ARE ALSO GIVEN. 1225 1451 25 ***** DECAY OF 24NA (FILES 8/103 AND 9/103) ******** 1225 1451 26 THESE FILES WERE PROVIDED BY C. REICH OF INEL FOR THE ENDF/B-V 1225 1451 27 EVALUATION EFFORT OF CSWEG. 1225 1451 28 THE 24MG(N,P) REACTION LEADS TO 24NA, WHICH HAS A HALFLIFE OF 1225 1451 29 15.02 HOURS. IT DECAYS 99.94% BACK TO THE 4.12 MEV LEVEL IN 24MG 1225 1451 30 WHICH THEN EMITS 2.754 MEV AND 1.369 MEV GAMMA RAYS IN THE DECAY 1225 1451 31 TO THE GROUND STATE OF 24MG. 1225 1451 32 ****** REFERENCES ******* 1225 1451 33 TA79 S. TAGESEN, H. VONACH AND B. STROHMAIER, PHYSICS DATA 1225 1451 34 REPORT NR 13-1, KARLSRUHE (1979) 1225 1451 35 1 451 37 01225 1451 36 3 103 17 01225 1451 37 1225 1 0 38 1225 0 0 39 1.202400+4 2.398500+1 0 0 0 01225 3103 40 -4.731000+6-4.731000+6 0 0 1 411225 3103 41 41 1 0 0 0 01225 3103 42 4.930000+6 2.100000-5 5.200000+6 4.700000-5 5.600000+6 2.100000-41225 3103 43 5.800000+6 1.907000-3 6.100000+6 4.359000-3 6.300000+6 8.705000-31225 3103 44 6.500000+6 3.698000-2 6.700000+6 4.364000-2 6.900000+6 3.575000-21225 3103 45 7.100000+6 5.225000-2 7.310000+6 4.658000-2 7.510000+6 8.020000-21225 3103 46 7.700000+6 9.339000-2 7.900000+6 1.063000-1 8.110000+6 1.199000-11225 3103 47 8.500000+6 1.193000-1 9.500000+6 1.234000-1 1.000000+7 1.482000-11225 3103 48 1.050000+7 1.580000-1 1.150000+7 1.820000-1 1.220000+7 1.928000-11225 3103 49 1.240000+7 2.096000-1 1.260000+7 2.002000-1 1.280000+7 2.008000-11225 3103 50 1.300000+7 1.977000-1 1.320000+7 2.147000-1 1.340000+7 2.177000-11225 3103 51 1.360000+7 2.014000-1 1.380000+7 1.891000-1 1.400000+7 1.965000-11225 3103 52 1.420000+7 1.968000-1 1.440000+7 1.907000-1 1.460000+7 1.823000-11225 3103 53 1.480000+7 1.718000-1 1.500000+7 1.782000-1 1.550000+7 1.570000-11225 3103 54 1.600000+7 1.398000-1 1.700000+7 1.223000-1 1.800000+7 1.135000-11225 3103 55 1.900000+7 9.713000-2 2.000000+7 8.091000-2 0.000000+0 0.000000+01225 3103 56 1225 3 0 57 1225 0 0 58 0 0 0 59 1.302700+4 2.675000+1 0 0 0 01325 1451 1 0.000000+0 0.000000+0 0 0 0 61325 1451 2 1.000000+0 0.000000+0 0 0 10 61325 1451 3 0.000000+0 0.000000+0 0 0 300 101325 1451 4 13-AL- 27 LANL EVAL-DEC73 P.G. YOUNG, D.G. FOSTER, JR. 1325 1451 5 LA-4726 (1973). DIST-JAN90 900123 1325 1451 6 ----ENDF/B-VI MATERIAL 1325 1325 1451 7 -----INCIDENT NEUTRON DATA 1325 1451 8 ------ENDF-6 FORMAT 1325 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1325 1451 10 ACTIVATION I 1325 1451 11 ******************************************************************1325 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1325 1451 13 * * * * * * *1325 1451 14 1325 1451 15 REVISED-AUG77. VERSION IV DATA, WITH ADDITION OF FILE 33. 1325 1451 16 1325 1451 17 ******************* REVISED 11/73 ****************** 1325 1451 18 THE NEW EXPERIMENTAL DATA ARE DESCRIBED BELOW. BRIEFLY, 1325 1451 19 THE FOLLOWING IMPROVEMENTS WERE MADE. 1325 1451 20 1. THE RADIATIVE CAPTURE GAMMA-RAY SPECTRUM FOR THERMAL 1325 1451 21 NEUTRONS WAS REVISED TO BETTER AGREE WITH RECENT DATA. 1325 1451 22 2. IMPROVED (N,P) AND (N,ALPHA) CROSS SECTIONS WERE INCOR- 1325 1451 23 PORATED. THESE DATA ARE THE SAME AS WERE PROVIDED 1325 1451 24 EARLIER TO THE STANDARDS SUBCOMMITTEE OF CSEWG. 1325 1451 25 3. FILE 13 AND FILE 15 (N,NGAMMA) AND (N,NPGAMMA) DATA WERE 1325 1451 26 REVISED TO INCLUDE THE MEASUREMENTS OF DI73. 1325 1451 27 4. THE (N,NPRIME) CROSS SECTIONS TO HIGH-LYING PSEUDO LEVELS 1325 1451 28 WERE REVISED FOR NEUTRON ENERGIES NEAR 14 MEV TO GIVE 1325 1451 29 BETTER AGREEMENT WITH MEASUREMENTS OF KA72. IN ADDITION, 1325 1451 30 (N,NPRIME) DATA TO LOWER LEVELS WERE REVISED TO BE 1325 1451 31 CONSISTENT WITH CHANGES MADE UNDER ITEM 3. 1325 1451 32 5. ANISOTROPIC (N,NPRIME) ANGULAR DISTRIBUTIONS BASED ON 1325 1451 33 EXPERIMENTAL DATA WERE INCORPORATED. 1325 1451 34 6. TOTAL NEUTRON CROSS SECTION WAS EXTENSIVELY REVISED, ES- 1325 1451 35 PECIALLY BELOW 1 MEV, TO INCLUDE THE MEASUREMENT OF PE72. 1325 1451 36 **************************************************************** 1325 1451 37 1325 1451 38 MF=2 --- RESONANCE PARAMETERS --- 1325 1451 39 MT=151 EFFECTIVE SCATTERING RADIUS = 0.32752E-12 CM 1325 1451 40 MF=3 --- NEUTRON SMOOTH CROSS SECTIONS --- 1325 1451 41 THE 2200 M/S CROSS SECTIONS ARE AS FOLLOWS, 1325 1451 42 MT=1 SIGMA = 1.580 B MT=2 SIGMA = 1.348 B 1325 1451 43 MT=3 SIGMA = 0.232 B MT=102 SIGMA = 0.232 B 1325 1451 44 MT=1 TOTAL CROSS SECTION 1325 1451 45 BELOW 4.6 KEV, 1/V FIT TO ME52 AND HI59 (NORMALIZED TO ME52),1325 1451 46 USING THERMAL CAPTURE XS OF 232 MB (GO71) AND RESULTING 1325 1451 47 (N,N) XS OF 1.580 B. 1325 1451 48 4.6 - 189 KEV, FROM GA65 NORMALIZED TO ME52 VIA HI59 AT LOW 1325 1451 49 ENERGIES AND TO PE72 AT HIGH ENERGIES. 1325 1451 50 209 - 475 KEV, FROM PE72 WITH ENERGY SCALE CORRECTED TO MATCH1325 1451 51 CI68 AT HIGHER ENERGIES. 1325 1451 52 .475 - 11.5 MEV, COMPOSITE OF PE72 AND SC69, NORMALIZED TO 1325 1451 53 THEIR WEIGHTED AVERAGE, WITH INSERTS OF NORMALIZED CI68 1325 1451 54 WHERE NEEDED TO PRESERVE RESOLUTION. 1325 1451 55 11.5 - 20 MEV, COMPOSITE OF PE72,FO71,AL66,AND PE60 NORM- 1325 1451 56 ALIZED TO THEIR WEIGHTED AVERAGE. SLOPE AT 20 MEV INCLUDES 1325 1451 57 GUIDANCE FROM TA52. 1325 1451 58 SMOOTHING BETWEEN 4.6 KEV AND 2 MEV BY APPROXIMATE BREIT- 1325 1451 59 WIGNER FITS WHERE POSSIBLE, CONNECTED BY POLYNOMIAL FITS. 1325 1451 60 2 - 12 MEV SMOOTHED BY RUNNING CUBIC POLYNOMIAL FITS. 1325 1451 61 ABOVE 12 MEV FITTED SECONDARY POLYNOMIAL TO MIDDLES OF 1325 1451 62 RUNNING POLYNOMIAL FITS. 1325 1451 63 MT=2 ELASTIC SCATTERING CROSS SECTION 1325 1451 64 BELOW 5 MEV, SUBTRACTED NONELASTIC FROM TOTAL. 1325 1451 65 5 TO 16 MEV, MAINLY BASED ON ELASTIC DATA OF HO69, ST59, KI701325 1451 66 ,ST65,CO58,CO59,BE58,MI68,BE56, AND KA72 TOGETHER WITH THE 1325 1451 67 EVAL. TOTAL AND THE NONELASTIC MEASUREMENTS LISTED BELOW. 1325 1451 68 16 TO 20 MEV, SMOOTH EXTRAP. TO 1/2 THE TOTAL AT 20 MEV. 1325 1451 69 MT=3 NONELASTIC CROSS SECTION (IMPLICIT - NOT IN FILE) 1325 1451 70 BELOW 9 MEV, BASED ON THE NONELASTIC MEASUREMENTS OF BA58, 1325 1451 71 BE56, TA55, DE65, ON THE SUM OF MT=4,102,103,107, AND ON 1325 1451 72 THE DIFFERENCE BETWEEN THE EVALUATED TOTAL AND THE ELASTIC 1325 1451 73 MEASUREMENTS OF HO69, KI70, BE56, MI68. 1325 1451 74 9 TO 16 MEV, BASED ON NONELASTIC MEASUREMENTS OF BA58, TA55, 1325 1451 75 GR55, PH52, MA57, DE61, FL56, CH67, AND ON THE DIFFERENCE 1325 1451 76 BETWEEN MT=1 AND MT=2 DATA OF ST59, ST65, CO58, CO59, BE58 1325 1451 77 16 TO 20 MEV, DIFFERENCE BETWEEN MT=1 AND MT=2 1325 1451 78 MT=4 INELASTIC CROSS SECTION 1325 1451 79 THRES. TO 5 MEV, SUM OF MT=51-63. 1325 1451 80 5 TO 9 MEV, BASED ON (N,NPRIME) DATA OF TH63, TO67, THE EVAL.1325 1451 81 (N,NPRIME) DATA OF DI71 WHICH INCLUDES CONSIDERATION OF 1325 1451 82 SEVERAL OTHER MEASUREMENTS, AND THE (N,NG) DATA OF DI71, 1325 1451 83 OR71, AND DI73. 1325 1451 84 9 TO 20 MEV, THE DIFFERENCE BETWEEN MT=1 AND THE SUM OF 1325 1451 85 MT=2,16,102,103,104,105,107. 1325 1451 86 MT=16 (N,2N) CROSS SECTION 1325 1451 87 THRES. TO 20 MEV, ESTIMATED USING A NUCLEAR TEMP. CALCULATION1325 1451 88 ASSUMING THAT HIGHLY EXCITED STATES IN AL-27 DECAY 50 PER 1325 1451 89 CENT BY NEUTRON EMISSION. 1325 1451 90 MT=51-63 INELASTIC CROSS SECTION TO DISCRETE STATES 1325 1451 91 MT=51 Q=-0.843 MEV MT=56 Q=-3.001 MEV MT=60 Q=-4.409 MEV 1325 1451 92 52 -1.013 57 -3.678 61 -4.508 1325 1451 93 53 -2.210 58 -3.956 62 -4.580 1325 1451 94 54 -2.732 59 -4.055 63 -4.811 1325 1451 95 55 -2.980 1325 1451 96 THRES. TO 5 MEV, BASED ON THE (N,NPRIME) DATA OF TO62, WI63,1325 1451 97 TS61, AND THE (N,NG) DATA OF CH68, MA65, DI71, OR71, DI73. 1325 1451 98 5 TO 9 MEV, BASED ON AN EVALUATION OF SEVERAL MEASUREMENTS 1325 1451 99 GIVEN IN DI71 (TABLE B1). 1325 1451 100 9 TO 20 MEV, SMOOTH EXTRAPOLATION PASSING THROUGH 14 MEV DATA1325 1451 101 OF ST65, BO65A. 1325 1451 102 MT=64-90 INELASTIC CROSS SECTION TO GROUPS OF DISCRETE STATES 1325 1451 103 IN BANDS CENTERED ABOUT THE Q-VALUES GIVEN BELOW, 1325 1451 104 MT=64 Q=- 5.25 MEV MT=73 Q=- 9.75 MEV MT=82 Q=-14.25 MEV 1325 1451 105 65 - 5.75 74 -10.25 83 -14.75 1325 1451 106 66 - 6.25 75 -10.75 84 -15.25 1325 1451 107 67 - 6.75 76 -11.25 85 -15.75 1325 1451 108 68 - 7.25 77 -11.75 86 -16.25 1325 1451 109 69 - 7.75 78 -12.25 87 -16.75 1325 1451 110 70 - 8.25 79 -12.75 88 -17.375 1325 1451 111 71 - 8.75 80 -13.25 89 -18.125 1325 1451 112 72 - 9.25 81 -13.75 90 -18.875 1325 1451 113 THRES. TO 20 MEV, INTEGRATED CROSS SECTION OVER BANDS 1325 1451 114 OBTAINED BY SUBTRACTING MT=51-63 FROM MT=4. CROSS SECTION 1325 1451 115 DIVIDED AMONG BANDS ACCORDING TO A NUCLEAR TEMPERATURE 1325 1451 116 CALCULATION USING TEMP. BASED ON (N,NPRIME) DATA OF TH63, 1325 1451 117 GR53. THE CROSS SECTION TO THE BANDS WITH MT=64-71 WAS 1325 1451 118 ADJUSTED EXTENSIVELY TO PRODUCE AGREEMENT WITH THE 14-MEV 1325 1451 119 MEASUREMENTS OF SECONDARY NEUTRON SPECTRA BY KA72. 1325 1451 120 ****PLEASE NOTE THAT MUCH OF THE CROSS SECTION TO BANDS ABOVE EX=1325 1451 121 ****9 MEV SUBSEQUENTLY RESULTS IN CHARGED PARTICLE EMISSION. 1325 1451 122 ****SINCE THESE DATA ARE NOT INCLUDED EXPLICITLY AS (N,NX) REAC- 1325 1451 123 ****TIONS, IT IS IMPORTANT THAT USERS INVOLVED IN CERTAIN CALCU- 1325 1451 124 ****LATIONS (E.G., LOCAL HEATING) BE AWARE OF THIS INFORMATION. 1325 1451 125 MT=102 (N,GAMMA) CROSS SECTION 1325 1451 126 BELOW 1 KEV, 1/V FROM THERMAL VALUE OF 232 MB (GO71). 1325 1451 127 1 TO 140 KEV, FROM BL68. 6-KEV RESONANCE HAS WIDTH DEDUCED 1325 1451 128 FROM TOTAL X-SECT. SMALL RESONANCES NEARBY ALSO FROM TOTAL.1325 1451 129 ABOVE 140 KEV, MAINLY FROM HE50, HE53, AND CA62. 1325 1451 130 FROM TOTAL X-SECT. SMALL RESONANCES NEARBY ALSO FROM TOTAL.1325 1451 131 ABOVE 140 KEV, MAINLY FROM HE50, HE53, AND CA62. 1325 1451 132 MT=103 (N,P) CROSS SECTION (SEE YO72 FOR MORE DETAILS) 1325 1451 133 THRES. TO 4 MEV, BASED ON THE MEASUREMENTS OF HE54 AND GR67, 1325 1451 134 EXTRAPOLATED FROM 3 MEV TO THRESHOLD WITH AN L=0 PENETRA- 1325 1451 135 BILITY FUNCTION FOR THE OUTGOING P+MG27 CHANNEL. 1325 1451 136 4 TO 20 MEV, SMOOTH CURVE THROUGH THE MEASUREMENTS OF HE54, 1325 1451 137 GR67, CA62, BA66, MA60. 1325 1451 138 MT=104 (N,D) CROSS SECTION 1325 1451 139 THRES. TO 20 MEV, SMOOTH CURVE THROUGH SINGLE DATUM OF GL61. 1325 1451 140 MT=105 (N,T) CROSS SECTION 1325 1451 141 THRES. TO 20 MEV, SMOOTH CURVE WITH SAME SHAPE AS MT=104, 1325 1451 142 REACHING MAXIMUM OF 15 MB AT 20 MEV. 1325 1451 143 MT=107 (N,ALPHA) CROSS SECTION (SEE YO72 FOR MORE DETAILS). 1325 1451 144 THRES. TO 20 MEV, BASED ON A SMOOTH CURVE THROUGH EXPERI- 1325 1451 145 MENTAL DATA, MAINLY THOSE OF BU63, PA65, AND LI66, WITH 1325 1451 146 RESULTS FROM GR67, SC61, GR58, BA61, MA60, GA62, IM64, 1325 1451 147 KE59 AND SEVERAL 14-MEV POINTS ALSO BEING CONSIDERED. 1325 1451 148 THE CURVE WAS EXTRAPOLATED FROM 6 MEV TO THRESHOLD WITH AN 1325 1451 149 L=0 PENETRABILITY FUNCTION FOR THE OUTGOING ALPHA+NA24 1325 1451 150 CHANNEL. 1325 1451 151 MT=203 TOTAL H PRODUCTION IS THE SUM OF MTS 75 + 78 +80 + 81 1325 1451 152 + 83 + 84 + 85 + 87 + 88 + 90 + 103. 1325 1451 153 MT=207 TOTAL HE-4 PRODUCTION IS THE SUM OF MTS 82 + 86 + 89 1325 1451 154 + 107. 1325 1451 155 MF=4 --- NEUTRON ANGULAR DISTRIBUTIONS --- 1325 1451 156 MT=2 ELASTIC ANGULAR DISTRIBUTIONS 1325 1451 157 FROM SMOOTH CURVES THROUGH PLOTS OF COEFFICIENTS FROM FITS 1325 1451 158 TO ALL AVAILABLE DATA ABOVE .25 MEV, WITHOUT EVALUATION 1325 1451 159 OF MEASUREMENTS. MAINLY FROM LA57, CH66, TO62, TS61, KI70, 1325 1451 160 BE58, WITH OPTICAL-MODEL BRIDGE TO ST62. SOME OF DATA 1325 1451 161 AUGMENTED BEFORE FITTING BY ZERO-DEGREE POINT SLIGHTLY 1325 1451 162 ABOVE WICK LIMIT, AND COEFFICIENTS ADJUSTED EMPIRICALLY 1325 1451 163 AFTERWARDS TO OBEY WICK LIMIT, BUT ONLY BARELY AT HIGHER 1325 1451 164 ENERGIES. 1325 1451 165 MT=16 (N,2N) ANGULAR DISTRIBUTIONS 1325 1451 166 ASSUMED ISOTROPIC IN CM, USING 2-BODY KINEMATICS TO ESTIMATE 1325 1451 167 TRANSFORMATION TO LAB SYSTEM. 1325 1451 168 MT=51-63 INELASTIC NEUTRON ANGULAR DISTRIBUTIONS 1325 1451 169 ANISOTROPIC DISTRIBUTIONS BASED ON MEASUREMENTS BY TS61,TO62,1325 1451 170 WI63, MI68, TA70, GL72, ST65, BO65A, KA72 WERE IN- 1325 1451 171 CORPORATED OVER VARYING ENERGY RANGES FROM THRES.TO 20 MEV.1325 1451 172 IN SEVERAL REGIONS WHERE DATA WERE LACKING, ISOTROPY WAS 1325 1451 173 ASSUMED. 1325 1451 174 MT=64-90 INELASTIC NEUTRON ANGULAR DISTRIBUTIONS 1325 1451 175 ASSUMED ISOTROPIC IN THE CENTER-OF-MASS SYSTEM. 1325 1451 176 MF=5 --- NEUTRON ENERGY DISTRIBUTIONS --- 1325 1451 177 MT= 16 (N,2N) ENERGY DISTRIBUTIONS, BASED ON STATISTICAL THEORY1325 1451 178 MF=12 --- GAMMA RAY MULTIPLICITIES --- 1325 1451 179 MT=102 (N,G) CAPTURE MULTIPLICITIES 1325 1451 180 THE AL-28 DECAY SCHEME FOR EXCITATION BY RADIATIVE CAPTURE 1325 1451 181 WITH THERMAL NEUTRONS FROM HA69 WAS ADOPTED AFTER SOME 1325 1451 182 MODIFICATION TO ENHANCE AGREEMENT WITH EXPERIMENT. THE 1325 1451 183 RESULTS HAVE BEEN COMPARED WITH THE LESS DETAILED DATA OF 1325 1451 184 BA67, JU71, AND MA69, AND ARE REASONABLY CONSISTENT. SOME 1325 1451 185 OF THE LINES IN RA70 BELOW 1 MEV APPEAR TO BE SPURIOUS 1325 1451 186 AND HAVE BEEN DROPPED. SPECTRUM FOR THERMAL NEUTRONS IS 1325 1451 187 ASSUMED TO APPLY AT ALL ENERGIES. 1325 1451 188 MF=13 --- GAMMA RAY SMOOTH CROSS SECTIONS --- 1325 1451 189 MT=4 (N,NG) CROSS SECTIONS 1325 1451 190 THRES. TO 5 MEV, BASED ON THE (N,NPRIME) DATA OF TO62, WI63, 1325 1451 191 TS61, AND THE (N,NG) DATA OF CH68,MA65,DI71,OR71, AND DI73.1325 1451 192 5 TO 20 MEV, MAINLY FROM (N,NG) DATA OF DI73, OR71, DI71, 1325 1451 193 DR73, PE64, BE66, CL69, EN67, BO65, MA68, CA60, PR60, 1325 1451 194 SUPPLEMENTED BY STATISTICAL THEORY CALCULATIONS. 1325 1451 195 MT=28 (N,NPG) CROSS SECTIONS 1325 1451 196 THRES. TO 20 MEV, BASED ON THE MEASUREMENTS OF DI73, OR71, 1325 1451 197 EN67, PR60, CL69, BE66, BO65, AND ON STATISTICAL THEORY 1325 1451 198 MT=103 (N,PG) CROSS SECTIONS 1325 1451 199 THRES. TO 9 MEV, USED DATA OF DI71. 1325 1451 200 9 TO 20 MEV, SMOOTH EXTRAPOLATION. 1325 1451 201 MF=14 --- GAMMA RAY ANGULAR DISTRIBUTIONS --- 1325 1451 202 MT=4 (N,NG) ANGULAR DISTRIBUTIONS, ASSUMED ISOTROPIC. 1325 1451 203 MT=28 (N,NPG) ANGULAR DISTRIBUTIONS ASSUMED ISOTROPIC. 1325 1451 204 MT=103 (N,PG) ANGULAR DISTRIBUTIONS, ASSUMED ISOTROPIC 1325 1451 205 MF=15 --- GAMMA RAY ENERGY DISTRIBUTIONS --- 1325 1451 206 MT=4 (N,NG) ENERGY DISTRIBUTIONS 1325 1451 207 STATISTICAL THEORY CAL. ADJUSTED TO FIT MEAS. OF DI73 1325 1451 208 MT=28 (N,NPG) ENERGY DISTRIBUTIONS 1325 1451 209 STATISTICAL THEORY CAL. ADJUSTED TO FIT MEAS. OF DI73 1325 1451 210 MF=33 --- CORRELATED ERRORS --- 1325 1451 211 BASED ON REVISED VERSION OF TABLE 6 IN LA-4726. ERRORS ARE 1325 1451 212 GIVEN ONLY FOR MT = 1, 2, 4, 16, 102, 103, AND 107. 1325 1451 213 MT=2 IS TAKEN FROM EXPERIMENT BETWEEN 9 AND 17 MEV, AND 1325 1451 214 DERIVED EVERYWHERE ELSE. MT=4 IS DERIVED ABOVE 9 MEV. 1325 1451 215 THE DERIVATION FORMULAS ARE GIVEN BY NC-TYPE SUB-SUBSECTIONS 1325 1451 216 WITH LTY=0 IN MT=2 AND MT=4. 1325 1451 217 1325 1451 218 --------------------------- REFERENCES --------------------------1325 1451 219 BA58 W.P.BALL ET AL.(LRL), PHYS.REV.110,1392 (1958). 1325 1451 220 BA61 B.P.BAYHURST+R.J.PRESTWOOD (LAS),PHYS.REV.121,1438 (1961). 1325 1451 221 BA66 R.BASS, EANDC(E)-66U,P64, AND PRIVATE COMMUNICATION (1966).1325 1451 222 BA67 G.A.BARTHOLOMEW ET AL., NUCL. DATA A3, 367 (1967) 1325 1451 223 BE55 J.R.BEYSTER ET AL.(LAS), PHYS.REV.98,1216 (1955). 1325 1451 224 BE56 J.R.BEYSTER ET AL.(LAS), PHYS.REV.104,1319 (1956). 1325 1451 225 BE58 S.BERKO ET AL., NUCL. PHYS. 6, 210 (1958) 1325 1451 226 BE66 V.M.BEZOTOSNYI ET AL.(RUS),SOV.J.NUCL.PHYS.3,632 (1966). 1325 1451 227 BL68 R.C.BLOCK, PRIVATE COMMUNICATION TO R.J.HOWERTON (1968) 1325 1451 228 BO59 N.A.BOSTROM ET AL.(TNC), WADC-TN-59-107 (1959). 1325 1451 229 BO65 V.N.BOCHKAREV+V.V.NEFEDOV (LEB),SOV.J.NUCL.PHYS.1,574(1965)1325 1451 230 BO65A G.C.BONAZZOLA ET AL.(TUR), PHYS.REV.140,835 (1965). 1325 1451 231 BU63 J.P.BUTLER AND D.C.SANTRY, CAN.J.PHYS.41, 372 (1963.) 1325 1451 232 CA60 R.L.CALDWELL ET AL.(SOC),NUCL.SCI.ENG.8,173 (1960). 1325 1451 233 CA62 G.CALVI ET AL., NUCL. PHYS. 39, 621 (1962) 1325 1451 234 CA67 A.D.CARLSON AND H.H.BARSCHALL, PHYS. REV. 158, 1142 (1967) 1325 1451 235 CH66 J.P.CHIEN AND A.B.SMITH, NUCL. SCI. ENG. 26, 500 (1966) 1325 1451 236 CH67 A.CHATTERJEE+A.M.GHOSE(BOS), PHYS.REV.161,1181 (1967). 1325 1451 237 CH68 K.C.CHUNG ET AL.(KTY),NUCL.PHYS.68,476 (1968). 1325 1451 238 CI68 S.CIERJACKS ET AL., KFK-1000 (1968) 1325 1451 239 CL69 G.CLAYEUX+G.GRENIER (FR),CEA-R-3807,(1969). 1325 1451 240 CO58 J.H.COON ET AL.(LAS), PHYS.REV. 111,250 (1958). 1325 1451 241 CO59 J.H.COON (LAS),PRIVATE COMMUNICATION TO R.J.HOWERTON (1959)1325 1451 242 DE61 YU.G.DEGTYAREV+V.G.NADTOCHII (RUS), SOV.J.AT.ENERGY 11,10431325 1451 243 (1961). 1325 1451 244 DE65 YU.G.DEGTYAREV (RUS), J.NUCL.ENERGY 20,818 (1965). 1325 1451 245 DI71 J.K.DICKENS (ORL), ORNL-TM-3284, 1971. 1325 1451 246 DI73 J.K.DICKENS ET AL., ORNL-TM-4232 (1973). 1325 1451 247 DR70 D.M.DRAKE ET AL. (LAS), NUCL.SCI.ENG.40,294 (1970). 1325 1451 248 EN67 F.C.ENGESSER+W.E.THOMPSON (NRD),J.NUCL.ENERGY 21,487 (1967)1325 1451 249 FE67 J.M.FERGUSON+J.C.ALBERGOTTI (NRD),NUCL.PHYS.98,65 (1967). 1325 1451 250 FL56 N.N.FLEROV+V.M.TALYZIN (RUS),ATOMNAYA ENERGIYA 1,155 (1956)1325 1451 251 FO71 D.G.FOSTER JR. AND D.W.GLASGOW, PHYS. REV. C 3, 576 (1971) 1325 1451 252 GA62 F.GABBARD+B.D.KERN(KTY), PHYS.REV.128,1276 (1962). 1325 1451 253 GA65 J.B.GARG ET AL., PRIV. COMM. TO R.J.HOWERTON (1965) 1325 1451 254 GL61 R.N.GLOVER+E.WIEGOLD (CBR),NUCL.PHYS.24,630 (1961). 1325 1451 255 GL72 D.W.GLASGOW, PRIVATE COMMUNICATION (1972). 1325 1451 256 GO71 D.T.GOLDMAN, UNPUBLISHED EVALUATION (1971) 1325 1451 257 GR53 E.R.GRAVES+L.ROSEN(LAS),PHYS.REV.89,343 (1953). 1325 1451 258 GR55 E.R.GRAVES+R.W.DAVIS(LAS), PHYS.REV.97, 1205(1955). 1325 1451 259 GR58 J.A.GRUNDL ET AL.(LAS),PHYS.REV.109,425 (1958). 1325 1451 260 GR67 J.A.GRUNDL (LAS), NUCL.SCI.ENG.30,69 (1967). 1325 1451 261 HA69 R.HARDELL ET AL., NUCL.PHYS.A126,392 (1969). 1325 1451 262 HE50 R.L.HENKEL AND H.H.BARSCHALL, PHYS. REV. 80, 145 (1950) 1325 1451 263 HE53 R.L.HENKEL, PRIV. COMM. TO SIGMA CENTER (1953) 1325 1451 264 HI59 C.T.HIBDON, PHYS. REV. 114, 179 (1959) 1325 1451 265 HO69 B.HOLMQVIST+T.WIEDLING (AE), AE-366 (1969). 1325 1451 266 IM64 W.L.IMHOF (LOK),PRIVATE COMMUNICATION TO BNL SIGMA CENTER 1325 1451 267 (1964). 1325 1451 268 JO64 G.D.JOANOU+C.A.STEVENS (GA), GA-5884 (1964). 1325 1451 269 JU71 E.T.JURNEY, PRIVATE COMMUNICATION (1971) 1325 1451 270 KA72 J.L.KAMMERDIENER,THESIS, UNIV.OF CAL.AT DAVIS (1972). 1325 1451 271 KE59 B.D.KERN ET AL.(NRD), NUCL.PHYS.10,226 (1959). 1325 1451 272 KI70 W.E.KINNEY+F.G.PEREY (ORL),ORNL-4516,(1970). 1325 1451 273 LA57 A.LANGSDORF ET AL., PHYS. REV. 107, 1077 (1957) 1325 1451 274 LI66 H.LISKIEN AND A.PAULSEN, NUCLEONICS 8,315 (1966). 1325 1451 275 MA57 M.H.MACGREGOR ET AL.(LRL), PHYS.REV.108,726(1957). 1325 1451 276 MA60 G.S.MANI ET AL.(HAR),NUCL.PHYS.19,535 (1960). 1325 1451 277 MA65 S.C.MATHUR ET AL.(TNC),NUCL.PHYS.73,561 (1965). 1325 1451 278 MA68 G.N.MASLOV ET AL.(RUS),SOV.J.AT.ENERGY 24,704 (1968). 1325 1451 279 MA69 R.E.MAERKER AND F.J.MUCKENTHALER, ORNL-4382 (1969). 1325 1451 280 ME52 A.W.MERRISON AND E.R.WIBLIN, PROC.ROY.SOC.(L) 215,278(1952)1325 1451 281 MI68 A.MITTLER ET AL.(KTY), BULL.AM.PHYS.SOC.13,1420 (1968). 1325 1451 282 OR71 V.J.ORPHAN AND C.G.HOOT, GULF-RT-A10743, (1971). 1325 1451 283 PA65 A.PAULSEN+H.LISKIEN (GEL),J.NUCL.ENERGY 19,907 (1965). 1325 1451 284 PE64 J.L.PERKIN (ALD),NUCL.PHYS.60,561 (1964). 1325 1451 285 PE72 F.G.PEREY ET AL., ORNL-4823 (1972). 1325 1451 286 PH52 D.D.PHILLIPS ET AL.(LAS), PHYS.REV.88,600 (1952). 1325 1451 287 PR60 J.T.PRUDHOMME ET AL.(TNC),AFSWC-TR-60-30 (1960). 1325 1451 288 RA70 N.C.RASMUSSEN ET AL., GA-10248 (1970) 1325 1451 289 SC61 H.W.SCHMITT+J.HALPERIN(ORL),PHYS.REV.121,827 (1961). 1325 1451 290 SC70 R.B.SCHWARTZ, PRIVATE COMMUNICATION (1970) 1325 1451 291 ST59 C.ST.PIERRE ET AL.(MON), PHYS.REV.115,999 (1959). 1325 1451 292 ST62 T.P.STUART ET AL., PHYS. REV. 125, 276 (1962) 1325 1451 293 ST65 P.H.STELSON+R.L.ROBINSON (ORL), NUCL.PHYS.68,97 (1965). 1325 1451 294 TA55 H.L.TAYLOR ET AL.(RIC), PHYS.REV.100,174 (1955). 1325 1451 295 TA70 S.TANAKA ET AL., NUCL.DATA FOR REACTORS (IAEA,1970),P317. 1325 1451 296 TH63 D.B.THOMPSON (LAS),PHYS.REV.129,1649 (1963). 1325 1451 297 TO62 J.H.TOWLE AND W.B.GILBOY, NUCL. PHYS. 39, 300 (1962) 1325 1451 298 TO67 J.H.TOWLE+R.O.OWENS(ALD),NUCL.PHYS.A100,257 (1967). 1325 1451 299 TS61 K.TSUKADA ET AL., PHYSICS OF FAST AND INTERMEDIATE 1325 1451 300 REACTORS, VIENNA (1961). 1325 1451 301 WI63 D.WINTERHALTER (ZAG), NUCL.PHYS.43,339(1963). 1325 1451 302 YO72 P.G.YOUNG, LASL MEMO T-2-99 TO THE NORM. AND STANDARDS 1325 1451 303 SUBCOMMITTEE OF CSEWG, (1972). 1325 1451 304 1 451 314 01325 1451 305 2 151 4 01325 1451 306 3 16 9 01325 1451 307 3 102 40 01325 1451 308 3 103 41 01325 1451 309 3 107 31 01325 1451 310 33 16 4 01325 1451 311 33 102 16 01325 1451 312 33 103 18 01325 1451 313 33 107 15 01325 1451 314 1325 1 0 315 1325 0 0 316 1.302700+4 2.675000+1 0 0 1 01325 2151 317 1.302700+4 1.000000+0 0 0 1 01325 2151 318 1.000000-5 1.000000+3 0 0 0 01325 2151 319 2.500000+0 3.275200-1 0 0 0 01325 2151 320 1325 2 0 321 1325 0 0 322 1.302700+4 2.675000+1 0 0 0 01325 3 16 323 -1.305700+7-1.305700+7 0 0 1 161325 3 16 324 16 2 0 0 0 01325 3 16 325 1.354500+7 0.000000+0 1.375000+7 9.525700-3 1.400000+7 2.400000-21325 3 16 326 1.425000+7 4.557200-2 1.450000+7 7.306900-2 1.500000+7 1.232000-11325 3 16 327 1.550000+7 1.689100-1 1.600000+7 2.071000-1 1.650000+7 2.387500-11325 3 16 328 1.700000+7 2.651000-1 1.750000+7 2.857900-1 1.800000+7 3.030000-11325 3 16 329 1.850000+7 3.175800-1 1.900000+7 3.300000-1 1.950000+7 3.400900-11325 3 16 330 2.000000+7 3.500000-1 0.000000+0 0.000000+0 0.000000+0 0.000000+01325 3 16 331 1325 3 0 332 1.302700+4 2.675000+1 0 0 0 01325 3102 333 7.724000+6 7.724000+6 0 0 2 1101325 3102 334 10 5 110 2 0 01325 3102 335 1.000000-5 1.167000+1 1.000000-4 3.690000+0 1.000000-3 1.167000+01325 3102 336 1.000000-2 3.690000-1 2.530000-2 2.320000-1 1.000000-1 1.170000-11325 3102 337 1.000000+0 3.690000-2 1.000000+1 1.170000-2 1.000000+2 3.690000-31325 3102 338 1.000000+3 1.800000-3 2.000000+3 2.755600-3 4.000000+3 4.666700-31325 3102 339 5.500000+3 6.100000-3 5.600000+3 6.800000-3 5.700000+3 8.700000-31325 3102 340 5.800000+3 1.800000-2 5.820000+3 2.500000-2 5.840000+3 3.800000-21325 3102 341 5.850000+3 5.100000-2 5.860000+3 7.200000-2 5.870000+3 1.110000-11325 3102 342 5.880000+3 1.950000-1 5.890000+3 4.190000-1 5.900000+3 1.088000+01325 3102 343 5.906000+3 1.478000+0 5.910000+3 1.275000+0 5.920000+3 5.030000-11325 3102 344 5.930000+3 2.230000-1 5.940000+3 1.220000-1 5.950000+3 7.800000-21325 3102 345 5.960000+3 5.400000-2 5.980000+3 3.200000-2 6.000000+3 2.200000-21325 3102 346 6.020000+3 1.600000-2 6.040000+3 1.340000-2 6.060000+3 1.140000-21325 3102 347 6.080000+3 1.000000-2 6.100000+3 9.100000-3 6.200000+3 6.900000-31325 3102 348 7.000000+3 5.300000-3 8.000000+3 4.200000-3 9.000000+3 3.800000-31325 3102 349 1.000000+4 3.400000-3 1.500000+4 2.900000-3 2.000000+4 2.900000-31325 3102 350 2.500000+4 3.100000-3 3.000000+4 4.000000-3 3.200000+4 6.200000-31325 3102 351 3.300000+4 9.600000-3 3.400000+4 2.300000-2 3.420000+4 2.800000-21325 3102 352 3.440000+4 3.600000-2 3.460000+4 4.600000-2 3.480000+4 5.500000-21325 3102 353 3.500000+4 6.000000-2 3.520000+4 5.800000-2 3.540000+4 4.900000-21325 3102 354 3.560000+4 4.000000-2 3.580000+4 3.100000-2 3.600000+4 2.500000-21325 3102 355 3.700000+4 1.010000-2 3.800000+4 6.300000-3 4.000000+4 4.100000-31325 3102 356 4.200000+4 3.500000-3 4.400000+4 3.300000-3 5.000000+4 1.800000-31325 3102 357 5.500000+4 1.000000-3 6.000000+4 9.000000-4 7.000000+4 8.000000-41325 3102 358 7.600000+4 1.300000-3 8.000000+4 2.300000-3 8.500000+4 3.600000-31325 3102 359 9.000000+4 3.000000-3 9.400000+4 2.300000-3 9.600000+4 2.700000-31325 3102 360 9.800000+4 4.900000-3 9.900000+4 6.000000-3 1.000000+5 4.700000-31325 3102 361 1.020000+5 2.100000-3 1.050000+5 1.500000-3 1.100000+5 1.100000-31325 3102 362 1.120000+5 1.300000-3 1.140000+5 1.600000-3 1.160000+5 2.500000-31325 3102 363 1.180000+5 4.300000-3 1.200000+5 5.900000-3 1.220000+5 4.300000-31325 3102 364 1.240000+5 2.400000-3 1.260000+5 1.900000-3 1.300000+5 1.900000-31325 3102 365 1.340000+5 2.400000-3 1.400000+5 2.700000-3 1.450000+5 2.800000-31325 3102 366 1.500000+5 2.700000-3 1.550000+5 2.500000-3 1.600000+5 2.200000-31325 3102 367 1.640000+5 1.700000-3 1.700000+5 1.300000-3 2.000000+5 8.700000-41325 3102 368 3.000000+5 7.100000-4 4.000000+5 9.800000-4 5.000000+5 3.900000-41325 3102 369 8.000000+5 2.800000-4 1.000000+6 1.300000-4 2.000000+6 1.500000-41325 3102 370 3.000000+6 1.000000-4 4.000000+6 6.800000-5 5.000000+6 4.600000-51325 3102 371 1.500000+7 5.500000-4 2.000000+7 1.000000-3 0.000000+0 0.000000+01325 3102 372 1325 3 0 373 1.302700+4 2.675000+1 0 0 0 01325 3103 374 -1.827800+6-1.827800+6 0 0 3 1141325 3103 375 3 2 23 4 114 21325 3103 376 1.896100+6 0.000000+0 2.000000+6 9.09000-15 2.050000+6 2.18040-121325 3103 377 2.100000+6 5.23000-10 2.150000+6 9.748700-9 2.200000+6 6.600000-81325 3103 378 2.250000+6 3.302100-7 2.300000+6 1.150000-6 2.350000+6 3.320200-61325 3103 379 2.400000+6 8.000000-6 2.450000+6 1.708900-5 2.500000+6 3.280000-51325 3103 380 2.550000+6 5.835200-5 2.600000+6 9.690000-5 2.650000+6 1.526200-41325 3103 381 2.700000+6 2.290000-4 2.750000+6 3.299800-4 2.800000+6 4.590000-41325 3103 382 2.850000+6 6.208200-4 2.900000+6 8.180000-4 2.950000+6 1.053800-31325 3103 383 3.000000+6 1.330000-3 3.010000+6 1.390700-3 3.100000+6 2.010000-31325 3103 384 3.200000+6 2.460000-3 3.300000+6 2.930000-3 3.330000+6 3.178200-31325 3103 385 3.360000+6 3.625400-3 3.370000+6 3.860300-3 3.380000+6 4.178000-31325 3103 386 3.400000+6 5.100000-3 3.420000+6 6.336000-3 3.450000+6 8.900000-31325 3103 387 3.470000+6 9.864000-3 3.490000+6 1.015600-2 3.500000+6 1.010000-21325 3103 388 3.520000+6 9.780000-3 3.530000+6 9.280000-3 3.580000+6 5.340000-31325 3103 389 3.590000+6 4.830000-3 3.600000+6 4.600000-3 3.610000+6 4.978000-31325 3103 390 3.620000+6 5.652000-3 3.650000+6 8.700000-3 3.660000+6 9.062000-31325 3103 391 3.680000+6 9.212000-3 3.700000+6 9.100000-3 3.800000+6 7.700000-31325 3103 392 3.880000+6 7.076000-3 3.900000+6 7.000000-3 3.990000+6 6.942300-31325 3103 393 4.000000+6 6.966700-3 4.100000+6 7.500000-3 4.150000+6 7.952100-31325 3103 394 4.200000+6 8.600000-3 4.250000+6 9.543700-3 4.300000+6 1.070000-21325 3103 395 4.400000+6 1.350000-2 4.500000+6 1.700000-2 4.550000+6 1.900000-21325 3103 396 4.600000+6 2.155600-2 4.650000+6 2.174200-2 4.700000+6 2.000000-21325 3103 397 4.750000+6 1.750000-2 4.800000+6 1.650000-2 4.850000+6 1.677500-21325 3103 398 4.900000+6 1.800000-2 5.000000+6 2.330000-2 5.100000+6 2.634000-21325 3103 399 5.200000+6 2.833600-2 5.400000+6 3.316400-2 5.600000+6 3.770400-21325 3103 400 5.800000+6 4.207600-2 6.000000+6 4.640000-2 6.200000+6 5.061600-21325 3103 401 6.400000+6 5.486400-2 6.600000+6 5.928800-2 6.800000+6 6.367200-21325 3103 402 7.000000+6 6.780000-2 7.200000+6 7.155200-2 7.400000+6 7.520800-21325 3103 403 7.600000+6 7.880000-2 7.800000+6 8.228000-2 8.000000+6 8.560000-21325 3103 404 8.200000+6 8.897600-2 8.400000+6 9.190400-2 8.600000+6 9.414400-21325 3103 405 8.800000+6 9.605600-2 9.000000+6 9.800000-2 9.200000+6 1.004800-11325 3103 406 9.400000+6 1.023200-1 9.600000+6 1.034000-1 9.800000+6 1.039000-11325 3103 407 1.000000+7 1.040000-1 1.050000+7 1.025200-1 1.100000+7 1.000000-11325 3103 408 1.150000+7 9.601500-2 1.200000+7 9.220000-2 1.250000+7 8.823700-21325 3103 409 1.300000+7 8.500000-2 1.350000+7 8.157400-2 1.400000+7 7.770000-21325 3103 410 1.450000+7 7.397400-2 1.500000+7 7.000000-2 1.550000+7 6.640400-21325 3103 411 1.600000+7 6.270000-2 1.650000+7 5.880700-2 1.700000+7 5.520000-21325 3103 412 1.750000+7 5.168100-2 1.800000+7 4.780000-2 1.850000+7 4.400000-21325 3103 413 1.900000+7 4.020000-2 1.950000+7 3.638500-2 2.000000+7 3.220000-21325 3103 414 1325 3 0 415 1.302700+4 2.675000+1 0 0 0 01325 3107 416 -3.131600+6-3.131600+6 0 0 3 841325 3107 417 3 2 39 4 84 21325 3107 418 3.248700+6 0.000000+0 3.600000+6 3.16000-22 3.650000+6 1.01400-201325 3107 419 3.700000+6 3.25360-19 3.800000+6 3.35000-16 3.850000+6 3.56170-151325 3107 420 3.900000+6 2.88380-14 3.950000+6 1.77820-13 4.000000+6 8.35000-131325 3107 421 4.050000+6 3.67430-12 4.100000+6 1.42220-11 4.150000+6 4.84190-111325 3107 422 4.200000+6 1.45000-10 4.250000+6 4.09650-10 4.300000+6 1.075800-91325 3107 423 4.350000+6 2.626300-9 4.400000+6 5.960000-9 4.450000+6 1.293100-81325 3107 424 4.500000+6 2.678600-8 4.550000+6 5.296900-8 4.600000+6 1.000000-71325 3107 425 4.650000+6 1.832000-7 4.700000+6 3.252000-7 4.750000+6 5.593000-71325 3107 426 4.800000+6 9.320000-7 4.850000+6 1.516200-6 4.900000+6 2.410700-61325 3107 427 4.950000+6 3.746200-6 5.000000+6 5.690000-6 5.100000+6 1.246400-51325 3107 428 5.200000+6 2.550000-5 5.300000+6 4.924200-5 5.400000+6 9.020000-51325 3107 429 5.500000+6 1.580300-4 5.600000+6 2.650000-4 5.700000+6 4.270000-41325 3107 430 5.800000+6 6.670000-4 5.900000+6 1.010000-3 6.000000+6 1.490000-31325 3107 431 6.100000+6 2.140000-3 6.200000+6 2.990000-3 6.300000+6 4.000000-31325 3107 432 6.400000+6 5.140000-3 6.500000+6 6.540000-3 6.600000+6 8.200000-31325 3107 433 6.700000+6 9.870000-3 6.800000+6 1.180000-2 6.900000+6 1.370000-21325 3107 434 7.000000+6 1.590000-2 7.200000+6 2.010000-2 7.400000+6 2.500000-21325 3107 435 7.600000+6 3.000000-2 7.800000+6 3.560000-2 8.000000+6 4.130000-21325 3107 436 8.200000+6 4.710000-2 8.400000+6 5.330000-2 8.600000+6 5.920000-21325 3107 437 8.800000+6 6.490000-2 9.000000+6 7.020000-2 9.200000+6 7.510000-21325 3107 438 9.400000+6 7.970000-2 9.600000+6 8.380000-2 9.800000+6 8.770000-21325 3107 439 1.000000+7 9.120000-2 1.050000+7 9.961200-2 1.100000+7 1.075000-11325 3107 440 1.150000+7 1.149300-1 1.200000+7 1.212000-1 1.250000+7 1.260400-11325 3107 441 1.300000+7 1.288000-1 1.350000+7 1.279400-1 1.400000+7 1.247000-11325 3107 442 1.450000+7 1.193600-1 1.500000+7 1.129000-1 1.550000+7 1.052100-11325 3107 443 1.600000+7 9.700000-2 1.650000+7 8.840600-2 1.700000+7 7.940000-21325 3107 444 1.750000+7 7.118700-2 1.800000+7 6.370000-2 1.850000+7 5.653700-21325 3107 445 1.900000+7 4.980000-2 1.950000+7 4.343700-2 2.000000+7 3.800000-21325 3107 446 1325 3 0 447 1325 0 0 448 1.302700+4 2.675000+1 0 0 0 1132533 16 449 0.000000+0 0.000000+0 0 16 0 1132533 16 450 0.000000+0 0.000000+0 0 1 6 3132533 16 451 1.000000-5 0.000000+0 1.354500+7 2.500000-1 2.000000+7 0.000000+0132533 16 452 132533 0 453 1.302700+4 2.675000+1 0 0 0 1132533102 454 0.000000+0 0.000000+0 0 102 0 4132533102 455 0.000000+0 0.000000+0 0 1 22 11132533102 456 1.000000-5 9.000000-4 1.000000+2 1.000000-2 4.000000+3 1.000000-2132533102 457 1.000000+5 1.000000-2 1.000000+6 2.000000-2 3.000000+6 4.000000-2132533102 458 5.000000+6 6.000000-2 8.000000+6 1.000000-1 1.100000+7 2.000000-3132533102 459 1.400000+7 2.000000-3 2.000000+7 0.000000+0 0.000000+0 0.000000+0132533102 460 0.000000+0 0.000000+0 0 2 8 4132533102 461 1.000000-5 3.000000-2 1.000000+2 5.000000-2 4.000000+3 0.000000+0132533102 462 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0132533102 463 0.000000+0 0.000000+0 0 2 12 6132533102 464 1.000000-5 0.000000+0 1.000000+2 5.000000-2 4.000000+3 1.700000-1132533102 465 5.000000+6 2.800000-1 1.100000+7 0.000000+0 2.000000+7 0.000000+0132533102 466 0.000000+0 0.000000+0 0 2 10 5132533102 467 1.000000-5 0.000000+0 5.000000+6 2.800000-1 8.000000+6 5.000000-1132533102 468 1.100000+7 9.000000-1 2.000000+7 0.000000+0 0.000000+0 0.000000+0132533102 469 132533 0 470 1.302700+4 2.675000+1 0 0 0 1132533103 471 0.000000+0 0.000000+0 0 103 0 3132533103 472 0.000000+0 0.000000+0 0 1 46 23132533103 473 1.000000-5 0.000000+0 1.899000+6 6.250000-2 2.000000+6 4.000000-2132533103 474 2.200000+6 2.900000-2 2.400000+6 2.250000-2 2.600000+6 1.700000-2132533103 475 2.800000+6 1.650000-2 3.000000+6 1.400000-2 3.300000+6 1.200000-2132533103 476 3.700000+6 1.000000-2 4.100000+6 8.000000-3 4.500000+6 6.500000-3132533103 477 5.000000+6 5.000000-3 5.500000+6 4.500000-3 6.000000+6 3.500000-3132533103 478 7.000000+6 6.500000-3 8.000000+6 8.000000-3 9.000000+6 6.500000-3132533103 479 1.100000+7 5.000000-3 1.300000+7 4.500000-3 1.500000+7 6.000000-3132533103 480 1.700000+7 1.000000-2 2.000000+7 0.000000+0 0.000000+0 0.000000+0132533103 481 0.000000+0 0.000000+0 0 2 16 8132533103 482 1.000000-5 0.000000+0 1.899000+6 3.000000-1 2.400000+6 2.000000-1132533103 483 2.800000+6 1.500000-1 3.300000+6 1.000000-1 4.500000+6 8.000000-2132533103 484 5.500000+6 0.000000+0 2.000000+7 0.000000+0 0.000000+0 0.000000+0132533103 485 0.000000+0 0.000000+0 0 1 12 6132533103 486 1.000000-5 0.000000+0 5.500000+6 5.000000-3 8.000000+6 1.450000-2132533103 487 1.300000+7 6.500000-3 1.700000+7 1.000000-2 2.000000+7 0.000000+0132533103 488 132533 0 489 1.302700+4 2.675000+1 0 0 0 1132533107 490 0.000000+0 0.000000+0 0 107 0 3132533107 491 0.000000+0 0.000000+0 0 1 30 15132533107 492 1.000000-5 0.000000+0 3.248000+6 9.000000-2 3.500000+6 4.000000-2132533107 493 4.000000+6 2.000000-2 4.500000+6 8.000000-3 5.000000+6 6.500000-3132533107 494 5.500000+6 3.500000-3 6.000000+6 2.500000-3 7.000000+6 1.600000-3132533107 495 8.000000+6 9.000000-4 9.000000+6 9.000000-4 1.000000+7 6.000000-4132533107 496 1.200000+7 9.000000-4 1.500000+7 1.200000-3 2.000000+7 0.000000+0132533107 497 0.000000+0 0.000000+0 0 2 16 8132533107 498 1.000000-5 0.000000+0 3.248000+6 4.000000-1 4.000000+6 2.000000-1132533107 499 5.000000+6 8.000000-2 6.000000+6 6.000000-2 9.000000+6 5.000000-2132533107 500 1.200000+7 0.000000+0 2.000000+7 0.000000+0 0.000000+0 0.000000+0132533107 501 0.000000+0 0.000000+0 0 1 8 4132533107 502 1.000000-5 0.000000+0 1.200000+7 1.600000-3 1.500000+7 1.300000-3132533107 503 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0132533107 504 132533 0 505 1325 0 0 506 0 0 0 507 1.503100+4 3.070800+1 0 0 0 01525 1451 1 0.000000+0 0.000000+0 0 0 0 61525 1451 2 1.000000+0 0.000000+0 0 0 10 61525 1451 3 0.000000+0 0.000000+0 0 0 12 41525 1451 4 15-P - 31 LLNL EVAL-OCT77 HOWERTON 1525 1451 5 UCRL 50400 VOL15(E) DIST-JAN90 900123 1525 1451 6 ----ENDF/B-VI MATERIAL 1525 1525 1451 7 -----INCIDENT NEUTRON DATA 1525 1451 8 ------ENDF-6 FORMAT 1525 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1525 1451 10 ACTIVATION I 1525 1451 11 ******************************************************************1525 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1525 1451 13 * * * * * * *1525 1451 14 PART E (TO BE ISSUED IN JAN-1978) 1525 1451 15 1525 1451 16 1 451 20 01525 1451 17 2 151 4 01525 1451 18 3 102 33 01525 1451 19 3 103 13 01525 1451 20 1525 1 0 21 1525 0 0 22 1.503100+4 3.070800+1 0 0 1 01525 2151 23 1.503100+4 1.000000+0 0 0 1 01525 2151 24 1.000000-5 2.000000+7 0 0 0 01525 2151 25 5.000000-1 5.710000-1 0 0 0 01525 2151 26 1525 2 0 27 1525 0 0 28 1.503100+4 3.070800+1 0 0 0 01525 3102 29 7.930000+6 7.930000+6 0 0 2 891525 3102 30 2 5 89 2 0 01525 3102 31 1.000000-5 8.473320+0 1.000000-4 2.679500+0 1.219000-4 2.441400+01525 3102 32 1.477700-4 2.230300+0 1.785900-4 2.040300+0 2.141200-4 1.873500+01525 3102 33 2.546600-4 1.726900+0 3.021200-4 1.593600+0 3.569500-4 1.473400+01525 3102 34 4.190500-4 1.366500+0 4.918400-4 1.267400+0 5.742400-4 1.178400+01525 3102 35 6.669200-4 1.098300+0 7.705100-4 1.026300+0 8.899500-4 9.590900-11525 3102 36 1.022500-3 8.985100-1 1.168000-3 8.440300-1 1.335300-3 7.925700-11525 3102 37 1.523700-3 7.449000-1 1.740100-3 6.998300-1 1.974600-3 6.594500-11525 3102 38 2.243700-3 6.210100-1 2.532200-3 5.867000-1 2.861500-3 5.539300-11525 3102 39 3.615100-3 4.963100-1 4.539300-3 4.459400-1 5.626000-3 4.031500-11525 3102 40 6.927800-3 3.655800-1 8.491700-3 3.322200-1 1.054500-2 3.000800-11525 3102 41 1.304000-2 2.715700-1 1.600500-2 2.466300-1 1.947900-2 2.248900-11525 3102 42 2.351500-2 2.058400-1 2.832000-2 1.886200-1 3.389000-2 1.733500-11525 3102 43 4.015300-2 1.600700-1 4.895400-2 1.441500-1 5.657200-2 1.329400-11525 3102 44 6.636100-2 1.215800-1 7.543800-2 1.135800-1 8.893400-2 1.044400-11525 3102 45 1.043200-1 9.627500-2 1.217700-1 8.897600-2 1.414200-1 8.243900-21525 3102 46 1.699200-1 7.499400-2 2.023300-1 6.850700-2 2.397200-1 6.274300-21525 3102 47 2.826100-1 5.761300-2 3.315100-1 5.303900-2 3.888700-1 4.882900-21525 3102 48 4.516400-1 4.518500-2 5.245300-1 4.181400-2 6.000000-1 3.900000-21525 3102 49 6.662500-1 3.720700-2 7.699400-1 3.486500-2 8.853300-1 3.274400-21525 3102 50 1.056400+0 3.017000-2 1.190700+0 2.843500-2 1.348900+0 2.673300-21525 3102 51 1.528000+0 2.513400-2 1.739500+0 2.357200-2 1.970500+0 2.216100-21525 3102 52 2.232200+0 2.083500-2 2.516100+0 1.963700-2 2.836000+0 1.850800-21525 3102 53 3.265500+0 1.721500-2 4.066800+0 1.533800-2 4.964700+0 1.381000-21525 3102 54 6.000000+0 1.250000-2 7.361400+0 1.133700-2 9.000000+0 1.030000-21525 3102 55 4.232300+1 9.823900-3 6.900100+1 9.579000-3 1.119300+2 9.342700-31525 3102 56 1.701800+2 9.142800-3 3.542600+2 8.803100-3 6.445400+2 8.535300-31525 3102 57 1.093600+3 8.305400-3 1.721700+3 8.113000-3 3.656300+3 7.803600-31525 3102 58 7.133300+3 7.538900-3 1.240900+4 7.326500-3 1.993000+4 7.149400-31525 3102 59 3.000000+4 7.000000-3 3.000000+5 2.000000-3 3.000000+6 7.000000-41525 3102 60 1.400000+7 3.000000-4 2.000000+7 2.000000-4 0.000000+0 0.000000+01525 3102 61 1525 3 0 62 1.503100+4 3.070800+1 0 0 0 01525 3103 63 -7.100000+5-7.100000+5 0 0 1 301525 3103 64 30 2 0 0 0 01525 3103 65 7.331210+5 0.000000+0 1.500000+6 0.000000+0 1.590000+6 1.300000-31525 3103 66 1.650000+6 5.000000-3 2.200000+6 2.800000-2 2.500000+6 5.000000-21525 3103 67 2.730000+6 9.000000-2 2.780000+6 6.400000-2 2.840000+6 9.000000-21525 3103 68 2.940000+6 5.500000-2 3.125000+6 1.120000-1 3.210000+6 8.300000-21525 3103 69 3.350000+6 6.600000-2 3.460000+6 8.000000-2 3.500000+6 7.200000-21525 3103 70 3.610000+6 9.000000-2 3.720000+6 1.500000-1 3.820000+6 1.050000-11525 3103 71 4.140000+6 8.600000-2 4.220000+6 1.100000-1 4.350000+6 1.140000-11525 3103 72 4.425000+6 1.080000-1 4.540000+6 1.300000-1 4.800000+6 1.340000-11525 3103 73 5.050000+6 1.000000-1 5.500000+6 1.300000-1 1.000000+7 1.400000-11525 3103 74 1.200000+7 1.200000-1 1.400000+7 9.000000-2 2.000000+7 7.000000-21525 3103 75 1525 3 0 76 1525 0 0 77 0 0 0 78 1.603200+4 3.169700+1 -1 0 0 01625 1451 1 0.000000+0 0.000000+0 0 0 0 61625 1451 2 1.000000+0 0.000000+0 0 0 10 61625 1451 3 0.000000+0 0.000000+0 0 0 12 21625 1451 4 16-S - 32 LLNL EVAL-OCT77 HOWERTON 1625 1451 5 UCRL 50400 VOL15(E) DIST-JAN90 900123 1625 1451 6 ----ENDF/B-VI MATERIAL 1625 1625 1451 7 -----INCIDENT NEUTRON DATA 1625 1451 8 ------ENDF-6 FORMAT 1625 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1625 1451 10 ACTIVATION I 1625 1451 11 ******************************************************************1625 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1625 1451 13 * * * * * * *1625 1451 14 PART E (TO BE ISSUED IN JAN-1978) 1625 1451 15 1625 1451 16 1 451 18 01625 1451 17 3 103 16 01625 1451 18 1625 1 0 19 1625 0 0 20 1.603200+4 3.169700+1 0 0 0 01625 3103 21 -9.200000+5-9.200000+5 0 0 1 381625 3103 22 38 2 0 0 0 01625 3103 23 9.490250+5 0.000000+0 1.600000+6 0.000000+0 1.700000+6 1.000000-31625 3103 24 1.780000+6 4.600000-3 1.810000+6 5.950000-3 1.900000+6 1.000000-21625 3103 25 1.920000+6 1.167000-2 2.020000+6 2.000000-2 2.180000+6 3.600000-21625 3103 26 2.200000+6 3.800000-2 2.320000+6 5.000000-2 2.550000+6 7.300000-21625 3103 27 2.600000+6 7.800000-2 2.700000+6 8.800000-2 2.750000+6 9.300000-21625 3103 28 2.800000+6 9.800000-2 2.850000+6 1.030000-1 2.950000+6 1.130000-11625 3103 29 3.020000+6 1.200000-1 3.075000+6 1.301000-1 3.120000+6 1.384000-11625 3103 30 3.300000+6 1.714000-1 3.450000+6 1.990000-1 3.750000+6 2.541000-11625 3103 31 3.840000+6 2.706000-1 3.920000+6 2.853000-1 3.950000+6 2.908000-11625 3103 32 4.000000+6 3.000000-1 4.520000+6 2.682000-1 4.900000+6 2.450000-11625 3103 33 5.270000+6 2.450000-1 6.000000+6 3.200000-1 8.000000+6 3.600000-11625 3103 34 1.100000+7 3.850000-1 1.310000+7 2.917000-1 1.460000+7 2.250000-11625 3103 35 1.650000+7 1.300000-1 2.000000+7 8.500000-2 0.000000+0 0.000000+01625 3103 36 1625 3 0 37 1625 0 0 38 0 0 0 39 1.804000+4 3.961910+1 1 0 0 01837 1451 1 0.000000+0 0.000000+0 0 0 0 61837 1451 2 1.000000+0 0.000000+0 0 0 10 61837 1451 3 0.000000+0 0.000000+0 0 0 21 31837 1451 4 18-AR- 40 HEDL EVAL-JAN79 MANN 1837 1451 5 DIST-JAN90 900123 1837 1451 6 ----ENDF/B-VI MATERIAL 1837 1837 1451 7 -----INCIDENT NEUTRON DATA 1837 1451 8 ------ENDF-6 FORMAT 1837 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1837 1451 10 ACTIVATION I 1837 1451 11 ******************************************************************1837 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1837 1451 13 * * * * * * *1837 1451 14 MF= 2, MT= 151 RESOLVED RESONANCE REGION 1.0E-5 TO 5.75E+5 1837 1451 15 --- RESONANCE ENERGIES AND NEUTRON WIDTHS ARE FROM BNL-325, VOL 1 1837 1451 16 (1973), WHILE THE GAMMA WIDTH WAS CHOSEN TO MATCH THE DATA OF 1837 1451 17 BOSTROM ET AL (WADC-TR-59-107/(1959)). 1837 1451 18 --- A BOUND STATE WAS ADDED TO OBTAIN THE THERMAL CAPTURE CROSS 1837 1451 19 SECTION OF BNL-325(BNL-325= 0.66+-.01, EVALUATION= .65). 1837 1451 20 HOWEVER RESONANCE INTEGRAL IS LOW (BNL-325= 0.41+-.03, 1837 1451 21 EVALUATION= .29) 1837 1451 22 MF= 3, MT= 102 SMOOTH CAPTURE CROSS SECTION 1837 1451 23 --- EVALUATION BASED ON HAUSER-FESHBACH CALCULATION WHICH PASSES 1837 1451 24 THROUGH DATA OF BOSTROM ET AL. 1837 1451 25 1 451 28 01837 1451 26 2 151 28 01837 1451 27 3 102 10 01837 1451 28 1837 1 0 29 1837 0 0 30 1.804000+4 3.961910+1 0 0 1 01837 2151 31 1.804000+4 1.000000+0 0 0 1 01837 2151 32 1.000000-5 5.000000+5 1 1 0 01837 2151 33 0.000000+0 5.000000-1 0 0 2 01837 2151 34 3.961910+1 0.000000+0 0 0 42 71837 2151 35 -2.330000+4 5.000000-1 5.002400+3 5.000000+3 2.400000+0 0.000000+01837 2151 36 7.730000+4 5.000000-1 5.002400+3 5.000000+3 2.400000+0 0.000000+01837 2151 37 1.728000+5 5.000000-1 4.902400+3 4.900000+3 2.400000+0 0.000000+01837 2151 38 2.200000+5 5.000000-1 2.002400+3 2.000000+3 2.400000+0 0.000000+01837 2151 39 2.551000+5 5.000000-1 3.802400+3 3.800000+3 2.400000+0 0.000000+01837 2151 40 2.684000+5 5.000000-1 4.024000+2 4.000000+2 2.400000+0 0.000000+01837 2151 41 3.906000+5 5.000000-1 1.002400+3 1.000000+3 2.400000+0 0.000000+01837 2151 42 3.961910+1 0.000000+0 1 0 90 151837 2151 43 1.117000+4 5.000000-1 2.490000+0 8.999700-2 2.400000+0 0.000000+01837 2151 44 1.795000+4 5.000000-1 2.658000+0 2.579900-1 2.400000+0 0.000000+01837 2151 45 5.925000+4 5.000000-1 5.939900+0 3.539900+0 2.400000+0 0.000000+01837 2151 46 1.157000+5 5.000000-1 5.323900+2 5.299900+2 2.400000+0 0.000000+01837 2151 47 1.804000+5 5.000000-1 2.624000+2 2.600000+2 2.400000+0 0.000000+01837 2151 48 1.928000+5 5.000000-1 6.839800+1 6.599800+1 2.400000+0 0.000000+01837 2151 49 2.747000+5 5.000000-1 2.183900+2 2.159900+2 2.400000+0 0.000000+01837 2151 50 2.969000+5 5.000000-1 3.374000+2 3.350000+2 2.400000+0 0.000000+01837 2151 51 3.011000+5 5.000000-1 1.424000+2 1.400000+2 2.400000+0 0.000000+01837 2151 52 3.408000+5 1.500000+0 4.623900+2 4.599900+2 2.400000+0 0.000000+01837 2151 53 3.630000+5 5.000000-1 7.439800+1 7.199800+1 2.400000+0 0.000000+01837 2151 54 3.713000+5 1.500000+0 5.423900+2 5.399900+2 2.400000+0 0.000000+01837 2151 55 4.017000+5 5.000000-1 4.823900+2 4.799900+2 2.400000+0 0.000000+01837 2151 56 4.554000+5 5.000000-1 8.623900+2 8.599900+2 2.400000+0 0.000000+01837 2151 57 4.693000+5 1.500000+0 1.202400+3 1.200000+3 2.400000+0 0.000000+01837 2151 58 1837 2 0 59 1837 0 0 60 1.804000+4 3.961910+1 0 0 0 01837 3102 61 6.099000+6 6.099000+6 0 0 1 191837 3102 62 19 2 0 0 0 01837 3102 63 1.000000-5 0.000000+0 5.000000+5 0.000000+0 5.000000+5 1.150000-31837 3102 64 7.500000+5 1.100000-3 1.000000+6 1.120000-3 1.250000+6 1.180000-31837 3102 65 1.500000+6 8.700000-4 2.000000+6 5.000000-4 3.000000+6 3.300000-41837 3102 66 4.000000+6 2.800000-4 5.000000+6 2.500000-4 6.000000+6 2.300000-41837 3102 67 8.000000+6 2.000000-4 1.000000+7 1.800000-4 1.200000+7 1.700000-41837 3102 68 1.400000+7 1.700000-4 1.600000+7 1.600000-4 1.800000+7 1.600000-41837 3102 69 2.000000+7 1.500000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+01837 3102 70 1837 3 0 71 1837 0 0 72 0 0 0 73 1.904100+4 4.060990+1 -1 0 0 01931 1451 1 0.000000+0 0.000000+0 0 0 0 61931 1451 2 1.000000+0 0.000000+0 0 0 10 61931 1451 3 0.000000+0 0.000000+0 0 0 22 21931 1451 4 19-K - 41 HEDL EVAL-JAN79 MANN 1931 1451 5 DIST-JAN90 900123 1931 1451 6 ----ENDF/B-VI MATERIAL 1931 1931 1451 7 -----INCIDENT NEUTRON DATA 1931 1451 8 ------ENDF-6 FORMAT 1931 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************1931 1451 10 ACTIVATION I 1931 1451 11 ******************************************************************1931 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 1931 1451 13 * * * * * * *1931 1451 14 MF= 3, MT= 103 SMOOTH (N,P) CROSS SECTION 1931 1451 15 THE EVALUATION IS BASED ON A NUCLEAR MODEL CALCULATION 1931 1451 16 CONSISTING OF HAUSER-FESHBACH AND PRE-EQUILIBRIUM COMPONENTS. THE1931 1451 17 EVALUATION IS IN GOOD AGREEMENT WITH THE DATA OF BASS ET AL 1931 1451 18 (EANDG(E)-57(1965)P. 1). FOR (N,P)AR-41, FILE 3 MUST BE 1931 1451 19 MULTIPLIED BY QUANTITIES IN FILE 9. 1931 1451 20 MF= 9, MT= 103 (N,P) FRACTION 1931 1451 21 THE EVALUATION IS BASED ON A NUCLEAR MODEL CALCULATION UP 1931 1451 22 TO 16 MEV AND THEREAFTER FOLLOWS THE CROSS SECTIONS MEASURED BY 1931 1451 23 BORMANN ET AL (NUCL. PHYS. A130(1969)195, WHICH ARE A FACTOR OF 2 1931 1451 24 LOWER THAN CALCULATIONS AT 18 MEV. AT LOWER ENERGIES THE 1931 1451 25 AGREEMENT IS GOOD. 1931 1451 26 1 451 28 01931 1451 27 3 103 8 01931 1451 28 1931 1 0 29 1931 0 0 30 1.904100+4 4.060990+1 0 0 0 01931 3103 31 -1.709600+6-1.709600+6 0 0 1 141931 3103 32 14 2 0 0 0 01931 3103 33 1.751000+6 0.000000+0 3.000000+6 4.000000-5 4.000000+6 3.100000-31931 3103 34 5.000000+6 1.330000-2 6.000000+6 1.900000-2 7.000000+6 2.130000-21931 3103 35 8.000000+6 2.860000-2 9.000000+6 3.670000-2 1.000000+7 4.800000-21931 3103 36 1.200000+7 6.660000-2 1.400000+7 8.560000-2 1.600000+7 1.021000-11931 3103 37 1.800000+7 1.174000-1 2.000000+7 1.309000-1 0.000000+0 0.000000+01931 3103 38 1931 3 0 39 1931 0 0 40 0 0 0 41 2.104500+4 4.456790+1 1 0 0 02125 1451 1 0.000000+0 0.000000+0 0 0 0 62125 1451 2 1.000000+0 0.000000+0 0 0 10 62125 1451 3 0.000000+0 0.000000+0 0 0 80 52125 1451 4 21-SC- 45 BNL EVAL-JUL79 MAGURNO AND MUGHABGHAB 2125 1451 5 DIST-JAN90 900123 2125 1451 6 ----ENDF/B-VI MATERIAL 2125 2125 1451 7 -----INCIDENT NEUTRON DATA 2125 1451 8 ------ENDF-6 FORMAT 2125 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2125 1451 10 ACTIVATION I 2125 1451 11 ******************************************************************2125 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2125 1451 13 * * * * * * *2125 1451 14 P.C. TO NORMALIZATION AND STANDARDS SUBCOMMITTEE APRIL 1979 2125 1451 15 SC-45(N,GAMMA). EVALUATED BY B.A.MAGURNO AND S.F.MUGHABGHAB 2125 1451 16 THE POSITIVE ENERGY RESONANCE PARAMETERS LISTED BELOW 2125 1451 17 ARE THOSE EVALUATED FOR BNL-325 4-TH ED.(1)THE PARAMETER 2125 1451 18 SOURCES ARE REF.2,3,4. 2125 1451 19 THE BOUND LEVEL PARAMETERS WERE CHOSEN TO REPRODUCE A 2125 1451 20 CAPTURE CROSS SECTION OF 27.2B (26.4B CONTRIBUTED FROM BOUND 2125 1451 21 LEVEL,0.8B CONTRIBUTED FROM POSITIVE LEVELS).THE BOUND LEVEL 2125 1451 22 SPIN(J=3) CHOICE WAS BASED ON KOPECKY (5) POLARIZATION 2125 1451 23 EXPERIMENT WHICH SHOWED THAT A J=4 LEVEL CONTRIBUTION WOULD BE 2125 1451 24 LESS THAN 8PC. THIS IS IN AGREEMENT WITH RESULTS PREDICTED BY 2125 1451 25 MARSHAK(6),LIOU(2),BOLOTIN(7)AND DELANG(8). 2125 1451 26 IN THE FITTING PROCEDURE CARE WAS TAKEN TO REPRODUCE 2125 1451 27 THE ELASTIC SCATTERING CROSS SECTION RECOMMENDED IN REF1(22.1B)2125 1451 28 AND THE 2 KEV"WINDOW" TOTAL CROSS SECTION IN REF 2(0.71B). 2125 1451 29 KENNY (4) TABULATES THE AVERAGE CAPTURE CROSS 2125 1451 30 SECTION FROM 2 TO 10 KEV IN ONE KEV BINS AND FROM 10 KEV TO 90 2125 1451 31 KEV IN 10 KEV BINS.THE SLOPE OF THE AVERAGE CROSS SECTIONS FROM2125 1451 32 40 TO 90 KEV WAS USED TO EXTROPOLATE THE CROSS SECTION TO ONE 2125 1451 33 MEV. 2125 1451 34 THE CAPTURE CROSS SECTION FROM 1 MEV TO 20 MEV IS A 2125 1451 35 LINE FIT TO PERKIN DATA REFERENCE 12 AND A WEIGHTED AVERAGE OF 2125 1451 36 OF REF9,10,11,12 AT 14.6 MEV. 2125 1451 37 OTHER DATA CONSIDERED IN THE INITIAL EVALUATION BUT FOR2125 1451 38 THE MOST PART IGNORED IN THE FINAL ANAYSIS ARE IN REF 13,14. 2125 1451 39 2125 1451 40 -REFERENCES- 2125 1451 41 2125 1451 42 1.BNL-325 4TH ED. S.F.MUGHABGHAB ET.AL. TO BE PUBLISHED 2125 1451 43 2.LIOU ET.AL. NUC.SCI.AND ENG.67,326,1978 2125 1451 44 3.CHO ET.AL 2ND INT.CONF. NUC. DATA FOR REACT.CONF-700606,619,'702125 1451 45 4.KENNY ET.AL. AUS.J.OF PHYSICS 30,605,197 ) 2125 1451 46 5.KOPECKY ET.AL. TO BE PUBLISHED 2125 1451 47 6.MARSHAK H. BULL.AM.PHYS.SOC.22,993,1977 2125 1451 48 7.BOLOTIN H.H. PHYS.REV.168,1317,1968 2125 1451 49 8.DELANG ET.AL. CONF ON NUC STUDY WITH NEUTRON 2125 1451 50 9.WAGNER M. PRIV.COMM.NOV.1976 2125 1451 51 10.BUDNAR ET.AL. INDC(YUG)-5,1977 2125 1451 52 11.CSIKAI ET.AL. NUC.PHYS./A,95,229,1967 2125 1451 53 12.PERKIN J.L. J.NUC.EN.17,349,1963 2125 1451 54 13.ROMANOV ET.AL. YAD.FIZ.1,229,1965 2125 1451 55 14.BOOTH ET.AL. PHYS.REV.112,226,1958 2125 1451 56 ***** 2125 1451 57 SC-45(N,2N) THIS REACTION WAS EVALUATED FOR USE IN THE SPEC- 2125 1451 58 IAL PURPOSE FILE IN ENDF/B V FOR USE WITH THE INTERNATIONAL 2125 1451 59 REACTOR DOSIMETRY FILE. 2125 1451 60 THE SC(N,2N) WAS CALCULATED WITH THRESH AND ADJUSTED TO FIT 2125 1451 61 EXPERIMENTAL DATA. THE ISOMERIC RATIO ADOPTED WAS 0.71 AT 2125 1451 62 14.8 MEV. 2125 1451 63 ***** 2125 1451 64 REFERENCES 2125 1451 65 MUKHERJEE ET AL PROC. PHYS. COC. 77,508,61 2125 1451 66 PERKIN PRIVATE COMMUNICATION 1961 2125 1451 67 PRESTWOOD & BAYHURST PHYS. REV. 121,1438,61 2125 1451 68 RAYBURN PHYS. REV. 122,168,61 2125 1451 69 ARNOLD & RAYBURN BAPS 9, 352,64 2125 1451 70 TIWARI & KONDAIAH, NUC. & SOLID STATE SYM. BOMBAY FEB 66 2125 1451 71 VALLIS AWRE-0-76/77 2125 1451 72 NETHAWAY NUC. PHYS A1 90,635,72 2125 1451 73 BAYHURST ET AL PHYS. REV. C 12,451,75 2125 1451 74 EAPEN & SALAITA J. INORG. NUC. CHEM. 37,1121,75 2125 1451 75 KAO & ALFORD NUC. PHYS. A 237,11,75 2125 1451 76 PRASAD & SARKAR NUC. PHYS. A 94,476,67 2125 1451 77 CSIKAI & PETO ACT. PHYS. ACAD. SCI. HUNGARY 23,87,67 2125 1451 78 CSIKAI & PETO NUC. PHYS. A 122,234,68 2125 1451 79 WEIGEL ET AL RADIOCHEM. ACTA 22,11,75 2125 1451 80 CEVOLANI & PETRALIA NUOVO CIM. 26,1328,62 2125 1451 81 KHURANA & HANS NUC. PHYS. 28,560,61 2125 1451 82 BRAMLITT & FINK PHYS. REV. 131,2649,63 2125 1451 83 THRESH PEARLSTEIN J. NUC. ENERGY 27,81,73 2125 1451 84 1 451 89 02125 1451 85 2 151 197 02125 1451 86 3 16 9 02125 1451 87 3 102 11 02125 1451 88 33 102 11 02125 1451 89 2125 1 0 90 2125 0 0 91 2.104500+4 4.456790+1 0 0 1 02125 2151 92 2.104500+4 1.000000+0 0 0 1 02125 2151 93 1.000000-5 9.694379+4 1 2 0 02125 2151 94 3.500000+0 4.640000-1 0 0 2 02125 2151 95 4.456790+1 0.000000+0 0 0 474 792125 2151 96 -5.680000+2 3.000000+0 1.199090+2 1.190000+2 9.090000-1 0.000000+02125 2151 97 3.295000+3 3.000000+0 7.842400+1 7.771400+1 7.100000-1 0.000000+02125 2151 98 4.326000+3 4.000000+0 3.135200+2 3.128900+2 6.300000-1 0.000000+02125 2151 99 6.692000+3 3.000000+0 1.378800+2 1.371400+2 7.400000-1 0.000000+02125 2151 100 8.000000+3 4.000000+0 1.427900+2 1.422200+2 5.700000-1 0.000000+02125 2151 101 9.070000+3 4.000000+0 3.640600+1 3.555600+1 8.500000-1 0.000000+02125 2151 102 9.080000+3 3.000000+0 2.993900+2 2.982900+2 1.100000+0 0.000000+02125 2151 103 1.066200+4 3.000000+0 1.080000+1 1.000000+1 8.000000-1 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3.700000-1 0.000000+02125 2151 281 9.525000+4 4.000000+0 2.685400+1 2.666700+1 1.870000-1 0.000000+02125 2151 282 9.644000+4 5.000000+0 1.124600+1 1.090900+1 3.370000-1 0.000000+02125 2151 283 9.690000+4 3.000000+0 4.625400+1 4.571400+1 5.400000-1 0.000000+02125 2151 284 9.826000+4 4.000000+0 2.725300+1 2.666700+1 5.860000-1 0.000000+02125 2151 285 9.858500+4 5.000000+0 2.985500+1 2.909100+1 7.640000-1 0.000000+02125 2151 286 9.908000+4 2.000000+0 6.483000+1 6.400000+1 8.300000-1 0.000000+02125 2151 287 9.920000+4 3.000000+0 5.780500+1 5.714300+1 6.620000-1 0.000000+02125 2151 288 2125 2 0 289 2125 0 0 290 2.104500+4 4.456790+1 0 0 0 02125 3 16 291 -1.132000+7-1.132000+7 0 0 1 172125 3 16 292 17 2 0 0 0 02125 3 16 293 1.157000+7 0.000000+0 1.250000+7 7.300000-2 1.300000+7 1.350000-12125 3 16 294 1.350000+7 1.970000-1 1.400000+7 2.520000-1 1.450000+7 3.000000-12125 3 16 295 1.500000+7 3.400000-1 1.550000+7 3.740000-1 1.600000+7 4.020000-12125 3 16 296 1.650000+7 4.260000-1 1.700000+7 4.460000-1 1.750000+7 4.630000-12125 3 16 297 1.800000+7 4.770000-1 1.850000+7 4.910000-1 1.900000+7 5.030000-12125 3 16 298 1.950000+7 5.120000-1 2.000000+7 5.210000-1 0.000000+0 0.000000+02125 3 16 299 2125 3 0 300 2.104500+4 4.456790+1 0 0 0 02125 3102 301 8.760000+6 8.760000+6 0 0 2 242125 3102 302 3 2 24 5 0 02125 3102 303 1.000000-5 0.000000+0 9.694379+4 0.000000+0 9.694379+4 3.000000-22125 3102 304 1.500000+5 2.343000-2 3.000000+5 1.200000-2 3.600000+5 1.020000-22125 3102 305 4.000000+5 9.600000-3 4.800000+5 8.600000-3 5.200000+5 8.390000-32125 3102 306 6.000000+5 8.100000-3 7.000000+5 8.000000-3 8.000000+5 7.700000-32125 3102 307 9.500000+5 7.330000-3 1.100000+6 6.500000-3 1.300000+6 5.000000-32125 3102 308 1.500000+6 4.000000-3 1.700000+6 2.800000-3 1.900000+6 2.300000-32125 3102 309 2.050000+6 2.020000-3 2.500000+6 1.600000-3 3.500000+6 1.080000-32125 3102 310 4.500000+6 9.300000-4 1.460000+7 7.520000-4 2.000000+7 7.200000-42125 3102 311 2125 3 0 312 2125 0 0 313 2.104500+4 4.456790+1 0 0 0 1212533102 314 0.000000+0 0.000000+0 0 102 0 2212533102 315 0.000000+0 0.000000+0 0 1 8 4212533102 316 1.000000-5 1.500000-5 2.530000-2 1.000000-4 1.000000+6 1.400000-3212533102 317 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0212533102 318 0.000000+0 0.000000+0 0 1 28 14212533102 319 1.000000-5 3.000000-5 8.000000+3 1.400000-3 2.000000+4 3.400000-3212533102 320 5.000000+4 5.000000-3 1.000000+5 1.200000-3 1.500000+5 7.000000-4212533102 321 3.000000+5 2.100000-3 5.000000+5 1.800000-3 6.000000+5 3.800000-3212533102 322 8.000000+5 6.100000-3 1.000000+6 6.500000-3 6.000000+6 1.000000-2212533102 323 1.800000+7 4.000000-2 2.000000+7 0.000000+0 0.000000+0 0.000000+0212533102 324 212533 0 325 2125 0 0 326 0 0 0 327 2.204600+4 4.555780+1 -1 0 0 02225 1451 1 0.000000+0 0.000000+0 0 0 0 62225 1451 2 1.000000+0 0.000000+0 0 0 10 62225 1451 3 0.000000+0 0.000000+0 0 0 30 32225 1451 4 22-TI- 46 BRC,ANL EVAL-JAN77 C.PHILIS,O.BERSILLON,D.SMITH,+ 2225 1451 5 DIST-JAN90 900124 2225 1451 6 ----ENDF/B-VI MATERIAL 2225 2225 1451 7 -----INCIDENT NEUTRON DATA 2225 1451 8 ------ENDF-6 FORMAT 2225 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2225 1451 10 ACTIVATION I 2225 1451 11 ******************************************************************2225 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2225 1451 13 * * * * * * *2225 1451 14 ** 2225 1451 15 DOCUMENTATION ANL/NDM-27 2225 1451 16 ** 2225 1451 17 COMMENTS-EVALUATION IN ENERGY RANGES 3.50E+06 TO 1.0E+07 AND 2225 1451 18 1.25E+07 TO 2.0E+07 BASED ON EXPERIMENTAL DATA.INTERPOLATION AND2225 1451 19 EXTRAPOLATION TO OTHER ENERGIES BASED ON THEORETICAL CALCULATION2225 1451 20 PERFORMED AT BRUYERES LE CHATEL USING A CODE DEVELOPED BY JARRE.2225 1451 21 ** 2225 1451 22 REFERENCES 2225 1451 23 AL61 ALLAN D. NP24,27461 2225 1451 24 BO65 BORMAN M. EANDC-57,17,65 2225 1451 25 CR62 CROSS W. AND PAI H. EANDC(CAN)-16,2,62 2225 1451 26 CH71 GHORAI S. JNE 25,319,1971 2225 1451 27 KO64 KOEHLER D.AND ALFORD W.JNE18,81,64 2225 1451 28 LE69 LEVKOVSKII V. YF 10,44,69 2225 1451 29 LI65 LISKIEN H.AND PAULSEN A. NP63,393,65 2225 1451 30 LU71 LUKIC Y.AND CARROLL E. NSE 43,233,71 2225 1451 31 PA66 PAI H. CJP 44 2337,66 2225 1451 32 PO59 POULARIKAS A. FINK R. PR115,989,59 2225 1451 33 SM75 SMITH D.L.AND MEADOWS J. ANL/NDM10,75 2225 1451 34 1 451 37 02225 1451 35 3 103 11 02225 1451 36 33 103 7 02225 1451 37 2225 1 0 38 2225 0 0 39 2.204600+4 4.555780+1 0 0 0 02225 3103 40 -1.584900+6-1.584900+6 0 0 1 242225 3103 41 24 2 0 0 0 02225 3103 42 1.619400+6 0.000000+0 2.400000+6 4.000000-7 2.750000+6 1.200000-52225 3103 43 3.000000+6 1.000000-3 3.250000+6 3.300000-3 3.500000+6 8.000000-32225 3103 44 4.000000+6 2.600000-2 4.500000+6 4.800000-2 5.000000+6 7.300000-22225 3103 45 5.500000+6 9.900000-2 6.000000+6 1.240000-1 6.500000+6 1.500000-12225 3103 46 7.000000+6 1.730000-1 8.000000+6 2.080000-1 9.000000+6 2.320000-12225 3103 47 1.000000+7 2.520000-1 1.100000+7 2.640000-1 1.200000+7 2.700000-12225 3103 48 1.300000+7 2.680000-1 1.400000+7 2.600000-1 1.500000+7 2.450000-12225 3103 49 1.700000+7 2.100000-1 1.900000+7 1.720000-1 2.000000+7 1.520000-12225 3103 50 2225 3 0 51 2225 0 0 52 2.204600+4 4.555780+1 0 0 0 1222533103 53 0.000000+0 0.000000+0 0 103 0 2222533103 54 0.000000+0 0.000000+0 0 1 6 3222533103 55 1.000000-5 0.000000+0 1.619400+6 1.000000-2 2.000000+7 0.000000+0222533103 56 0.000000+0 0.000000+0 0 1 8 4222533103 57 1.000000-5 0.000000+0 1.619400+6 6.400000-3 1.000000+7 1.000000-2222533103 58 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222533103 59 222533 0 60 2225 0 0 61 0 0 0 62 2.204700+4 4.654800+1 -1 0 0 02228 1451 1 0.000000+0 0.000000+0 0 0 0 62228 1451 2 1.000000+0 0.000000+0 0 0 10 62228 1451 3 0.000000+0 0.000000+0 0 0 38 52228 1451 4 22-TI- 47 BRC,ANL EVAL-JAN77 C.PHILIS,O.BERSILLON,D.SMITH+ 2228 1451 5 DIST-JAN90 900124 2228 1451 6 ----ENDF/B-VI MATERIAL 2228 2228 1451 7 -----INCIDENT NEUTRON DATA 2228 1451 8 ------ENDF-6 FORMAT 2228 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2228 1451 10 ACTIVATION I 2228 1451 11 ******************************************************************2228 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2228 1451 13 * * * * * * *2228 1451 14 ** 2228 1451 15 DOCUMENTATION ANL/NDM-27 (N,P) ANL/NDM-28(N,NP) 2228 1451 16 ** 2228 1451 17 COMMENTS- (N,P) EVAL IN ENERGY RANGES 1.10E+06 TO 1.0E+07 AND 2228 1451 18 1.35E+07 TO 2.0E+07 BASED ON EXPERIMENTAL DATA.INTERPOLATION AND2228 1451 19 EXTRAPOLATION TO OTHER ENERGIES BASED ON THEORETICAL CALCULATION2228 1451 20 PERFORMED AT BRUYERES LE CHATEL USING CODE DEVELOPED BY JARRE. 2228 1451 21 PSEUDO-THRESHOLD=0.5 MEV PER P.C. MACFARLANE TO MAGURNO 6/20/83 2228 1451 22 ** 2228 1451 23 (N,NP) AND (N,D) CROSS SECTIONS EVAL BY C.Y.FU ORNL 2228 1451 24 (N,D)CROSS SECTIONS WERE TAKEN TO HAVE A SHAPE SIMILAR TO THAT 2228 1451 25 OF (N,NP),NORMALIZED TO 8+-3 MB AT 14.8 MEV BASED ON THE 2228 1451 26 MEASUREMENT OF HAIGHT AND GRIMES (UCRL-80235) FOR TI-46(9+-4MB) 2228 1451 27 AND TI-48(7+-3 MB).(N,NP)AND (N,D) ADDED FOR DOSIMETRY PURPOSES.2228 1451 28 REFERENCES 2228 1451 29 AL61 ALLAN D. NP24,274,61 2228 1451 30 AR78 ARTHUR E. PC 1978 2228 1451 31 AR75 ARMITAGE P.C. NNDC 2228 1451 32 CR62 CROSS W.AND PAI H. EANDC(CAN)-16,2,62 2228 1451 33 FU79 C.Y.FU PRIVATE COMM 1979 2228 1451 34 GH71 GHORAI S.AND CARROLL E. NSE 43,233,71 2228 1451 35 GO62 GONZALES ET.AL. PR126,271,62 2228 1451 36 HI HILLMAN M. NP37,78,62 2228 1451 37 LE69 LEVKOVSKII V. Y.F.10,44,69 2228 1451 38 PA66 PAI H.CJP 44 2337,66 2228 1451 39 PO59 POULARIKIS A. AND FINK R. PR115,989,59 2228 1451 40 SM75 SMITH D.L.AND MEADOWS J. ANL/NDM10,75 2228 1451 41 TI68 TIKKU ET.AL. SYMP ON NUCL CROSS SECT AND TECH WASH.1968 2228 1451 42 1 451 47 02228 1451 43 3 28 8 02228 1451 44 3 103 15 02228 1451 45 33 28 4 02228 1451 46 33 103 7 02228 1451 47 2228 1 0 48 2228 0 0 49 2.204700+4 4.654800+1 0 0 0 02228 3 28 50 -1.046000+7-1.046000+7 0 0 2 152228 3 28 51 2 2 15 4 0 02228 3 28 52 1.068000+7 0.000000+0 1.100000+7 1.500000-3 1.160000+7 2.800000-32228 3 28 53 1.200000+7 4.380000-3 1.220000+7 5.500000-3 1.260000+7 9.200000-32228 3 28 54 1.320000+7 2.020000-2 1.400000+7 4.720000-2 1.460000+7 7.300000-22228 3 28 55 1.520000+7 9.800000-2 1.600000+7 1.230000-1 1.700000+7 1.480000-12228 3 28 56 1.800000+7 1.580000-1 1.900000+7 1.540000-1 2.000000+7 1.410000-12228 3 28 57 2228 3 0 58 2.204700+4 4.654800+1 0 0 0 02228 3103 59 3.187100+5 3.187100+5 0 0 1 342228 3103 60 34 2 0 0 0 02228 3103 61 1.000000-5 0.000000+0 5.000000+5 0.000000+0 9.000000+5 3.600000-92228 3103 62 1.000000+6 1.900000-7 1.150000+6 1.250000-3 1.225000+6 2.800000-32228 3103 63 1.300000+6 3.800000-3 1.425000+6 3.100000-3 1.440000+6 3.300000-32228 3103 64 1.500000+6 3.900000-3 1.600000+6 4.500000-3 2.250000+6 2.300000-22228 3103 65 2.350000+6 3.050000-2 2.450000+6 3.170000-2 2.600000+6 3.030000-22228 3103 66 2.750000+6 3.060000-2 3.250000+6 5.000000-2 3.750000+6 6.400000-22228 3103 67 4.250000+6 7.400000-2 4.750000+6 8.000000-2 5.000000+6 8.000000-22228 3103 68 6.000000+6 1.000000-1 6.500000+6 1.060000-1 7.000000+6 1.040000-12228 3103 69 8.000000+6 1.190000-1 9.000000+6 1.290000-1 1.000000+7 1.370000-12228 3103 70 1.100000+7 1.400000-1 1.200000+7 1.360000-1 1.300000+7 1.300000-12228 3103 71 1.400000+7 1.200000-1 1.600000+7 9.800000-2 1.800000+7 7.850000-22228 3103 72 2.000000+7 7.000000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02228 3103 73 2228 3 0 74 2228 0 0 75 2.204700+4 4.654800+1 0 0 0 1222833 28 76 0.000000+0 0.000000+0 0 28 0 1222833 28 77 0.000000+0 0.000000+0 0 1 6 3222833 28 78 1.000000-5 0.000000+0 1.068000+7 9.000000-2 2.000000+7 0.000000+0222833 28 79 222833 0 80 2.204700+4 4.654800+1 0 0 0 1222833103 81 0.000000+0 0.000000+0 0 103 0 2222833103 82 0.000000+0 0.000000+0 0 1 6 3222833103 83 1.000000-5 0.000000+0 8.300000+5 6.400000-3 2.000000+7 0.000000+0222833103 84 0.000000+0 0.000000+0 0 1 8 4222833103 85 1.000000-5 0.000000+0 8.300000+5 6.400000-3 1.000000+7 1.000000-2222833103 86 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0222833103 87 222833 0 88 2228 0 0 89 0 0 0 90 2.204800+4 4.753600+1 -1 0 0 02231 1451 1 0.000000+0 0.000000+0 0 0 0 62231 1451 2 1.000000+0 0.000000+0 0 0 10 62231 1451 3 0.000000+0 0.000000+0 0 0 39 62231 1451 4 22-TI- 48 BRC,ANL+ EVAL-JAN77 C.PHILIS,O.BERSILLON,D.SMITH+ 2231 1451 5 DIST-JAN90 900124 2231 1451 6 ----ENDF/B-VI MATERIAL 2231 2231 1451 7 -----INCIDENT NEUTRON DATA 2231 1451 8 ------ENDF-6 FORMAT 2231 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2231 1451 10 ACTIVATION I 2231 1451 11 ******************************************************************2231 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2231 1451 13 * * * * * * *2231 1451 14 ** 2231 1451 15 DOCUMENTATION ANL/NDM-27 (N,P) ANL/NDM-28 (N,NP) 2231 1451 16 ** 2231 1451 17 (N,P) EVAL IN ENERGY RANGES 4.70E+06 TO 1.0E+07 AND 2231 1451 18 1.25E+07 TO 2.0E+07 BASED ON EXPERIMENTAL DATA. INTERPOLATION 2231 1451 19 AND EXTRAPOLATION TO OTHER ENERGIES BASED ON THEORETICAL CALCS 2231 1451 20 PERFORMED AT BRUYERES LE CHATEL USING CODE DEVELOPED BY J.JARRE 2231 1451 21 ** 2231 1451 22 (N,NP) AND (N,D) CROSS SECTIONS EVAL BY C.Y.FU ORNL 2231 1451 23 (N,D) CROSS SECTIONS WERE BASED ON THE MEASUREMENT OF HAIGHT 2231 1451 24 AND GRIMES(UCRL-80235) AT 14.8 MEV. THE SHAPE OF THE CROSS- 2231 1451 25 SECTION CURVE WAS ASSUMED TO BE THAT OF (N,NP).(N,D) AND (N,NP) 2231 1451 26 ADDED TOGETHER FOR DOSIMETRY PURPOSES. 2231 1451 27 REFERENCES 2231 1451 28 AL61 ALLAN D. NP24,274,61 2231 1451 29 BO65 BORMANN M.ET.AL.EANDC(E)57,17,65 2231 1451 30 CR62 CROSS W.AND PAI H. EANDC(CAN)-16 1962 2231 1451 31 FU79 C.Y.FU PRIVATE COMM 1979 2231 1451 32 GA62 GABBARD F.AND KERN B. PR128,1276,62 2231 1451 33 GH71 GHORAI S.ET.AL.JNE25,319,71 2231 1451 34 HI62 HILLMAN M. NP37,78,62 2231 1451 35 LE69 LEVKOVSKII YF10,44,69 2231 1451 36 LU71 LUKIC Y.AND CARROLL E. NSE43,233,71 2231 1451 37 MA75 MANNHART W.AND VONACH H. ZP,A272,279,75 2231 1451 38 PA66 PAI H. CJP44,2337,66 2231 1451 39 PO59 POULARIKAS A.AND FINK R. PR115,989,59 2231 1451 40 SM75 SMITH D.L.AND MEADOWS J. ANL/NDM-10,75 2231 1451 41 TI68 TIKKU L.ET.AL. SYMP.ON NUC CROSS SEC TECH WASH.1968 2231 1451 42 VO68 VONACH H.ET.AL. SYMP ON NUC CROSS SEC TECH WASH.1968 2231 1451 43 1 451 49 02231 1451 44 3 28 8 02231 1451 45 3 103 12 02231 1451 46 3 107 8 02231 1451 47 33 28 4 02231 1451 48 33 103 7 02231 1451 49 2231 1 0 50 2231 0 0 51 2.204800+4 4.753600+1 0 0 0 02231 3 28 52 -1.144600+7-1.144600+7 0 0 2 132231 3 28 53 2 2 13 4 0 02231 3 28 54 1.168600+7 0.000000+0 1.300000+7 3.000000-3 1.350000+7 4.000000-32231 3 28 55 1.360000+7 4.400000-3 1.400000+7 6.000000-3 1.460000+7 1.030000-22231 3 28 56 1.510000+7 1.500000-2 1.600000+7 2.480000-2 1.660000+7 3.200000-22231 3 28 57 1.760000+7 4.420000-2 1.800000+7 4.970000-2 1.860000+7 4.900000-22231 3 28 58 2.000000+7 4.690000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02231 3 28 59 2231 3 0 60 2.204800+4 4.753600+1 0 0 0 02231 3103 61 -3.208000+6-3.208000+6 0 0 1 262231 3103 62 26 2 0 0 0 02231 3103 63 3.275000+6 0.000000+0 4.000000+6 8.000000-8 4.200000+6 5.300000-72231 3103 64 4.400000+6 1.600000-5 4.700000+6 2.400000-5 4.900000+6 7.300000-52231 3103 65 5.100000+6 1.000000-4 5.400000+6 4.500000-4 5.700000+6 5.800000-42231 3103 66 6.000000+6 1.900000-3 6.500000+6 3.900000-3 7.000000+6 6.600000-32231 3103 67 7.500000+6 9.800000-3 8.000000+6 1.310000-2 9.000000+6 2.040000-22231 3103 68 1.000000+7 3.000000-2 1.100000+7 4.140000-2 1.200000+7 5.300000-22231 3103 69 1.300000+7 6.100000-2 1.350000+7 6.400000-2 1.400000+7 6.400000-22231 3103 70 1.500000+7 6.200000-2 1.600000+7 5.700000-2 1.800000+7 4.600000-22231 3103 71 1.900000+7 4.100000-2 2.000000+7 3.800000-2 0.000000+0 0.000000+02231 3103 72 2231 3 0 73 2.204800+4 4.753600+1 0 0 0 02231 3107 74 -2.032600+6-2.032600+6 0 0 1 142231 3107 75 14 2 0 0 0 02231 3107 76 2.075000+6 0.000000+0 4.000000+6 3.000000-7 6.000000+6 5.000000-52231 3107 77 8.000000+6 1.700000-3 9.000000+6 2.500000-3 1.000000+7 3.800000-32231 3107 78 1.100000+7 5.800000-3 1.200000+7 8.600000-3 1.300000+7 1.300000-22231 3107 79 1.400000+7 1.850000-2 1.500000+7 2.650000-2 1.600000+7 3.650000-22231 3107 80 1.800000+7 5.370000-2 2.000000+7 6.780000-2 0.000000+0 0.000000+02231 3107 81 2231 3 0 82 2231 0 0 83 2.204800+4 4.753600+1 0 0 0 1223133 28 84 0.000000+0 0.000000+0 0 28 0 1223133 28 85 0.000000+0 0.000000+0 0 1 6 3223133 28 86 1.000000-5 0.000000+0 1.168600+7 9.000000-2 2.000000+7 0.000000+0223133 28 87 223133 0 88 2.204800+4 4.753600+1 0 0 0 1223133103 89 0.000000+0 0.000000+0 0 103 0 2223133103 90 0.000000+0 0.000000+0 0 1 6 3223133103 91 1.000000-5 0.000000+0 3.275000+6 6.400000-3 2.000000+7 0.000000+0223133103 92 0.000000+0 0.000000+0 0 1 8 4223133103 93 1.000000-5 0.000000+0 3.275000+6 6.400000-3 1.000000+7 1.000000-2223133103 94 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0223133103 95 223133 0 96 2231 0 0 97 0 0 0 98 2.205000+4 4.957000+1 -1 0 0 02237 1451 1 0.000000+0 0.000000+0 0 0 0 62237 1451 2 1.000000+0 0.000000+0 0 0 10 62237 1451 3 0.000000+0 0.000000+0 0 0 12 22237 1451 4 22-TI- 50 LANL EVAL-MAY79 E.ARTHUR 2237 1451 5 DIST-JAN90 900124 2237 1451 6 ----ENDF/B-VI MATERIAL 2237 2237 1451 7 -----INCIDENT NEUTRON DATA 2237 1451 8 ------ENDF-6 FORMAT 2237 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2237 1451 10 ACTIVATION I 2237 1451 11 ******************************************************************2237 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2237 1451 13 * * * * * * *2237 1451 14 MF=3,MT=107 CROSS SECTIONS BASED ON STATISTICAL MODEL CALCULATIONS2237 1451 15 MF=8,MT=107 DECAY DATA BASED ON ENDF/B-V DATA FOR CA-47 2237 1451 16 1 451 18 02237 1451 17 3 107 8 02237 1451 18 2237 1 0 19 2237 0 0 20 2.205000+4 4.957000+1 0 0 0 02237 3107 21 -3.444000+6-3.444000+6 0 0 1 142237 3107 22 14 2 0 0 0 02237 3107 23 3.513480+6 0.000000+0 3.520000+6 0.000000+0 5.000000+6 3.000000-82237 3107 24 8.000000+6 7.600000-5 9.000000+6 1.800000-4 1.000000+7 4.300000-42237 3107 25 1.100000+7 9.200000-4 1.200000+7 1.800000-3 1.300000+7 3.600000-32237 3107 26 1.400000+7 6.800000-3 1.500000+7 1.200000-2 1.600000+7 1.900000-22237 3107 27 1.800000+7 3.950000-2 2.000000+7 5.600000-2 0.000000+0 0.000000+02237 3107 28 2237 3 0 29 2237 0 0 30 0 0 0 31 2.405000+4 4.951700+1 1 0 0 12425 1451 1 0.000000+0 0.000000+0 0 0 0 62425 1451 2 1.000000+0 0.000000+0 0 0 10 62425 1451 3 0.000000+0 0.000000+0 0 0 168 72425 1451 4 24-CR- 50 ORNL EVAL-NOV89 HETRICK,D.C. & N.M. LARSON,FU 2425 1451 5 ORNL/TM DIST-APR90 900305 2425 1451 6 ----ENDF/B-VI MATERIAL 2425 2425 1451 7 -----INCIDENT NEUTRON DATA 2425 1451 8 ------ENDF-6 FORMAT 2425 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2425 1451 10 ACTIVATION I 2425 1451 11 ******************************************************************2425 1451 12 THIS WORK EMPLOYED THE HAUSER-FESHBACH CODE TNG (1,2,3). 2425 1451 13 THE TNG CODE PROVIDES ENERGY AND ANGULAR DISTRIBUTIONS OF 2425 1451 14 PARTICLES EMITTED IN THE COMPOUND AND PRE-COMPOUND REACTIONS, 2425 1451 15 ENSURES CONSISTENCY AMONG ALL REACTIONS, AND MAINTAINS ENERGY 2425 1451 16 BALANCE. DETAILS PERTINENT TO THE CONTENTS OF THIS EVALUATION 2425 1451 17 WILL BE PUBLISHED AT A LATER DATE. 2425 1451 18 2425 1451 19 ----- DESCRIPTION OF FILES 2425 1451 20 (MF-MT) 2425 1451 21 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2425 1451 22 2-151 RESONANCE PARAMETERS; USED TO PROVIDE THE TOTAL, 2425 1451 23 SCATTERING, AND CAPTURE CROSS SECTIONS FROM 1.E-5 EV TO 2425 1451 24 792 KEV. A SMALL CONTRIBUTION IN FILE 3-102 IS ADDED FOR 2425 1451 25 CAPTURE FROM 325 TO 792 KEV (SEE 3-102 BELOW). THE 2425 1451 26 RESONANCE PARAMETERS ARE TAKEN FROM REF. (4) 2425 1451 27 WITH HELP FROM BRUSEGAN ET AL. (PRIVATE COMM., 1988), AND 2425 1451 28 ARE ADJUSTED TO GIVE CORRECT THERMAL VALUES. THE 2425 1451 29 PARAMETERS WERE ALSO ADJUSTED TO THE DATA OF REF. (8), 2425 1451 30 AND A BACKGROUND FILE IS GIVEN IN 3/1 FROM 30 TO 792 KEV. 2425 1451 31 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2425 1451 32 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2425 1451 33 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2425 1451 34 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2425 1451 35 3-1 TOTAL CROSS SECTION; GIVEN BY RESONANCE PARAMETERS UP TO 2425 1451 36 792 KEV WITH NEGATIVE ENERGY RESONANCES ADJUSTED TO GIVE 2425 1451 37 MEASURED THERMAL SCATTERING AND CAPTURE CROSS SECTIONS 2425 1451 38 (SEE DESCRIPTION FOR 3-102 BELOW). ABOVE 792 KEV, 2425 1451 39 ISOTOPIC DATA USED TO 4.0 MEV (REF. (8)) AND FROM 4.-20.0 2425 1451 40 MEV HIGH RESOLUTION NAT CR TRANSMISSION MEASUREMENTS WERE 2425 1451 41 USED (D.C. LARSON, J.A. HARVEY, AND N.W. HILL, PRIVATE 2425 1451 42 COMM., 1988; DATA AVAILABLE AT NNDC). 2425 1451 43 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2425 1451 44 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2425 1451 45 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2425 1451 46 3-28, 3-102, 3-103, 3-104, AND 3-107. 2425 1451 47 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, ... 2425 1451 48 ...,3-56, AND 3-91 2425 1451 49 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE MEASUREMENTS OF 2425 1451 50 GHORAI ET AL. (5) AND IKEDA ET AL. (6). 2425 1451 51 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE 2425 1451 52 (1,2,3); NO DATA AVAILABLE OTHER THAN A EMISSION. 2425 1451 53 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2425 1451 54 CODE (1,2,3). LITTLE DATA AVAILABLE; 3/28 ADDED TO 3/103 2425 1451 55 AGREES WELL WITH SPARSE P-EMISSION DATA. 2425 1451 56 3-51 TO 3-56 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2425 1451 57 FROM TNG (1,2,3). 2425 1451 58 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2425 1451 59 CALCULATED). 2425 1451 60 3-102 (N,G) CAPTURE CROSS SECTION; GIVEN BY RESONANCE PARAMETERS2425 1451 61 UP TO 792 KEV AND FROM 792 KEV TO 20 MEV, TNG CALCULATIONS2425 1451 62 WERE USED BUT NORMALIZED TO MEASURED AVE. CAPTURE BETWEEN 2425 1451 63 100 KEV AND 792 KEV. A SMALL CONTRIBUTION TO BE ADDED 2425 1451 64 TO 2-151 IS GIVEN FROM 325 TO 792 KEV DUE TO INCOMPLETE 2425 1451 65 EXPERIMENTAL CAPTURE RESONANCE INFORMATION. TNG 2425 1451 66 CALCULATIONS INCLUDED A PRECOMPOUND COMPONENT AND WEIGHTED2425 1451 67 CROSS SECTIONS FROM ALL ISOTOPES OF CR GIVE 0.82 MB AT 2425 1451 68 14.5 MEV, IN AGREEMENT WITH THE MEASUREMENT OF 0.75 MB 2425 1451 69 FOR NAT CR. 2425 1451 70 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2425 1451 71 CODE (1,2,3). LITTLE DATA AVAILABLE; SEE 3/28 ABOVE. 2425 1451 72 3-104 (N,D) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED 2425 1451 73 NORMALIZED TO AVAILABLE DATA (7). 2425 1451 74 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2425 1451 75 TNG CODE (1,2,3). 3/22 ADDED TO 3/107 AGREES WELL WITH 2425 1451 76 SPARSE A-EMISSION DATA. 2425 1451 77 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2425 1451 78 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2425 1451 79 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2425 1451 80 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2425 1451 81 PARAMETERS IN 2/151. 2425 1451 82 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2425 1451 83 NEUTRON AND 49CR RESIDUAL, AND ENERGY DEPENDENT YIELD 2425 1451 84 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2425 1451 85 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2425 1451 86 EACH PRODUCT. ISOTROPY IS ASSUMED. 2425 1451 87 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2425 1451 88 NEUTRON, ALPHA, AND 46TI RESIDUAL, AND ENERGY DEPENDENT 2425 1451 89 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2425 1451 90 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2425 1451 91 FOR EACH PRODUCT. ISOTROPY IS ASSUMED. 2425 1451 92 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2425 1451 93 NEUTRON AND 49V RESIDUAL, AND ENERGY DEPENDENT YIELD 2425 1451 94 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2425 1451 95 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2425 1451 96 EACH PRODUCT. ISOTROPY IS ASSUMED. (N,XP) D-D EMISSION 2425 1451 97 DATA USED TO BENCHMARK THE CALCULATION. 2425 1451 98 6-51 THROUGH 6-56 INELASTIC SCATTERING EXCITING LEVELS; 2425 1451 99 ASSUMED ISOTROPIC. 2425 1451 100 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2425 1451 101 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 50CR 2425 1451 102 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2425 1451 103 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2425 1451 104 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2425 1451 105 FOR EACH. ISOTROPY IS ASSUMED. 2425 1451 106 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2425 1451 107 AND 50V RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2425 1451 108 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2425 1451 109 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2425 1451 110 PRODUCT. ISOTROPY IS ASSUMED. (N,XP) D-D EMISSION DATA 2425 1451 111 USED TO BENCHMARK THE CALCULATION. 2425 1451 112 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2425 1451 113 AND 47TI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2425 1451 114 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2425 1451 115 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2425 1451 116 PRODUCT. ISOTROPY IS ASSUMED. (N,XA) D-D EMISSION DATA 2425 1451 117 USED TO BENCHMARK THE CALCULATION. 2425 1451 118 12-51 THROUGH 12-56 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2425 1451 119 12-102 (N,G) CAPTURE; TNG CALCULATED. 2425 1451 120 14-51 THROUGH 14-56 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2425 1451 121 ASSUMED TO BE ISOTROPIC. 2425 1451 122 15-102 (N,G) CAPTURE; TNG CALCULATED. 2425 1451 123 2425 1451 124 -------------------------------------------------------------- 2425 1451 125 UNCERTAINTY FILES 2425 1451 126 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2425 1451 127 REQUIRED BY ENDF/B-VI. 2425 1451 128 2425 1451 129 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2425 1451 130 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2425 1451 131 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2425 1451 132 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2425 1451 133 20 MEV THE FILES ARE DERIVED. 2425 1451 134 33-3 FROM 1.E-5 TO 792 KEV UNCERTAINTIES ARE DERIVED. FROM 7922425 1451 135 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82425 1451 136 33-4 UNCERTAINTIES ARE ALL DERIVED. 2425 1451 137 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG 2425 1451 138 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2425 1451 139 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2425 1451 140 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2425 1451 141 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2425 1451 142 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2425 1451 143 ENERGIES, AND CALCULATED RESULTS ABOVE 792 KEV. 2425 1451 144 33-104 UNCERTAINTIES ESTIMATED, BASED ON DATA. 2425 1451 145 33-103 UNCERTAINTIES ESTIMATED FROM TNG. 2425 1451 146 33-107 UNCERTAINTIES ESTIMATED FROM TNG. 2425 1451 147 2425 1451 148 REFERENCES: 2425 1451 149 (1) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2425 1451 150 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2425 1451 151 MOMENTUM," ORNL/TM-7042 (1980) AND NSE 100, 61 (1988). 2425 1451 152 (2) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2425 1451 153 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2425 1451 154 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2425 1451 155 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2425 1451 156 NATIONAL LAB. 2425 1451 157 (3) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2425 1451 158 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2425 1451 159 (4) A. BRUSEGAN, R. BUYL, F.CORVI, L. MEWISSEN, F.POORTMANS, 2425 1451 160 G. ROHR, R. SHELLEY, T. VAN DER VEEN, I. VAN MARCKE, "HIGH 2425 1451 161 RESOLUTION NEUTRON CAPTURE AND TOTAL CROSS SECTION 2425 1451 162 MEASUREMENTS OF 50CR, 52CR, AND 53CR," PROC. OF INT. CONF AT 2425 1451 163 SANTA FE, NM, PP. 633-640 (MAY 13-17, 1985). 2425 1451 164 (5) S.K. GHORAI, J.R. WILLIAMS, AND W.L. ALFORD, J. PHYS. G:. 2425 1451 165 NUCL. PHYS. 13, 405-410 (1987). 2425 1451 166 (6) Y. IKEDA, C. KONNO, K. OISHI, T. NAKAMURA, H. MIYADE, K. 2425 1451 167 KAWADE, H. YAMAMOTO, AND T. KATOH, JAERI 1312 (1988). 2425 1451 168 (7) S.M. GRIMES, R.C. HAIGHT, K.R. ALVAR, H.H. BARSCHALL, AND 2425 1451 169 R.R. BORCHERS, PHYS. REV., C19, 2127 (JUNE 1979). 2425 1451 170 (8) J.A. HARVEY AND H.M. AGRAWAL, PRIVATE COMMUNICATION (1988). 2425 1451 171 2425 1451 172 1 451 179 12425 1451 173 2 151 393 12425 1451 174 3 16 7 12425 1451 175 3 28 6 12425 1451 176 3 102 10 12425 1451 177 3 103 14 12425 1451 178 3 104 6 12425 1451 179 2425 1 0 180 2425 0 0 181 2.405000+4 4.951700+1 0 0 1 02425 2151 182 2.405000+4 1.000000+0 0 0 1 02425 2151 183 1.000000-5 7.920000+5 1 3 0 12425 2151 184 0.000000+0 5.375600-1 1 0 3 32425 2151 185 4.951700+1 5.375600-1 0 0 390 652425 2151 186 -5.092800+2 5.000000-1 7.416800+0 1.160500+0 0.000000+0 0.000000+02425 2151 187 5.504300+3 5.000000-1 1.625300+3 3.108800+0 0.000000+0 0.000000+02425 2151 188 2.843400+4 5.000000-1 4.758400+2 5.900000-1 0.000000+0 0.000000+02425 2151 189 3.726000+4 5.000000-1 2.346200+3 1.870000+0 0.000000+0 0.000000+02425 2151 190 5.507200+4 5.000000-1 2.646600+2 7.800000-1 0.000000+0 0.000000+02425 2151 191 6.452700+4 5.000000-1 4.278200+1 6.800000-1 0.000000+0 0.000000+02425 2151 192 9.489500+4 5.000000-1 1.305200+3 9.700000-1 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0.000000+0 0.000000+02425 3 28 590 2425 3 0 591 2.405000+4 4.951700+1 0 0 0 02425 3102 592 9.261700+6 9.261700+6 0 0 1 192425 3102 593 19 2 0 0 0 02425 3102 594 1.000000-5 0.000000+0 3.250000+5 0.000000+0 3.250000+5 4.600000-32425 3102 595 7.920000+5 2.600000-3 7.920000+5 6.150000-3 8.500000+5 4.820000-32425 3102 596 8.750000+5 4.150000-3 9.000000+5 3.480000-3 1.000000+6 2.928000-32425 3102 597 2.000000+6 2.685000-3 3.000000+6 2.850000-3 4.000000+6 2.244000-32425 3102 598 5.000000+6 1.644000-3 7.500000+6 8.160000-4 1.000000+7 1.600000-32425 3102 599 1.200000+7 1.320000-3 1.450000+7 1.020000-3 1.750000+7 5.660000-42425 3102 600 2.000000+7 2.600000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+02425 3102 601 2425 3 0 602 2.405000+4 4.951700+1 0 0 0 02425 3103 603 -2.563000+5-2.563000+5 0 0 2 312425 3103 604 2 1 31 2 0 02425 3103 605 2.614800+5 0.000000+0 1.000000+6 3.717400-8 1.250000+6 2.449900-62425 3103 606 1.500000+6 2.748100-5 1.750000+6 2.401500-4 2.000000+6 1.199300-32425 3103 607 2.250000+6 4.246400-3 2.500000+6 1.164600-2 2.750000+6 2.657400-22425 3103 608 3.000000+6 5.025100-2 3.500000+6 1.143000-1 4.000000+6 1.901800-12425 3103 609 4.500000+6 2.635900-1 5.000000+6 3.250400-1 5.500000+6 3.723600-12425 3103 610 6.000000+6 4.078900-1 6.500000+6 4.346100-1 7.000000+6 4.518700-12425 3103 611 7.500000+6 4.613800-1 8.000000+6 4.668900-1 8.500000+6 4.686800-12425 3103 612 9.000000+6 4.679300-1 9.500000+6 4.672000-1 1.000000+7 4.666700-12425 3103 613 1.100000+7 4.666000-1 1.200000+7 4.607400-1 1.300000+7 4.244400-12425 3103 614 1.450000+7 3.025100-1 1.600000+7 1.839700-1 1.750000+7 1.125000-12425 3103 615 2.000000+7 6.112400-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02425 3103 616 2425 3 0 617 2.405000+4 4.951700+1 0 0 0 02425 3104 618 -7.364000+6-7.364000+6 0 0 1 82425 3104 619 8 2 0 0 0 02425 3104 620 7.512700+6 0.000000+0 9.000000+6 6.000000-4 1.000000+7 1.000000-32425 3104 621 1.100000+7 3.000000-3 1.200000+7 6.000000-3 1.300000+7 9.000000-32425 3104 622 1.480000+7 1.200000-2 2.000000+7 1.100000-2 0.000000+0 0.000000+02425 3104 623 2425 3 0 624 2425 0 0 625 0 0 0 626 2.405200+4 5.149400+1 -1 0 0 12431 1451 1 0.000000+0 0.000000+0 0 0 0 62431 1451 2 1.000000+0 0.000000+0 0 0 10 62431 1451 3 0.000000+0 0.000000+0 0 0 195 42431 1451 4 24-CR- 52 ORNL EVAL-NOV89 HETRICK, D.C. & N.M. LARSON,FU 2431 1451 5 ORNL/TM10417,ENDF-346 DIST-APR90 900305 2431 1451 6 ----ENDF/B-VI MATERIAL 2431 2431 1451 7 -----INCIDENT NEUTRON DATA 2431 1451 8 ------ENDF-6 FORMAT 2431 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2431 1451 10 ACTIVATION I 2431 1451 11 ******************************************************************2431 1451 12 THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE 2431 1451 13 DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1) 2431 1451 14 AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES 2431 1451 15 ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE 2431 1451 16 COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL2431 1451 17 REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE 2431 1451 18 CONTENTS OF THIS EVALUATION AND EXTENSIVE COMPARISONS OF 2431 1451 19 CALCULATIONS WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5).2431 1451 20 2431 1451 21 ----- DESCRIPTION OF FILES 2431 1451 22 (MF-MT) 2431 1451 23 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2431 1451 24 2-151 RESONANCE PARAMETERS; USED TO PROVIDE THE TOTAL AND 2431 1451 25 SCATTERING CROSS SECTIONS FROM 1.E-5 EV TO 980 KEV, AND 2431 1451 26 CAPTURE FROM 1.E-5 TO 375 KEV. A SMALL CONTRIBUTION IN 2431 1451 27 3-102 IS ADDED TO 2-151 FOR CAPTURE FROM 375 TO 980 KEV 2431 1451 28 (SEE 3-102 BELOW). THE RESONANCE PARAMETERS 2431 1451 29 FROM REF.(6) (WITH HELP FROM BRUSEGAN ET AL. (PRIVATE 2431 1451 30 COMM., 1988)) WERE ADJUSTED TO MINIMIZE DIFFERENCE WITH 2431 1451 31 DATA OF REF. (12). 2431 1451 32 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2431 1451 33 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2431 1451 34 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2431 1451 35 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2431 1451 36 3-1 TOTAL CROSS SECTION; GIVEN BY RESONANCE PARAMETERS UP TO 2431 1451 37 980 KEV WITH NEGATIVE ENERGY RESONANCES ADJUSTED TO GIVE 2431 1451 38 MEASURED THERMAL SCATTERING AND CAPTURE CROSS SECTIONS 2431 1451 39 (SEE 3-102 BELOW). FROM 20 - 980 KEV A BACKGROUND FILE 2431 1451 40 IS REQUIRED. FROM 980 KEV TO 20.0 MEV, HIGH 2431 1451 41 RESOLUTION NAT CR TRANSMISSION MEASUREMENTS WERE USED 2431 1451 42 D.C. LARSON, J.A. HARVEY, AND N.W. HILL, PRIVATE COMM., 2431 1451 43 1988; DATA AVAILABLE AT NNDC) RATHER THAN LOWER 2431 1451 44 RESOLUTION ISOTOPIC DATA. 2431 1451 45 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2431 1451 46 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2431 1451 47 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2431 1451 48 3-28, 3-102, 3-103, AND 3-107. 2431 1451 49 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2431 1451 50 .., 3-60, AND 3-91 2431 1451 51 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE ACTIVATION 2431 1451 52 FILE FOR 52CR BUT WERE ADJUSTED TO BE SMALLER 2431 1451 53 BELOW ENERGY OF 15.5 MEV TO MATCH THE DATA 2431 1451 54 OF WAGNER ET AL. (7) WHICH AGREES WELL WITH OTHER 2431 1451 55 DATA IN THIS ENERGY REGION. 2431 1451 56 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2431 1451 57 CODE (2,3,4,5). NO DATA AVAILABLE OTHER THAN A-EMISSION. 2431 1451 58 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2431 1451 59 CODE (2,3,4,5). NO DATA AVAILABLE OTHER THAN P-EMISSION. 2431 1451 60 3-51 TO 3-60 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2431 1451 61 FROM TNG (2,3,4,5) WHICH INCLUDES DIRECT INTERACTION 2431 1451 62 CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. COMPARISONS 2431 1451 63 WITH EXPERIMENTAL DATA USED IN THE EVALUATION PROCESS ARE 2431 1451 64 SHOWN IN (5). 2431 1451 65 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2431 1451 66 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA (5). 2431 1451 67 3-102 (N,G) CAPTURE CROSS SECTION; GIVEN BY RESONANCE PARAMETERS2431 1451 68 UP TO 980 KEV AND FROM 980 KEV TO 20 MEV, TNG CALC'S 2431 1451 69 WERE USED BUT NORMALIZED TO MEASURED AVE. CAPTURE BETWEEN 2431 1451 70 100 KEV AND 1.0 MEV. A SMALL CONTIBUTION TO BE ADDED TO 2431 1451 71 2-151 IS GIVEN FROM 375-980 KEV DUE TO INCOMPLETE 2431 1451 72 CAPTURE RESONANCE INFORMATION. TNG CALCULATIONS INCLUDED 2431 1451 73 A PRECOMPOUND COMPONENT AND WEIGHTED CROSS SECTIONS FROM 2431 1451 74 ISOTOPES OF CR GIVE 0.82 MB AT 14.5 MEV, IN AGREEMENT WITH2431 1451 75 THE MEASUREMENT OF 0.75 MB FOR NAT CR. 2431 1451 76 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2431 1451 77 CODE (2,3,4,5), BUT MODIFIED BETWEEN EN OF 7 TO 16 MEV TO 2431 1451 78 BETTER FIT THE DATA OF SMITH ET AL. (8) UP TO 9 MEV AND 2431 1451 79 RECENT MEASUREMENTS AT 14.5 MEV (9-11). (EYE GUIDE). 2431 1451 80 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2431 1451 81 TNG CODE (2,3,4,5). NO DATA AVAILABLE OTHER THAN A- 2431 1451 82 EMISSION. 2431 1451 83 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2431 1451 84 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2431 1451 85 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2431 1451 86 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2431 1451 87 PARAMETERS IN 2/151. 2431 1451 88 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2431 1451 89 NEUTRON AND 51CR RESIDUAL, AND ENERGY DEPENDENT YIELD 2431 1451 90 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2431 1451 91 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2431 1451 92 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2431 1451 93 THE OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY 2431 1451 94 USED TO BENCHMARK THE TNG CALCULATIONS (5). 2431 1451 95 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2431 1451 96 NEUTRON, ALPHA, AND 48TI RESIDUAL, AND ENERGY DEPENDENT 2431 1451 97 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2431 1451 98 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2431 1451 99 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2431 1451 100 FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2431 1451 101 ALPHA AND RESIDUAL). (N,XA) D-D EMISSION DATA HEAVILY 2431 1451 102 USED TO BENCHMARK THE CALCULATIONS (5). 2431 1451 103 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2431 1451 104 NEUTRON AND 51V RESIDUAL, AND ENERGY DEPENDENT YIELD 2431 1451 105 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2431 1451 106 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2431 1451 107 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2431 1451 108 THE OUTGOING NEUTRON). (N,XP) D-D EMISSION DATA HEAVILY 2431 1451 109 USED TO BENCHMARK THE CALCULATIONS (5). 2431 1451 110 6-51 THROUGH 6-60 INELASTIC SCATTERING EXCITING LEVELS; EACH 2431 1451 111 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2431 1451 112 AND 52CR RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2431 1451 113 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2431 1451 114 BY DWUCK (1) AND TNG (2,3,4,5)). COMPARISONS WITH 2431 1451 115 ANGULAR DISTRIBUTION DATA ARE GIVEN IN (5). 2431 1451 116 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2431 1451 117 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 52CR 2431 1451 118 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2431 1451 119 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2431 1451 120 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2431 1451 121 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2431 1451 122 OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY USED 2431 1451 123 TO BENCHMARK THE TNG CALCULATIONS (5). 2431 1451 124 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2431 1451 125 AND 52V RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2431 1451 126 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2431 1451 127 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2431 1451 128 PRODUCT. (N,XP) D-D EMISSION DATA USED TO BENCHMARK 2431 1451 129 THE TNG CALCULATIONS (5). 2431 1451 130 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2431 1451 131 AND 49TI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2431 1451 132 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2431 1451 133 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2431 1451 134 PRODUCT. (N,XA) D-D EMISSION DATA USED TO BENCHMARK 2431 1451 135 THE TNG CALCULATIONS (5). 2431 1451 136 12-51 THROUGH 12-60 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2431 1451 137 BY HETRICK ET AL. (5), ARE GIVEN. 2431 1451 138 12-102 (N,G) CAPTURE; TNG CALCULATED. 2431 1451 139 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2431 1451 140 ASSUMED TO BE ISOTROPIC. 2431 1451 141 15-102 (N,G) CAPTURE; TNG CALCULATED. 2431 1451 142 2431 1451 143 -------------------------------------------------------------- 2431 1451 144 UNCERTAINTY FILES 2431 1451 145 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2431 1451 146 REQUIRED BY ENDF/B-VI. 2431 1451 147 2431 1451 148 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2431 1451 149 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2431 1451 150 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2431 1451 151 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2431 1451 152 20 MEV THE FILES ARE DERIVED. 2431 1451 153 33-3 FROM 1.E-5 TO 980 KEV UNCERTAINTIES ARE DERIVED. FROM 9802431 1451 154 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82431 1451 155 33-4 UNCERTAINTIES ARE ALL DERIVED. 2431 1451 156 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, CSISRS DATA USED 2431 1451 157 AS A GUIDE. 2431 1451 158 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2431 1451 159 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2431 1451 160 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2431 1451 161 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2431 1451 162 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2431 1451 163 ENERGIES, AND CALCULATED RESULTS ABOVE 980 KEV. 2431 1451 164 33-103 UNCERTAINTIES ESTIMATED FROM TNG. 2431 1451 165 33-107 UNCERTAINTIES ESTIMATED FROM TNG. 2431 1451 166 2431 1451 167 REFERENCES: 2431 1451 168 (1) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2431 1451 169 COLORADO, UNPUBLISHED (1972). 2431 1451 170 (2) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2431 1451 171 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2431 1451 172 MOMENTUM," ORNL/TM-7042 (1980) AND NSE 100, 61 (1988). 2431 1451 173 (3) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2431 1451 174 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2431 1451 175 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2431 1451 176 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2431 1451 177 NATIONAL LAB. 2431 1451 178 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2431 1451 179 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2431 1451 180 (5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2431 1451 181 -INDUCED CROSS SECTIONS FOR 52CR FROM 1 TO 20 MEV AND 2431 1451 182 COMPARISONS WITH EXPERIMENT," ORNL/TM-10417,ENDF-346 (1987). 2431 1451 183 (6) A. BRUSEGAN, R. BUYL, F.CORVI, L. MEWISSEN, F.POORTMANS, 2431 1451 184 G. ROHR, R. SHELLEY, T. VAN DER VEEN, I. VAN MARCKE, "HIGH 2431 1451 185 RESOLUTION NEUTRON CAPTURE AND TOTAL CROSS SECTION 2431 1451 186 MEASUREMENTS OF 50CR, 52CR, AND 53CR," PROC. OF INT. CONF AT 2431 1451 187 SANTA FE, NM, PP. 633-640 (MAY 13-17, 1985). 2431 1451 188 (7) M. WAGNER, G. WINKLER, H. LISKIEN, AND R. WIDERA, 2431 1451 189 "MEASUREMENT OF THE EXCITATION FUNCTION FOR THE 52CR(N,2N)51CR2431 1451 190 REACTION FROM 12.7 TO 19.5 MEV," IRK PROGRESS REPORT (1987/ 2431 1451 191 1988). 2431 1451 192 (8) D.L. SMITH AND J.W. MEADOWS, NUCL. SCI. ENG.,76,43-48 (1980).2431 1451 193 (9) GUPTA ET AL., J. OF PHYSICS, INDIA, 24, 637 (1985). 2431 1451 194 (10) ARTEM'EV ET AL., ATOMNAJA ENERGIJA, 49(3), 195 (1980). 2431 1451 195 (11) N.I. MOLLA AND S.M. QAIM, NUCL. PHYS., A283, 269-288 (1977). 2431 1451 196 (12) H.M. AGRAWAL, J.B. GARG, AND J.A. HARVEY, PHYS. REV. C30, 2431 1451 197 1880 (1984). 2431 1451 198 2431 1451 199 1 451 203 12431 1451 200 3 16 7 12431 1451 201 3 103 11 12431 1451 202 33 16 12 12431 1451 203 2431 1 0 204 2431 0 0 205 2.405200+4 5.149400+1 0 0 0 02431 3 16 206 -1.203900+7-1.203900+7 0 0 1 122431 3 16 207 12 2 0 0 0 02431 3 16 208 1.227300+7 0.000000+0 1.275000+7 4.000000-2 1.300000+7 7.900000-22431 3 16 209 1.350000+7 1.650000-1 1.400000+7 2.600000-1 1.450000+7 3.540000-12431 3 16 210 1.509000+7 4.420000-1 1.611000+7 5.374000-1 1.713000+7 5.983000-12431 3 16 211 1.815000+7 6.351000-1 1.917000+7 6.489000-1 2.000000+7 6.441000-12431 3 16 212 2431 3 0 213 2.405200+4 5.149400+1 0 0 0 02431 3103 214 -3.194000+6-3.194000+6 0 0 1 222431 3103 215 22 2 0 0 0 02431 3103 216 3.256000+6 0.000000+0 4.000000+6 2.115000-7 4.500000+6 5.855000-52431 3103 217 5.000000+6 8.937000-4 5.500000+6 4.514000-3 6.000000+6 1.199000-22431 3103 218 6.500000+6 2.297000-2 7.000000+6 3.125000-2 7.500000+6 3.720000-22431 3103 219 8.000000+6 4.250000-2 8.500000+6 4.700000-2 9.000000+6 5.250000-22431 3103 220 9.500000+6 5.850000-2 1.000000+7 6.350000-2 1.100000+7 7.350000-22431 3103 221 1.200000+7 8.250000-2 1.300000+7 8.830000-2 1.400000+7 8.900000-22431 3103 222 1.450000+7 8.700000-2 1.600000+7 7.000000-2 1.750000+7 5.486000-22431 3103 223 2.000000+7 3.787000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02431 3103 224 2431 3 0 225 2431 0 0 226 2.405200+4 5.149400+1 0 0 0 1243133 16 227 0.000000+0 0.000000+0 0 16 0 3243133 16 228 0.000000+0 0.000000+0 0 1 6 3243133 16 229 1.000000-5 0.000000+0 1.275000+7 5.000000-3 2.000000+7 0.000000+0243133 16 230 0.000000+0 0.000000+0 0 1 14 7243133 16 231 1.000000-5 0.000000+0 1.275000+7 1.800000-2 1.350000+7 1.012500-2243133 16 232 1.450000+7 6.480000-3 1.509000+7 4.500000-3 1.713000+7 4.500000-3243133 16 233 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16 234 0.000000+0 0.000000+0 0 8 14 7243133 16 235 1.000000-5 0.000000+0 1.275000+7 3.200000-6 1.350000+7 3.062800-5243133 16 236 1.450000+7 9.022800-5 1.509000+7 9.768200-5 1.713000+7 1.789800-4243133 16 237 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0243133 16 238 243133 0 239 2431 0 0 240 0 0 0 241 2.405400+4 5.347600+1 1 0 0 12437 1451 1 0.000000+0 0.000000+0 0 0 0 62437 1451 2 1.000000+0 0.000000+0 0 0 10 62437 1451 3 0.000000+0 0.000000+0 0 0 133 42437 1451 4 24-CR- 54 ORNL EVAL-NOV89 HETRICK,D.C. & N.M. LARSON,FU 2437 1451 5 ORNL/TM DIST-APR90 900307 2437 1451 6 ----ENDF/B-VI MATERIAL 2437 2437 1451 7 -----INCIDENT NEUTRON DATA 2437 1451 8 ------ENDF-6 FORMAT 2437 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2437 1451 10 ACTIVATION I 2437 1451 11 ******************************************************************2437 1451 12 THIS WORK EMPLOYED THE HAUSER-FESHBACH CODE TNG (1,2,3). 2437 1451 13 THE TNG CODE PROVIDES ENERGY AND ANGULAR DISTRIBUTIONS OF 2437 1451 14 PARTICLES EMITTED IN THE COMPOUND AND PRE-COMPOUND REACTIONS, 2437 1451 15 ENSURES CONSISTENCY AMONG ALL REACTIONS, AND MAINTAINS ENERGY 2437 1451 16 BALANCE. DETAILS PERTINENT TO THE CONTENTS OF THIS EVALUATION 2437 1451 17 WILL BE PUBLISHED AT A LATER DATE. 2437 1451 18 2437 1451 19 ----- DESCRIPTION OF FILES 2437 1451 20 (MF-MT) 2437 1451 21 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2437 1451 22 2-151 RESONANCE PARAMETERS; USED TO PROVIDE THE TOTAL, 2437 1451 23 SCATTERING, AND CAPTURE CROSS SECTIONS FROM 1.E-5 EV TO 2437 1451 24 900 KEV. THE RESONANCE PARAMETERS ARE TAKEN FROM REF'S 2437 1451 25 (4) AND (5), AND READJUSTED TO ATTEMPT TO MATCH THE 2437 1451 26 THERMAL VALUES. A BACKGROUND FILE IN 3/1 IS USED FROM 2437 1451 27 11-900 KEV. 2437 1451 28 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2437 1451 29 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2437 1451 30 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2437 1451 31 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2437 1451 32 3-1 TOTAL CROSS SECTION; GIVEN BY RESONANCE PARAMETERS UP TO 2437 1451 33 900 KEV WITH NEGATIVE ENERGY RESONANCES ADJUSTED TO GIVE 2437 1451 34 MEASURED THERMAL SCATTERING AND CAPTURE CROSS SECTIONS. 2437 1451 35 ABOVE 900 KEV, ISOTOPIC DATA USED TO 4.0 MEV (J.A. HARVEY 2437 1451 36 AND H.M. AGRAWAL, PRIVATE COMM., 1988) AND FROM 4.0-20.0 2437 1451 37 MEV HIGH RESOLUTION NAT CR TRANSMISSION MEASUREMENTS WERE 2437 1451 38 USED (D.C. LARSON, J.A. HARVEY, AND N.W. HILL, PRIVATE 2437 1451 39 COMM., 1988; DATA AVAILABLE AT NNDC). 2437 1451 40 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2437 1451 41 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2437 1451 42 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 2437 1451 43 3-102, 3-103, AND 3-107. 2437 1451 44 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, ... 2437 1451 45 ...,3-54, AND 3-91 2437 1451 46 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2437 1451 47 CODE (1,2,3). NO DATA AVAILABLE. 2437 1451 48 3-51 TO 3-54 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2437 1451 49 FROM TNG (1,2,3). 2437 1451 50 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2437 1451 51 CALCULATED). 2437 1451 52 3-102 (N,G) CAPTURE CROSS SECTION; GIVEN BY RESONANCE PARAMETERS2437 1451 53 UP TO 900 KEV AND FROM 900 KEV TO 20 MEV, TNG CALC'S 2437 1451 54 WERE USED BUT NORMALIZED TO MEASURED AVE. CAPTURE BETWEEN 2437 1451 55 100 KEV AND 900 KEV. TNG CALCULATIONS INCLUDED A PRE- 2437 1451 56 COMPOUND COMPONENT AND WEIGHTED CROSS SECTIONS FROM ALL 2437 1451 57 ISOTOPES OF CR GIVE 0.82 MB AT 14.5 MEV, IN AGREEMENT WITH2437 1451 58 THE MEASUREMENT OF 0.75 MB FOR NAT CR. 2437 1451 59 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2437 1451 60 CODE (1,2,3). CALCULATIONS AGREE WELL WITH DATA. 2437 1451 61 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2437 1451 62 TNG CODE (1,2,3). CALCULATIONS AGREE WELL WITH DATA. 2437 1451 63 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2437 1451 64 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2437 1451 65 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2437 1451 66 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2437 1451 67 PARAMETERS IN 2/151. 2437 1451 68 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2437 1451 69 NEUTRON AND 53CR RESIDUAL, AND ENERGY DEPENDENT YIELD 2437 1451 70 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2437 1451 71 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2437 1451 72 EACH PRODUCT. ISOTROPY IS ASSUMED. 2437 1451 73 6-51 THROUGH 6-54 INELASTIC SCATTERING EXCITING LEVELS; 2437 1451 74 ASSUMED ISOTROPIC. 2437 1451 75 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2437 1451 76 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 54CR 2437 1451 77 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2437 1451 78 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2437 1451 79 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2437 1451 80 FOR EACH. ISOTROPY IS ASSUMED. 2437 1451 81 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2437 1451 82 AND 54V RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2437 1451 83 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2437 1451 84 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2437 1451 85 PRODUCT. ISOTROPY IS ASSUMED. 2437 1451 86 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2437 1451 87 AND 51TI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2437 1451 88 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2437 1451 89 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2437 1451 90 PRODUCT. ISOTROPY IS ASSUMED. 2437 1451 91 12-51 THROUGH 12-54 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2437 1451 92 12-102 (N,G) CAPTURE; TNG CALCULATED. 2437 1451 93 14-51 THROUGH 14-54 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2437 1451 94 ASSUMED TO BE ISOTROPIC. 2437 1451 95 15-102 (N,G) CAPTURE; TNG CALCULATED. 2437 1451 96 2437 1451 97 -------------------------------------------------------------- 2437 1451 98 UNCERTAINTY FILES 2437 1451 99 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2437 1451 100 REQUIRED BY ENDF/B-VI. 2437 1451 101 2437 1451 102 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2437 1451 103 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2437 1451 104 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2437 1451 105 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2437 1451 106 20 MEV THE FILES ARE DERIVED. 2437 1451 107 33-3 FROM 1.E-5 TO 900 KEV UNCERTAINTIES ARE DERIVED. FROM 9002437 1451 108 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82437 1451 109 33-4 UNCERTAINTIES ARE ALL DERIVED. 2437 1451 110 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG 2437 1451 111 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2437 1451 112 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2437 1451 113 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2437 1451 114 ENERGIES, AND CALCULATED RESULTS ABOVE 900 KEV. 2437 1451 115 33-103 UNCERTAINTIES ESTIMATED FROM TNG. 2437 1451 116 33-107 UNCERTAINTIES ESTIMATED FROM TNG. 2437 1451 117 2437 1451 118 REFERENCES: 2437 1451 119 (1) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2437 1451 120 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2437 1451 121 MOMENTUM," ORNL/TM-7042 (1980). 2437 1451 122 (2) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2437 1451 123 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2437 1451 124 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2437 1451 125 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2437 1451 126 NATIONAL LAB. 2437 1451 127 (3) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2437 1451 128 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2437 1451 129 (4) H.M. AGRAWAL, J.B. GARG, AND J.A. HARVEY, PHYS. REV. C, 2437 1451 130 30, 6, 1880-1894 (DEC., 1984). 2437 1451 131 (5) B.J. ALLEN AND A.R. DE L. MUSGROVE, "S-WAVE RESONANCE 2437 1451 132 PARAMETERS IN THE STRUCTURAL MATERIALS," PROC. OF A 2437 1451 133 SPECIALISTS' MEETING ON NEUTRON DATA OF STRUCTURAL MATERIALS 2437 1451 134 FOR FAST REACTORS HELD AT CENTRAL BUREAU FOR NUCLEAR MEAS. 2437 1451 135 GEEL, BELGIUM (DEC. 5-8, 1977). 2437 1451 136 2437 1451 137 1 451 141 12437 1451 138 2 151 123 12437 1451 139 3 102 9 12437 1451 140 3 107 10 12437 1451 141 2437 1 0 142 2437 0 0 143 2.405400+4 5.347600+1 0 0 1 02437 2151 144 2.405400+4 1.000000+0 0 0 1 02437 2151 145 1.000000-5 9.000000+5 1 3 0 12437 2151 146 0.000000+0 5.512500-1 1 0 3 32437 2151 147 5.347600+1 5.512500-1 0 0 126 212437 2151 148 -7.718600+5 5.000000-1 3.766000+5 2.009800+0 0.000000+0 0.000000+02437 2151 149 -1.386200+5 5.000000-1 1.003400+3 2.001900+0 0.000000+0 0.000000+02437 2151 150 -7.069500+3 5.000000-1 2.080200+1 1.439900+1 0.000000+0 0.000000+02437 2151 151 2.262400+4 5.000000-1 1.866100+3 2.020400-1 0.000000+0 0.000000+02437 2151 152 1.193000+5 5.000000-1 4.866500+3 4.600000+0 0.000000+0 0.000000+02437 2151 153 1.313500+5 5.000000-1 3.040200+2 2.500000+0 0.000000+0 0.000000+02437 2151 154 1.764000+5 5.000000-1 2.087100+3 1.000000+0 0.000000+0 0.000000+02437 2151 155 2.833700+5 5.000000-1 9.251702+3 3.000000+0 0.000000+0 0.000000+02437 2151 156 3.298000+5 5.000000-1 9.296100+3 2.500000+0 0.000000+0 0.000000+02437 2151 157 3.523000+5 5.000000-1 4.875500+2 2.500000+0 0.000000+0 0.000000+02437 2151 158 4.859800+5 5.000000-1 1.238900+4 2.500000+0 0.000000+0 0.000000+02437 2151 159 5.523500+5 5.000000-1 1.788700+3 2.500000+0 0.000000+0 0.000000+02437 2151 160 5.950000+5 5.000000-1 7.101000+4 2.500000+0 0.000000+0 0.000000+02437 2151 161 6.623800+5 5.000000-1 9.478100+3 2.500000+0 0.000000+0 0.000000+02437 2151 162 7.386500+5 5.000000-1 2.006500+3 2.500000+0 0.000000+0 0.000000+02437 2151 163 7.530600+5 5.000000-1 4.412400+3 2.500000+0 0.000000+0 0.000000+02437 2151 164 7.905000+5 5.000000-1 1.098400+3 2.500000+0 0.000000+0 0.000000+02437 2151 165 8.096000+5 5.000000-1 9.997700+2 2.500000+0 0.000000+0 0.000000+02437 2151 166 1.000000+6 5.000000-1 3.207500+3 2.500000+0 0.000000+0 0.000000+02437 2151 167 1.200000+6 5.000000-1 9.255000+2 2.500000+0 0.000000+0 0.000000+02437 2151 168 2.000000+6 5.000000-1 1.254000+4 2.500000+0 0.000000+0 0.000000+02437 2151 169 5.347600+1 5.512500-1 1 0 276 462437 2151 170 1.029000+4 1.500000+0 4.000000-1 1.600000-1 0.000000+0 0.000000+02437 2151 171 1.444300+4 1.500000+0 6.500000-1 2.700000-1 0.000000+0 0.000000+02437 2151 172 1.482500+4 5.000000-1 4.200000-1 6.800000-1 0.000000+0 0.000000+02437 2151 173 1.921000+4 1.500000+0 3.000000-1 2.800000-1 0.000000+0 0.000000+02437 2151 174 5.113000+4 1.500000+0 2.000000-1 1.600000-1 0.000000+0 0.000000+02437 2151 175 5.491200+4 5.000000-1 5.900000+1 3.000000-1 0.000000+0 0.000000+02437 2151 176 6.737900+4 1.500000+0 1.300000+0 5.800000-1 0.000000+0 0.000000+02437 2151 177 9.460200+4 5.000000-1 8.600000+1 6.800000-1 0.000000+0 0.000000+02437 2151 178 1.012600+5 1.500000+0 1.050000+1 6.800000-1 0.000000+0 0.000000+02437 2151 179 1.290600+5 1.500000+0 8.000000+0 6.800000-1 0.000000+0 0.000000+02437 2151 180 1.359000+5 5.000000-1 1.290000+2 6.800000-1 0.000000+0 0.000000+02437 2151 181 1.647000+5 1.500000+0 9.500000+0 8.800000-1 0.000000+0 0.000000+02437 2151 182 1.702000+5 5.000000-1 1.800000+2 8.800000-1 0.000000+0 0.000000+02437 2151 183 1.838000+5 1.500000+0 3.000000+0 6.800000-1 0.000000+0 0.000000+02437 2151 184 2.036400+5 5.000000-1 8.600000+1 6.800000-1 0.000000+0 0.000000+02437 2151 185 2.486000+5 1.500000+0 2.500000+2 1.200000+0 0.000000+0 0.000000+02437 2151 186 2.668400+5 1.500000+0 4.900000+1 6.800000-1 0.000000+0 0.000000+02437 2151 187 2.745600+5 5.000000-1 9.000000+0 6.800000-1 0.000000+0 0.000000+02437 2151 188 3.147000+5 1.500000+0 8.750000+1 6.800000-1 0.000000+0 0.000000+02437 2151 189 3.322900+5 1.500000+0 5.000000+1 6.800000-1 0.000000+0 0.000000+02437 2151 190 3.764800+5 5.000000-1 7.000000+1 6.800000-1 0.000000+0 0.000000+02437 2151 191 3.872700+5 1.500000+0 5.000000+2 6.800000-1 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1.500000+0 3.250000+0 4.300000-1 0.000000+0 0.000000+02437 2151 218 9.577600+4 2.500000+0 8.000000+0 1.600000+0 0.000000+0 0.000000+02437 2151 219 1.566000+5 1.500000+0 3.400000+1 6.800000-1 0.000000+0 0.000000+02437 2151 220 1.904000+5 2.500000+0 4.700000+1 6.800000-1 0.000000+0 0.000000+02437 2151 221 2.098100+5 1.500000+0 4.850000+1 1.600000+0 0.000000+0 0.000000+02437 2151 222 2.255700+5 2.500000+0 1.066700+1 2.350000+0 0.000000+0 0.000000+02437 2151 223 2.496300+5 2.500000+0 5.667000+0 1.600000+0 0.000000+0 0.000000+02437 2151 224 2.506800+5 2.500000+0 8.667000+0 1.600000+0 0.000000+0 0.000000+02437 2151 225 2.762500+5 1.500000+0 7.500000+0 1.600000+0 0.000000+0 0.000000+02437 2151 226 3.049200+5 1.500000+0 5.300000+1 1.600000+0 0.000000+0 0.000000+02437 2151 227 3.208700+5 2.500000+0 6.000000+1 1.600000+0 0.000000+0 0.000000+02437 2151 228 3.331700+5 2.500000+0 1.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 229 3.583100+5 1.500000+0 2.505000+2 1.600000+0 0.000000+0 0.000000+02437 2151 230 3.800500+5 2.500000+0 1.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 231 3.859300+5 1.500000+0 5.000000+1 1.600000+0 0.000000+0 0.000000+02437 2151 232 4.308600+5 2.500000+0 6.000000+2 6.800000-1 0.000000+0 0.000000+02437 2151 233 4.415600+5 1.500000+0 1.500000+3 1.600000+0 0.000000+0 0.000000+02437 2151 234 4.533500+5 2.500000+0 8.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 235 4.580000+5 2.500000+0 4.000000+1 6.800000-1 0.000000+0 0.000000+02437 2151 236 4.707300+5 2.500000+0 3.000000+2 6.800000-1 0.000000+0 0.000000+02437 2151 237 4.903200+5 1.500000+0 4.750000+2 1.600000+0 0.000000+0 0.000000+02437 2151 238 5.306700+5 2.500000+0 2.666700+2 1.600000+0 0.000000+0 0.000000+02437 2151 239 5.375900+5 2.500000+0 3.500000+2 1.600000+0 0.000000+0 0.000000+02437 2151 240 5.516700+5 2.500000+0 1.500000+2 1.600000+0 0.000000+0 0.000000+02437 2151 241 5.722500+5 1.500000+0 1.250000+2 1.600000+0 0.000000+0 0.000000+02437 2151 242 5.773500+5 1.500000+0 1.250000+2 1.600000+0 0.000000+0 0.000000+02437 2151 243 6.141000+5 1.500000+0 1.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 244 6.240000+5 1.500000+0 2.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 245 6.251000+5 2.500000+0 5.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 246 6.293000+5 2.500000+0 1.066700+3 1.600000+0 0.000000+0 0.000000+02437 2151 247 6.311000+5 2.500000+0 9.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 248 6.479000+5 1.500000+0 2.000000+3 1.600000+0 0.000000+0 0.000000+02437 2151 249 6.480200+5 2.500000+0 3.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 250 6.890000+5 2.500000+0 2.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 251 7.074000+5 1.500000+0 4.500000+2 6.800000-1 0.000000+0 0.000000+02437 2151 252 7.342000+5 2.500000+0 1.000000+3 1.600000+0 0.000000+0 0.000000+02437 2151 253 7.438000+5 1.500000+0 1.000000+3 1.600000+0 0.000000+0 0.000000+02437 2151 254 7.490000+5 2.500000+0 7.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 255 7.541500+5 2.500000+0 7.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 256 7.606800+5 1.500000+0 3.150000+2 1.600000+0 0.000000+0 0.000000+02437 2151 257 7.850800+5 2.500000+0 3.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 258 7.940000+5 1.500000+0 6.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 259 8.127200+5 2.500000+0 2.333300+2 1.600000+0 0.000000+0 0.000000+02437 2151 260 8.157000+5 1.500000+0 1.250000+3 1.600000+0 0.000000+0 0.000000+02437 2151 261 8.405800+5 1.500000+0 7.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 262 8.408100+5 2.500000+0 1.500000+2 1.600000+0 0.000000+0 0.000000+02437 2151 263 8.481900+5 2.500000+0 1.433300+2 1.600000+0 0.000000+0 0.000000+02437 2151 264 8.531100+5 1.500000+0 2.050000+2 1.600000+0 0.000000+0 0.000000+02437 2151 265 8.834600+5 2.500000+0 3.000000+2 1.600000+0 0.000000+0 0.000000+02437 2151 266 2437 2 0 267 2437 0 0 268 2.405400+4 5.347600+1 0 0 0 02437 3102 269 6.246300+6 6.246300+6 0 0 1 162437 3102 270 16 2 0 0 0 02437 3102 271 1.000000-5 0.000000+0 9.000000+5 0.000000+0 9.000000+5 2.100000-32437 3102 272 9.500000+5 1.430000-3 1.000000+6 1.192000-3 1.500000+6 1.084000-32437 3102 273 2.000000+6 9.760000-4 3.000000+6 8.800000-4 4.000000+6 6.872000-42437 3102 274 5.000000+6 5.200000-4 7.500000+6 2.808000-4 1.000000+7 2.830000-42437 3102 275 1.200000+7 5.110000-4 1.450000+7 5.540000-4 1.750000+7 4.360000-42437 3102 276 2.000000+7 5.990000-5 0.000000+0 0.000000+0 0.000000+0 0.000000+02437 3102 277 2437 3 0 278 2.405400+4 5.347600+1 0 0 0 02437 3107 279 -1.552000+6-1.552000+6 0 0 1 202437 3107 280 20 2 0 0 0 02437 3107 281 1.581000+6 0.000000+0 4.500000+6 1.265900-7 5.000000+6 1.328100-62437 3107 282 5.500000+6 8.368000-6 6.000000+6 1.594600-5 6.500000+6 3.655200-42437 3107 283 7.000000+6 9.550100-4 7.500000+6 1.898400-3 8.000000+6 2.998600-32437 3107 284 8.500000+6 3.964700-3 9.000000+6 4.635600-3 9.500000+6 5.538700-32437 3107 285 1.000000+7 6.189700-3 1.100000+7 7.440200-3 1.200000+7 8.491200-32437 3107 286 1.300000+7 9.638900-3 1.450000+7 1.160500-2 1.600000+7 1.422300-22437 3107 287 1.750000+7 1.739000-2 2.000000+7 2.384700-2 0.000000+0 0.000000+02437 3107 288 2437 3 0 289 2437 0 0 290 0 0 0 291 2.505500+4 5.446610+1 1 0 0 12525 1451 1 0.000000+0 0.000000+0 0 0 0 62525 1451 2 1.000000+0 0.000000+0 0 0 10 62525 1451 3 0.000000+0 0.000000+0 0 0 213 102525 1451 4 25-MN- 55 JAERI,ORNL EVAL-MAR88 K.SHIBATA 2525 1451 5 DIST-APR90 900420 2525 1451 6 ----ENDF/B-VI MATERIAL 2525 2525 1451 7 -----INCIDENT NEUTRON DATA 2525 1451 8 ------ENDF-6 FORMAT 2525 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2525 1451 10 ACTIVATION I 2525 1451 11 ******************************************************************2525 1451 12 2525 1451 13 MF=1 GENERAL INFORMATION 2525 1451 14 MT=451 DESCRIPTIVE DATA AND DICTIONARY 2525 1451 15 2525 1451 16 MF=2 RESONANCE PARAMETERS 2525 1451 17 MT=151 RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA 2525 1451 18 THE PARAMETERS OF THE LOWEST FOUR RESONANCES WERE TAKEN 2525 1451 19 FROM THE WORK OF MACKLIN /1/. OTHERS WERE TAKEN FROM THE 2525 1451 20 COMPILATION OF MUGHABGHAB ET AL./2/ EXCEPT THAT THE 2525 1451 21 PARAMETERS OF TWO NEGATIVE RESONANCES WERE ADJUSTED SO AS 2525 1451 22 TO FIT TO EXPERIMENTAL THERMAL CROSS SECTIONS. 2525 1451 23 RESONANCE REGION : 1.0E-5 EV TO 100 KEV. 2525 1451 24 SCATTERING RADIUS: 5.15 FM 2525 1451 25 CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS 2525 1451 26 2200-M/S RES. INTEG. 2525 1451 27 ELASTIC 2.167 B - 2525 1451 28 CAPTURE 13.413 B 11.73 B 2525 1451 29 TOTAL 15.579 B - 2525 1451 30 2525 1451 31 MF=3 NEUTRON CROSS SECTIONS 2525 1451 32 MT=1 TOTAL 2525 1451 33 BELOW 100 KEV : NO BACKGROUND 2525 1451 34 ABOVE 100 KEV : BASED ON THE EXPERIMENTAL DATA /3,4,5/. 2525 1451 35 MT=2 ELASTIC SCATTERING 2525 1451 36 (TOTAL) - (NONELASTIC CROSS SECTION) 2525 1451 37 MT=3 NON ELASTIC 2525 1451 38 SUM OF MT=4, 16, 22, 28, 102, 103, 104, 105, 106 AND 107 2525 1451 39 MT=4,51-79,91 INELASTIC SCATTERING 2525 1451 40 STATISTICAL-MODEL CALCULATIONS WERE PERFORMED USING THE 2525 1451 41 TNG CODE /6/. THE PRECOMPOUND PROCESS WAS CONSIDERED 2525 1451 42 ABOVE 5 MEV. THE CALCULATED CROSS SECTION OF MT=51 2525 1451 43 WAS MULTIPLIED BY A FACTOR OF 1.2. 2525 1451 44 FOR THE LEVELS OF MT=51,52,57,61,64,65,67,70, 2525 1451 45 THE DIRECT PROCESS COMPONENTS WERE TAKEN INTO ACCOUNT 2525 1451 46 BY THE DWBA CALCULATIONS. 2525 1451 47 THE OPTICAL POTENTIAL PARAMETERS USED ARE AS FOLLOWS/7/ 2525 1451 48 (IN THE UNITS OF MEV AND FM): 2525 1451 49 V = 49.747 - 0.4295*E - 0.0003*E**2 R0 = 1.287 A0 = 0.56 2525 1451 50 WS = 11.2 - 0.09*E RS = 1.345 AS = 0.47 2525 1451 51 VSO= 6.2 RSO= 1.120 ASO = 0.47 2525 1451 52 THE LEVEL SCHEME WAS TAKEN FROM REF./8/. 2525 1451 53 NO. ENERGY(MEV) SPIN-PARITY 2525 1451 54 G.S. 0.0 5/2 - 2525 1451 55 1. 0.126 7/2 - 2525 1451 56 2. 0.984 9/2 - 2525 1451 57 3. 1.290 1/2 - 2525 1451 58 4. 1.292 11/2 - 2525 1451 59 5. 1.293 1/2 - 2525 1451 60 6. 1.528 3/2 - 2525 1451 61 7. 1.884 7/2 - 2525 1451 62 8. 2.015 7/2 - 2525 1451 63 9. 2.198 7/2 - 2525 1451 64 10. 2.215 5/2 - 2525 1451 65 11. 2.252 3/2 - 2525 1451 66 12. 2.267 5/2 - 2525 1451 67 13. 2.312 13/2 - 2525 1451 68 14. 2.366 5/2 - 2525 1451 69 15. 2.398 9/2 + 2525 1451 70 16. 2.427 1/2 + 2525 1451 71 17. 2.563 3/2 - 2525 1451 72 18. 2.727 7/2 - 2525 1451 73 19. 2.753 5/2 - 2525 1451 74 20. 2.822 9/2 - 2525 1451 75 21. 2.824 5/2 - 2525 1451 76 22. 2.873 1/2 - 2525 1451 77 23. 2.954 3/2 - 2525 1451 78 24. 2.976 3/2 - 2525 1451 79 25. 2.992 7/2 - 2525 1451 80 26. 3.006 3/2 - 2525 1451 81 27. 3.036 11/2 - 2525 1451 82 28. 3.038 1/2 - 2525 1451 83 29. 3.040 3/2 + 2525 1451 84 2525 1451 85 LEVELS ABOVE 3.046 MEV WERE ASSUMED TO BE OVERLAPPING. 2525 1451 86 2525 1451 87 MT=16,22,28,103,107 (N,2N),(N,N'A),(N,N'P),(N,P) AND (N,A) 2525 1451 88 CROSS SECTIONS 2525 1451 89 CALCULTED WITH TNG. 2525 1451 90 GLOBAL OPTICAL-POTENTIAL PARAMETERS WERE EMPLOYED 2525 1451 91 FOR PROTONS AND ALPHA-PARTICLES /9,10/. 2525 1451 92 2525 1451 93 MT=102 RADIATIVE CAPTURE CROSS SECTION 2525 1451 94 BELOW 100 KEV : RESONANCE PARAMETERS GIVEN (NO BACKGROUND)2525 1451 95 ABOVE 100 KEV : BASED ON THE EXPERIMENTAL DATA /11/-/15/. 2525 1451 96 (TAKEN FROM JENDL-2 /20/) 2525 1451 97 2525 1451 98 MT=104 (N,D) CROSS SECTION 2525 1451 99 THE EXCITATION FUNCTION OF THE (N,P) CROSS SECTION 2525 1451 100 CALCULATED WITH TNG WAS USED FOR THE (N,D) REACTION BY 2525 1451 101 SHIFTING THE THRESHOLD ENERGY. THE CROSS SECTIONS WERE 2525 1451 102 NORMALIZED TO THE EXPERIMENTAL DATUM AT 14.1 MEV /16/. 2525 1451 103 2525 1451 104 MT=105 (N,T) CROSS SECTION 2525 1451 105 THE EXCITATION FUNCTION OF THE (N,P) CROSS SECTION 2525 1451 106 CALCULATED WITH TNG WAS USED FOR THE (N,T) REACTION BY 2525 1451 107 SHIFTING THE THRESHOLD ENERGY. THE CROSS SECTIONS WERE 2525 1451 108 NORMALIZED TO THE EXPERIMENTAL DATUM AT 14.7 MEV /17/. 2525 1451 109 2525 1451 110 MT=106 (N,HE-3) CROSS SECTION 2525 1451 111 BASED ON THE EXPERMENTAL DATA /18,19/. 2525 1451 112 2525 1451 113 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 2525 1451 114 MT=2 ELASTIC 2525 1451 115 OPTICAL AND STATISTICAL-MODEL CALCULATIONS 2525 1451 116 2525 1451 117 MF=6 ENERGY-ANGLE DISTRIBUTIONS 2525 1451 118 MT=16 (N,2N) 2525 1451 119 ENERGY DISTRIBUTIONS OF NEUTRONS, RECOILS AND GAMMA-RAYS 2525 1451 120 WERE CALCULATED BY TNG. ANGULAR DISTRIBUTIONS ARE GIVEN 2525 1451 121 ONLY FOR NEUTRONS. 2525 1451 122 2525 1451 123 MT=22 (N,N'A) 2525 1451 124 ENERGY DISTRIBUTIONS OF NEUTRONS, ALPHAS, RECOILS AND 2525 1451 125 GAMMA-RAYS WERE CALCULATED BY TNG. ANGULAR DISTRIBUTIONS 2525 1451 126 ARE GIVEN ONLY FOR NEUTRONS. 2525 1451 127 2525 1451 128 MT=28 (N,N'P) 2525 1451 129 ENERGY DISTRIBUTIONS OF NEUTRONS, PROTONS, RECOILS AND 2525 1451 130 GAMMA-RAYS WERE CALCULATED BY TNG. ANGULAR DISTRIBUTIONS 2525 1451 131 ARE GIVEN ONLY FOR NEUTRONS. 2525 1451 132 2525 1451 133 MT=51 TO 79 INELASTIC SCATTERING TO DISCRETE LEVELS 2525 1451 134 OPTICAL AND STATISTICAL-MODEL CALCULATIONS 2525 1451 135 THE COMPONENTS OF THE DIRECT-INTERACTION PROCESS WERE 2525 1451 136 ADDED TO THE LEVELS OF MT=51,52,57,61,64,65,67,70 BY THE 2525 1451 137 DWBA CALCULATIONS. 2525 1451 138 2525 1451 139 MT=91 INELASTIC SCATTERING TO CONTINUUM LEVELS 2525 1451 140 ENERGY DISTRIBUTIONS OF NEUTRONS, RECOILS AND GAMMA-RAYS 2525 1451 141 WERE CALCULATED BY TNG. ANGULAR DISTRIBUTIONS ARE GIVEN 2525 1451 142 ONLY FOR NEUTRONS. 2525 1451 143 2525 1451 144 MT=103 (N,P) 2525 1451 145 ENERGY DISTRIBUTIONS OF PROTONS, RECOILS AND GAMMA-RAYS 2525 1451 146 WERE CALCULATED BY TNG. 2525 1451 147 2525 1451 148 MT=107 (N,A) 2525 1451 149 ENERGY DISTRIBUTIONS OF ALPHAS, RECOILS AND GAMMA-RAYS 2525 1451 150 WERE CALCULATED BY TNG. 2525 1451 151 2525 1451 152 MF=12 PHOTON PRODUCTION MULTIPLICITIES 2525 1451 153 MT=51 TO 79 2525 1451 154 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2525 1451 155 MT=102 CAPTURE 2525 1451 156 CALCULATED WITH TNG. 2525 1451 157 2525 1451 158 MF=14 PHOTON ANGULAR DISTRIBUTIONS 2525 1451 159 MT=51 TO 79 2525 1451 160 ASSUMED TO BE ISOTROPIC. 2525 1451 161 MT=102 CAPTURE 2525 1451 162 ASSUMED TO BE ISOTROPIC. 2525 1451 163 2525 1451 164 MF=15 PHOTON ENERGY DISTRIBUTIONS 2525 1451 165 MT=102 CAPTURE 2525 1451 166 CALCULATED WITH TNG. 2525 1451 167 2525 1451 168 MF=33 COVARIANCE DATA 2525 1451 169 MT=1,2,3,4,16,22,28,51-79,91,102,103,104,105,106,107 2525 1451 170 ESTIMATED FROM EXPERIMENTAL DATA AND CALCULATION 2525 1451 171 2525 1451 172 REFERNCES 2525 1451 173 1) MACKLIN, R.L.: NUCL. SCI. ENG., 89, 362 (1985). 2525 1451 174 2) MUGABGHAB, S.F., DIVADEENAM, M. AND HOLDEN, N.E.: "NEUTRON 2525 1451 175 CROSS SECTIONS", VOL. 1, PART A, ACADEMIC PRESS (1981). 2525 1451 176 3) CIERJACKS, S., FORTI, P., KOPSCH, D., KROPP, L., NEBE, J. 2525 1451 177 AND UNSELD, H.: "HIGH RESOLUTION TOTAL CROSS SECTIONS 2525 1451 178 FOR NA, CL, K, V, MN AND CO BETWEEN 0.5 AND 30 MEV", 2525 1451 179 KFK-1000 (1968). 2525 1451 180 4) PINEO, W.F.E., DIVADEENAM, M., BILPUCH, E.G., SETH, K.K. 2525 1451 181 AND NEWSON, H.W.: ANN. PHYS., 84, 165 (1974). 2525 1451 182 5) GARG, J.B., RAINWATER, J. AND HAVENS, JR., W.W.: 2525 1451 183 NUCL. SCI. ENG., 65, 76 (1978). 2525 1451 184 6) FU, C.Y.: "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2525 1451 185 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2525 1451 186 MOMENTUM", ORNL/TM-7042 (1980). 2525 1451 187 7) FU, C.Y.: PRIVATE COMMUNICATION (1985). 2525 1451 188 8) ZHOU ENCHEN, HUO JUNDE, ZHOU CHUNMEI, LU XIANE AND 2525 1451 189 WANG LIZHENG: NUCL. DATA SHEETS, 44, 463 (1985). 2525 1451 190 9) PEREY, F.G.: PHYS. REV., 131, 745 (1963). 2525 1451 191 10) HUIZENGA, J.R. AND IGO, G.J.: NUCL. PHYS., 29, 462 (1962). 2525 1451 192 11) GARG, J.B., MACKLIN, R.L. AND HALPERIN, J.: PHYS. REV., 2525 1451 193 C18, 2079 (1978). 2525 1451 194 12) DOVBENKO, A.G., KOLESOV, V.E., KOROLEVA, V.P., TOLSTIKOV, 2525 1451 195 V.A.: ATOM. ENERG., 26, 67 (1969). 2525 1451 196 13) MENLOVE, H.O., COOP, K.L., GRENCH, H.A. AND SHER, R.: 2525 1451 197 PHYS. REV., 163, 1299 (1967). 2525 1451 198 14) SCHWERER, O., WINKLER-ROHATSCH, M., WARHANEK, H. AND 2525 1451 199 WINKLER, G.: NUCL. PHYS., A264, 105 (1976). 2525 1451 200 15) BUDNAR, M., CVELBAR, F., HODGSON, E., HUDOKLIN, A., 2525 1451 201 IVKOVIC, V., LIKAR, A., MIHAILOVIC, M.V., MARTINCIC, R., 2525 1451 202 NAJZER, M., PERDAN, A., POTOKAR, M. AND RAMSAK, V.: 2525 1451 203 "PROMPT GAMMA-RAY SPECTRA AND INTEGARTED CROSS SECTIONS 2525 1451 204 FOR THE RADIATIVE CAPTURE OF 14 MEV NEUTRONS FOR 28 2525 1451 205 NATURAL TARGETS IN THE MASS REGION FROM 12 TO 208", 2525 1451 206 INDC(YUG)-6 (1979). 2525 1451 207 16) COLLI, L., IORI, I., MICHELETTI, S. AND PIGNANELLI, M.: 2525 1451 208 NUOVO. CIM., 21, 966 (1962). 2525 1451 209 17) SUDAR, S. AND CSIKAI, J.: NUCL. PHYS., A319, 157 (1979). 2525 1451 210 18) DIKSIC, M., STROHAL, P. AND SLAUS, I.: J. INORG. NUCL. 2525 1451 211 CHEM., 36, 477 (1974). 2525 1451 212 19) WU, C.H., WOELFLE, R. AND QAIM, S.M.: NUCL. PHYS., A329, 2525 1451 213 63 (1979). 2525 1451 214 20) NAKAGAWA, T.: "SUMMARY OF JENDL-2 GENERAL PURPOSE 2525 1451 215 FILE", JAERI-M 84-103 (1984). 2525 1451 216 2525 1451 217 1 451 227 12525 1451 218 2 151 155 12525 1451 219 3 16 7 12525 1451 220 3 102 58 12525 1451 221 3 103 13 12525 1451 222 3 107 12 12525 1451 223 33 16 12 12525 1451 224 33 102 17 12525 1451 225 33 103 12 12525 1451 226 33 107 14 12525 1451 227 2525 1 0 228 2525 0 0 229 2.505500+4 5.446610+1 0 0 1 02525 2151 230 2.505500+4 1.000000+0 0 0 1 02525 2151 231 1.000000-5 1.000000+5 1 2 0 02525 2151 232 2.500000+0 5.150000-1 0 0 2 02525 2151 233 5.446610+1 0.000000+0 0 0 312 522525 2151 234 -5.100000+3 3.000000+0 3.195500+2 3.169000+2 2.650000+0 0.000000+02525 2151 235 -2.400000+3 2.000000+0 2.786000+2 2.759500+2 2.650000+0 0.000000+02525 2151 236 3.373000+2 2.000000+0 2.230000+1 2.199000+1 3.100000-1 0.000000+02525 2151 237 1.099000+3 3.000000+0 1.569200+1 1.538000+1 3.120000-1 0.000000+02525 2151 238 1.658000+3 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6.800000-42525 3102 446 1.200000+7 6.780000-4 1.250000+7 6.750000-4 1.300000+7 6.720000-42525 3102 447 1.350000+7 6.690000-4 1.400000+7 6.650000-4 1.450000+7 6.600000-42525 3102 448 1.500000+7 6.540000-4 1.550000+7 6.480000-4 1.600000+7 6.400000-42525 3102 449 1.650000+7 6.280000-4 1.700000+7 6.080000-4 1.750000+7 5.730000-42525 3102 450 1.800000+7 5.280000-4 1.850000+7 4.740000-4 1.900000+7 4.100000-42525 3102 451 1.950000+7 3.350000-4 2.000000+7 2.490000-4 0.000000+0 0.000000+02525 3102 452 2525 3 0 453 2.505500+4 5.446610+1 0 0 0 02525 3103 454 -1.821200+6-1.821200+6 0 0 1 282525 3103 455 28 2 0 0 0 02525 3103 456 1.854640+6 0.000000+0 2.750000+6 6.152290-8 3.000000+6 2.641800-62525 3103 457 3.500000+6 5.968400-5 4.000000+6 3.849400-4 4.500000+6 1.377900-32525 3103 458 5.000000+6 1.942000-3 5.500000+6 5.719700-3 6.000000+6 8.223900-32525 3103 459 6.500000+6 1.035800-2 7.000000+6 1.181000-2 7.500000+6 1.310400-22525 3103 460 8.000000+6 1.444300-2 8.500000+6 1.601500-2 9.000000+6 1.809700-22525 3103 461 9.500000+6 2.077100-2 1.000000+7 2.397900-2 1.100000+7 3.127600-22525 3103 462 1.200000+7 3.693800-2 1.300000+7 3.900300-2 1.400000+7 3.740200-22525 3103 463 1.450000+7 3.586200-2 1.500000+7 3.412900-2 1.600000+7 2.996100-22525 3103 464 1.700000+7 2.652500-2 1.800000+7 2.420300-2 1.900000+7 2.217700-22525 3103 465 2.000000+7 2.055600-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02525 3103 466 2525 3 0 467 2.505500+4 5.446610+1 0 0 0 02525 3107 468 -6.243000+5-6.243000+5 0 0 1 252525 3107 469 25 2 0 0 0 02525 3107 470 6.357620+5 0.000000+0 4.000000+6 3.587300-7 4.500000+6 5.048300-62525 3107 471 5.000000+6 3.486400-5 5.500000+6 1.584600-4 6.000000+6 5.272700-42525 3107 472 6.500000+6 1.368900-3 7.000000+6 2.807900-3 7.500000+6 4.788500-32525 3107 473 8.000000+6 6.920700-3 8.500000+6 8.898700-3 9.000000+6 1.071600-22525 3107 474 9.500000+6 1.235900-2 1.000000+7 1.382500-2 1.100000+7 1.672300-22525 3107 475 1.200000+7 1.997000-2 1.300000+7 2.384700-2 1.400000+7 2.768500-22525 3107 476 1.450000+7 2.892000-2 1.500000+7 2.909700-2 1.600000+7 2.682200-22525 3107 477 1.700000+7 2.217600-2 1.800000+7 1.761700-2 1.900000+7 1.369400-22525 3107 478 2.000000+7 1.075100-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02525 3107 479 2525 3 0 480 2525 0 0 481 2.505500+4 5.446600+1 0 0 0 1252533 16 482 0.000000+0 0.000000+0 0 16 0 3252533 16 483 0.000000+0 0.000000+0 0 1 6 3252533 16 484 1.000000-5 0.000000+0 1.041500+7 2.500000-3 2.000000+7 0.000000+0252533 16 485 0.000000+0 0.000000+0 0 1 16 8252533 16 486 1.000000-5 0.000000+0 1.041500+7 8.100000-2 1.200000+7 8.100000-2252533 16 487 1.300000+7 7.290000-3 1.400000+7 4.050000-3 1.500000+7 3.240000-3252533 16 488 1.700000+7 3.240000-3 2.000000+7 0.000000+0 0.000000+0 0.000000+0252533 16 489 0.000000+0 0.000000+0 0 8 16 8252533 16 490 1.000000-5 0.000000+0 1.041500+7 3.954900-5 1.200000+7 9.471800-4252533 16 491 1.300000+7 2.620600-4 1.400000+7 2.326300-4 1.500000+7 2.291100-4252533 16 492 1.700000+7 2.509400-4 2.000000+7 0.000000+0 0.000000+0 0.000000+0252533 16 493 252533 0 494 2.505500+4 5.446600+1 0 0 0 1252533102 495 0.000000+0 0.000000+0 0 102 0 3252533102 496 0.000000+0 0.000000+0 0 1 8 4252533102 497 1.000000-5 1.600000-3 1.000000+3 2.500000-3 2.000000+6 1.000000-2252533102 498 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0252533102 499 0.000000+0 0.000000+0 0 1 26 13252533102 500 1.000000-5 3.960000-4 2.530000-2 2.227500-4 5.000000+1 3.960000-4252533102 501 2.000000+3 3.564000-3 6.000000+4 6.336000-3 1.500000+5 9.900000-3252533102 502 1.000000+6 2.227500-2 2.000000+6 2.227500-2 5.000000+6 3.960000-2252533102 503 7.000000+6 3.960000-2 1.000000+7 8.910000-2 1.450000+7 8.910000-2252533102 504 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0252533102 505 0.000000+0 0.000000+0 0 8 26 13252533102 506 1.000000-5 1.960000-2 2.530000-2 6.692000-3 5.000000+1 1.090900-6252533102 507 2.000000+3 2.851600-3 6.000000+4 1.747200-7 1.500000+5 5.975300-9252533102 508 1.000000+6 1.802000-9 2.000000+6 7.37120-10 5.000000+6 4.24360-10252533102 509 7.000000+6 2.29830-10 1.000000+7 4.22300-10 1.450000+7 3.92040-10252533102 510 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0252533102 511 252533 0 512 2.505500+4 5.446600+1 0 0 0 1252533103 513 0.000000+0 0.000000+0 0 103 0 3252533103 514 0.000000+0 0.000000+0 0 1 6 3252533103 515 1.000000-5 0.000000+0 1.854600+6 2.000000-2 2.000000+7 0.000000+0252533103 516 0.000000+0 0.000000+0 0 1 18 9252533103 517 1.000000-5 0.000000+0 1.854600+6 1.800000-2 3.000000+6 1.800000-2252533103 518 4.000000+6 1.800000-2 6.000000+6 1.800000-2 8.000000+6 1.800000-2252533103 519 1.000000+7 1.800000-2 1.450000+7 1.800000-2 2.000000+7 0.000000+0252533103 520 0.000000+0 0.000000+0 0 8 18 9252533103 521 1.000000-5 0.000000+0 1.854600+6 7.57010-18 3.000000+6 1.39580-14252533103 522 4.000000+6 2.96360-10 6.000000+6 1.352700-7 8.000000+6 4.172000-7252533103 523 1.000000+7 1.150000-6 1.450000+7 2.572200-6 2.000000+7 0.000000+0252533103 524 252533 0 525 2.505500+4 5.446600+1 0 0 0 1252533107 526 0.000000+0 0.000000+0 0 107 0 3252533107 527 0.000000+0 0.000000+0 0 1 6 3252533107 528 1.000000-5 0.000000+0 6.357600+5 5.000000-3 2.000000+7 0.000000+0252533107 529 0.000000+0 0.000000+0 0 1 20 10252533107 530 1.000000-5 0.000000+0 6.357600+5 1.012500-2 1.000000+6 1.012500-2252533107 531 3.000000+6 1.012500-2 5.000000+6 1.012500-2 7.000000+6 1.012500-2252533107 532 1.000000+7 1.012500-2 1.300000+7 4.500000-3 1.600000+7 4.500000-3252533107 533 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0252533107 534 0.000000+0 0.000000+0 0 8 20 10252533107 535 1.000000-5 0.000000+0 6.357600+5 1.44770-16 1.000000+6 1.69700-18252533107 536 3.000000+6 7.14990-17 5.000000+6 1.36740-12 7.000000+6 8.869800-9252533107 537 1.000000+7 2.150200-7 1.300000+7 2.843400-7 1.600000+7 3.597100-7252533107 538 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0252533107 539 252533 0 540 2525 0 0 541 0 0 0 542 2.605400+4 5.347600+1 1 0 0 12625 1451 1 0.000000+0 0.000000+0 0 0 0 62625 1451 2 1.000000+0 0.000000+0 0 0 10 62625 1451 3 0.000000+0 0.000000+0 0 0 178 132625 1451 4 26-FE- 54 ORNL EVAL-NOV89 D.M. HETRICK,C.Y. FU,N.M. LARSON 2625 1451 5 ORNL/TM- DIST-APR90 900326 2625 1451 6 ----ENDF/B-VI MATERIAL 2625 2625 1451 7 -----INCIDENT NEUTRON DATA 2625 1451 8 ------ENDF-6 FORMAT 2625 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2625 1451 10 ACTIVATION I 2625 1451 11 ******************************************************************2625 1451 12 THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE 2625 1451 13 DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1) 2625 1451 14 AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES 2625 1451 15 ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE 2625 1451 16 COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL2625 1451 17 REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE 2625 1451 18 CONTENTS OF THIS EVALUATION WILL BE PUBLISHED AT A LATER DATE. 2625 1451 19 RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS ARE FROM 2625 1451 20 REF. (5) AND ADJUSTED THROUGH SAMMY BY N. LARSON USING J.A. 2625 1451 21 HARVEY'S 54-FE DATA (J.A. HARVEY, PRIVATE COMMUNICATION, 1989). 2625 1451 22 BETWEEN 110 AND 700 KEV, CAPTURE CROSS SECTION BACKGROUND IN 2625 1451 23 FILE 3 WAS BASED ON REF. (6). ABOVE 700 KEV, 54-FE DATA FROM 2625 1451 24 J.A. HARVEY (PRIVATE COMMUNICATION, 1989) USED. 2625 1451 25 2625 1451 26 ----- DESCRIPTION OF FILES 2625 1451 27 (MF-MT) 2625 1451 28 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2625 1451 29 2-151 RESONANCE PARAMETERS; SEE ABOVE. 2625 1451 30 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2625 1451 31 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2625 1451 32 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2625 1451 33 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2625 1451 34 3-1 TOTAL CROSS SECTION; SEE ABOVE. 2625 1451 35 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2625 1451 36 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2625 1451 37 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2625 1451 38 3-28, 3-102, 3-103, 3-104, AND 3-107. 2625 1451 39 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2625 1451 40 .., 3-57, AND 3-91 2625 1451 41 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2625 1451 42 CODE (2,3,4). 2625 1451 43 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2625 1451 44 CODE (2,3,4). 2625 1451 45 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2625 1451 46 CODE (2,3,4). 2625 1451 47 3-51 TO 3-57 INELASTIC SCATTERING EXCITING LEVELS; FOR EN>6 MEV,2625 1451 48 RESULTS ARE FROM TNG (2,3,4) WHICH INCLUDES DIRECT 2625 1451 49 INTERACTION CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. 2625 1451 50 FOR EN<6 MEV, TNG CALCULATIONS WERE ADJUSTED TO FIT THE 2625 1451 51 DATA OF GUENTHER ET AL. (7). 2625 1451 52 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM ARE TNG 2625 1451 53 CALCULATED, BUT ADJUSTED AS FOR 3-51 TO 3-57 FOR EN<6 MEV.2625 1451 54 3-102 (N,G) CAPTURE CROSS SECTION; SEE ABOVE. TNG CALCULATIONS 2625 1451 55 NORMALIZED TO THE DATA WERE ADDED FOR ENERGIES FROM 1.0 2625 1451 56 TO 1.5 MEV. 2625 1451 57 3-103 (N,P) CROSS SECTIONS WERE TAKEN FROM THE GLUCS (8) 2625 1451 58 CALCULATION IN WHICH THIS REACTION WAS STUDIED 2625 1451 59 SIMULTANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2625 1451 60 SECTIONS (9). 2625 1451 61 3-104 (N,D) CROSS SECTIONS WERE TAKEN FROM (N,P) SHAPE WHICH 2625 1451 62 WAS NORMALIZED TO DATA OF GRIMES ET AL. (10) AT 14.8 MEV. 2625 1451 63 3-107 (N,A) CROSS SECTIONS WERE TAKEN FROM ENDF/B-V FOR EN < 9 2625 1451 64 MEV. ABOVE 9 MEV, ENDF/B-V CROSS SECTIONS WERE ADJUSTED 2625 1451 65 TO BE SMALLER TO BETTER FIT MEASURED DATA. 2625 1451 66 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2625 1451 67 ELASTIC SCATTERING ARE TAKEN FROM ENDF/B-V. 2625 1451 68 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2625 1451 69 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2625 1451 70 PARAMETERS IN 2/151. 2625 1451 71 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2625 1451 72 NEUTRON AND 53FE RESIDUAL, AND ENERGY DEPENDENT YIELD 2625 1451 73 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2625 1451 74 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2625 1451 75 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2625 1451 76 THE OUTGOING NEUTRON). 2625 1451 77 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2625 1451 78 NEUTRON, ALPHA, AND 50CR RESIDUAL, AND ENERGY DEPENDENT 2625 1451 79 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2625 1451 80 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2625 1451 81 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR2625 1451 82 THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2625 1451 83 ALPHA AND RESIDUAL). (N,XA) D-D EMISSION DATA HEAVILY 2625 1451 84 USED TO BENCHMARK THE CALCULATIONS. 2625 1451 85 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2625 1451 86 NEUTRON, P, AND 53MN RESIDUAL, AND ENERGY DEPENDENT YIELD 2625 1451 87 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2625 1451 88 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2625 1451 89 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2625 1451 90 THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE PROTON 2625 1451 91 AND RESIDUAL). (N,XP) D-D EMISSION USED TO BENCHMARK THE 2625 1451 92 TNG CALCULATIONS. 2625 1451 93 6-51 THROUGH 6-57 INELASTIC SCATTERING EXCITING LEVELS; EACH 2625 1451 94 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2625 1451 95 AND 54FE RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2625 1451 96 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2625 1451 97 BY DWUCK (1) AND TNG (2,3,4)). 2625 1451 98 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2625 1451 99 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 54FE 2625 1451 100 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2625 1451 101 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2625 1451 102 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2625 1451 103 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2625 1451 104 OUTGOING NEUTRON). 2625 1451 105 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2625 1451 106 AND 54MN RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2625 1451 107 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2625 1451 108 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2625 1451 109 PRODUCT. (N,XP) D-D EMISSION DATA USED TO BENCHMARK THE 2625 1451 110 TNG CALCULATIONS. 2625 1451 111 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2625 1451 112 AND 51CR RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2625 1451 113 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2625 1451 114 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2625 1451 115 PRODUCT. (N,XA) D-D EMISSION DATA USED TO BENCHMARK THE 2625 1451 116 CALCULATIONS. 2625 1451 117 12-51 THROUGH 12-57 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2625 1451 118 12-102 (N,G) CAPTURE; BELOW 1 MEV FROM ENDF/B-V FOR NAT FE, BUT 2625 1451 119 ADJUSTED FOR ENERGY BALANCE. ABOVE 1 MEV FROM 2625 1451 120 TNG CALCULATIONS. 2625 1451 121 14-51 THROUGH 14-57 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2625 1451 122 ASSUMED TO BE ISOTROPIC. 2625 1451 123 15-102 (N,G) CAPTURE; AS IN 12-102 2625 1451 124 2625 1451 125 -------------------------------------------------------------- 2625 1451 126 UNCERTAINTY FILES 2625 1451 127 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2625 1451 128 REQUIRED BY ENDF/B-VI. 2625 1451 129 2625 1451 130 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2625 1451 131 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2625 1451 132 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2625 1451 133 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2625 1451 134 20 MEV THE FILES ARE DERIVED. 2625 1451 135 33-3 FROM 1.E-5 TO 700 KEV UNCERTAINTIES ARE DERIVED. FROM 7002625 1451 136 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82625 1451 137 33-4 UNCERTAINTIES ARE ALL DERIVED. 2625 1451 138 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG 2625 1451 139 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2625 1451 140 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2625 1451 141 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2625 1451 142 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2625 1451 143 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2625 1451 144 ENERGIES, AND CALCULATED RESULTS ABOVE 700 KEV. 2625 1451 145 33-103 (N,P) COVARIANCES WERE TAKEN FROM THE GLUCS (8) 2625 1451 146 CALCULATION IN WHICH THIS REACTION WAS STUDIED 2625 1451 147 SIMULTANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2625 1451 148 SECTIONS (9). 2625 1451 149 33-104 UNCERTAINTIES ESTIMATED FROM DATA. 2625 1451 150 33-107 UNCERTAINTIES ESTIMATED FROM DATA. 2625 1451 151 2625 1451 152 REFERENCES: 2625 1451 153 (1) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2625 1451 154 COLORADO, UNPUBLISHED (1972). 2625 1451 155 (2) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2625 1451 156 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2625 1451 157 MOMENTUM," ORNL/TM-7042 (1980), AND NSE 100, 61 (1988). 2625 1451 158 (3) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2625 1451 159 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2625 1451 160 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2625 1451 161 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2625 1451 162 NATIONAL LAB. 2625 1451 163 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2625 1451 164 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2625 1451 165 (5) S. F. MUGHABGHAB, RESONANCE PARAMETERS AND THERMAL 2625 1451 166 CROSS SECTIONS, ACADEMIC PRESS, 1981. 2625 1451 167 (6) B. J. ALLEN, GEEL CONFERENCE, 1977. 2625 1451 168 (7) P.T. GUENTHER, D.L. SMITH, A.B. SMITH, AND J.F. WHALEN, ANN. 2625 1451 169 NUCL. ENERGY, 13 (11), 601-610 (1986). 2625 1451 170 (8) D.M. HETRICK AND C.Y. FU, "GLUCS: A GENERALIZED LEAST SQUARES2625 1451 171 PROGRAM FOR UPDATING CROSS SECTION EVALUATIONS WITH 2625 1451 172 CORRELATED DATA SETS," ORNL/TM-7341, ENDF-303 (OCT,1980). 2625 1451 173 (9) C.Y. FU AND D.M. HETRICK, "EXPERIENCE IN USING THE 2625 1451 174 COVARIANCES OF SOME ENDF/B-V DOSIMETRY CROSS SECTIONS: 2625 1451 175 PROPOSED IMPROVEMENTS AND ADDITIONS OF CROSS-REACTION 2625 1451 176 COVARIANCES," PROC. FOURTH ASTM-EURATOM SYMP. ON REACTOR 2625 1451 177 DOSIMETRY, GAITHERSBURG, MARYLAND, MARCH 22-26,1982, P877, 2625 1451 178 US NATIONAL BUREAU OF STANDARDS. 2625 1451 179 (10) S.M. GRIMES, R.C. HAIGHT, K.R. ALVAR, H.H. BARSCHALL, AND 2625 1451 180 R.R. BORCHERS, PHYS. 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779 262533 0 780 2.605400+4 5.347600+1 0 0 0 1262533107 781 0.000000+0 0.000000+0 0 107 0 4262533107 782 0.000000+0 0.000000+0 0 0 6 3262533107 783 1.000000-5 0.000000+0 3.000000+6 1.000000-8 2.000000+7 0.000000+0262533107 784 0.000000+0 0.000000+0 0 1 4 2262533107 785 1.000000-5 5.000000-3 2.000000+7 0.000000+0 0.000000+0 0.000000+0262533107 786 0.000000+0 0.000000+0 0 1 18 9262533107 787 1.000000-5 4.500000-3 4.000000+6 4.500000-3 6.000000+6 4.500000-3262533107 788 8.000000+6 4.500000-3 1.000000+7 4.500000-3 1.200000+7 4.500000-3262533107 789 1.400000+7 4.500000-3 1.600000+7 4.500000-3 2.000000+7 0.000000+0262533107 790 0.000000+0 0.000000+0 0 8 18 9262533107 791 1.000000-5 0.000000+0 4.000000+6 1.12500-11 6.000000+6 4.802000-8262533107 792 8.000000+6 6.125000-7 1.000000+7 1.518000-6 1.200000+7 2.592000-6262533107 793 1.400000+7 3.685100-6 1.600000+7 3.689400-6 2.000000+7 0.000000+0262533107 794 262533 0 795 2625 0 0 796 0 0 0 797 2.605600+4 5.545400+1 -1 0 0 12631 1451 1 0.000000+0 0.000000+0 0 0 0 62631 1451 2 1.000000+0 0.000000+0 0 0 10 62631 1451 3 0.000000+0 0.000000+0 0 0 178 52631 1451 4 26-FE- 56 ORNL EVAL-MAR89 FU, C.PEREY, HETRICK, F.PEREY 2631 1451 5 ORNL/TM-9964(1986) DIST-APR90 900413 2631 1451 6 ----ENDF/B-VI MATERIAL 2631 REVISION 0 2631 1451 7 -----INCIDENT NEUTRON DATA 2631 1451 8 ------ENDF-6 FORMAT 2631 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2631 1451 10 ACTIVATION I 2631 1451 11 ******************************************************************2631 1451 12 2631 1451 13 ORNL-4617(PE71) DESCRIBES ENDF/B-3. MAJOR REVISIONS FOR ENDF 2631 1451 14 /B-4 AND -5 ARE SUMMARIZED IN ORNL/TM-7523(FU80) AND ORNL/TM-8283 2631 1451 15 (FU82). THE PRESENT EVALUATION IS BASED ON THE CALCULATIONS 2631 1451 16 DESCRIBED IN ORNL/TM-9964(FU86). THE MAJOR IMPROVEMENTS OVER 2631 1451 17 ENDF-5 MOD3 ARE: 2631 1451 18 1. EVALUATION IS NOW ISOTOPIC. 2631 1451 19 2. ANALYSIS IS BASED ON A NEW TNG CODE MUCH IMPROVED OVER 2631 1451 20 THE VERSION USED FOR ENDF/B-5 FOR CALCULATING ENERGY-ANGLE 2631 1451 21 CORRELATED SPECTRA. 2631 1451 22 3. RESONANCE PARAMETERS ARE EXTENDED FROM 400 KEV TO 850 KEV 2631 1451 23 (PE89). 2631 1451 24 4. NEW DATA SETS (PA88,LA85,MA83,TA83,FU82,FR80,AR80,GR79, 2631 1451 25 HA89) ARE INCORPORATED. 2631 1451 26 5. INTEGRAL RESULTS (MA85,PA85,CR76,JO75) ARE CONSIDERED FOR 2631 1451 27 THE (N,N') EVALUATION ABOVE 3 MEV. 2631 1451 28 6. GAMMA-RAY PRODUCTION CROSS SECTIONS AND SPECTRA ARE GIVEN 2631 1451 29 FOR EACH REACTION,INCLUDING MT = 51-75, INSTEAD OF FOR THE 2631 1451 30 NONELASTIC. 2631 1451 31 7. RECOIL SPECTRA ARE GIVEN IN FILE-6. 2631 1451 32 8. CHARGED PARTICLE SPECTRA ARE GIVEN. 2631 1451 33 2631 1451 34 THE FOLLOWING DESCRIPTION FOR EACH FILE AND SECTION IS FOR 2631 1451 35 ENDF/B-VI: 2631 1451 36 2631 1451 37 FILE 2 RESONANCE PARAMETERS 2631 1451 38 REICH-MOORE PARAMETERS ARE GIVEN IN THE ENERGY 2631 1451 39 RANGE FROM 1.E-5 EV TO 850 KEV (PE88). 2631 1451 40 FILE 3 NEUTRON CROSS SECTIONS 2631 1451 41 SECTION 1 TOTAL INTERACTION 2631 1451 42 850 KEV TO 2 MEV -- HA89 FOR FE-56 2631 1451 43 2 MEV TO 20 MEV -- ENDF/B-V DATA FOR NATURAL FE USED 2631 1451 44 SECTION 2 ELASTIC SCATTERING 2631 1451 45 DERIVED BY SUBTRACTING THE NON-ELASTIC CROSS SECTION FROM THE 2631 1451 46 TOTAL CROSS SECTION. 2631 1451 47 SECTION 3 NON-ELASTIC INTERACTION 2631 1451 48 SUM OF ALL REACTION CROSS SECTIONS DESCRIBED BELOW. 2631 1451 49 SECTION 4 TOTAL INELASTIC SCATTERING 2631 1451 50 DERIVED BY ADDING INELASTIC SCATTERING CROSS SECTIONS FOR 2631 1451 51 EXCITING DISCRETE LEVELS AND THE CONTINUUM. 2631 1451 52 SECTION 16 N,2N REACTION -- SA71, FR80 2631 1451 53 SECTION 22 N,NA REACTION -- GR79 2631 1451 54 SECTION 28 N,NP REACTION -- GR79, AL61 2631 1451 55 SECTION 51 INELASTIC SCATTERING EXCITING FIRST LEVEL IN FE-56 2631 1451 56 .8611 MEV TO 1.5 MEV -- VO71,KI77. 2631 1451 57 1.5 MEV TO 2.122 MEV -- GI65 VO71 2631 1451 58 2.122 MEV TO 20 MEV -- BA66 KI70 MA71 RA70 PE69 SM73 2631 1451 59 SECTION 52 THROUGH 75 -- INELASTIC SCATTERING EXCITING LEVELS 2631 1451 60 BA66 MA71 RA70 KI70 2631 1451 61 SECTION 91 INELASTIC SCATTERING EXCITING THE CONTINUUM 2631 1451 62 GO66 KI70 KA73 BO63 SC65 CL72 MA69 HE75 TA83 PA8 2631 1451 63 SECTION 102 RADIATIVE CAPTURE -- HO69 ST70 GA76 AL76 LE76 2631 1451 64 1.E-5 EV TO 400 KEV -- COMPLETELY FROM RESONANCES 2631 1451 65 400 KEV TO 850 KEV -- COMBINATION OF RESONANCES AND FILE 3 2631 1451 66 850 KEV TO 20 MEV -- COMBINATION OF DATA AND CALCULATION 2631 1451 67 SECTION 103 N,P REACTION 2631 1451 68 LEAST-SQUARES ANALYSIS OF MANY DATA AND RATIOS (FU82) 2631 1451 69 UPDATED IN 1989 TO INCLUDE ENDF/B-VI STANDARDS 2631 1451 70 SECTION 104 N,D REACTION -- (AR80). 2631 1451 71 SECTION 105 N,T REACTION -- (AR80). 2631 1451 72 SECTION 106 N,HE-3 REACTION -- (AR80). 2631 1451 73 SECTION 107 N,A REACTION -- GR79,KI72 2631 1451 74 FILE 4 ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS 2631 1451 75 ALL DISTRIBUTIONS IN FILE 4 ARE GIVEN IN THE CENTER OF MASS 2631 1451 76 SYSTEM IN THE LEGENDRE POLYNOMIAL REPRESENTATION. 2631 1451 77 SECTION 2 ELASTIC SCATTERING 2631 1451 78 .00001 EV TO 1.23 MEV -- BA68 CO63 KO63 PA64,KP77 2631 1451 79 1.23 MEV TO 4 MEV -- BA68 BE56 BE66 BO59 CR69 HO68,KP77 2631 1451 80 4 MEV TO 20 MEV -- BA68 KI70 PE70 2631 1451 81 SECTION 51 INELASTIC SCATTERING EXCITING FIRST LEVEL IN FE-56 2631 1451 82 BA66 GIL65 KI70 RA70 2631 1451 83 SECTION 52 THROUGH 75 -- INELASTIC SCATTERING EXCITING LEVELS 2631 1451 84 BA66 KI70 RA70 MA71 2631 1451 85 FILE 6 ENERGY-ANGLE DISTRIBUTIONS OF SECONDARY PARTICLES, RECOILS,2631 1451 86 AND GAMMA RAYS -- ALL SPECTRA, INCLUDING RECOILS, ARE BASED2631 1451 87 ON TNG (FU88) ANALYSIS OF THE DATA GIVEN BELOW AND ARE 2631 1451 88 GIVEN IN THE LAB SYSTEM 2631 1451 89 SECTION 16 N,2N REACTION 2631 1451 90 FOR NEUTRON: SA71, HE75, KA72, TA83, PA88 2631 1451 91 FOR GAMMA RAYS: DA70, DI73, CH76 2631 1451 92 SECTION 22 N,NA REACTION -- AS FOR (N,2N) 2631 1451 93 SECTION 28 N,NP REACTION -- AS FOR (N,2N) 2631 1451 94 SECTION 91 INELASTIC SCATTERING EXCITING THE CONTINUUM 2631 1451 95 FOR NEUTRONS: KI70 MA69 PE69 BO63 SC65 KA72 CL72 HA73 HE75 2631 1451 96 TA88 PA88 2631 1451 97 FOR GAMMA RAYS: DA70 DI73 CH76 LA85 2631 1451 98 SECTION 103 (N,P) REACTION 2631 1451 99 FOR PROTON: GR79 2631 1451 100 SECTION 107 (N,A) REACTION 2631 1451 101 FOR ALPHAS: GR79 2631 1451 102 FILE 12 MULTIPLICITIES OF GAMMA RAYS PRODUCED BY NEUTRON REACTIONS2631 1451 103 SECTION 51-75 INELASTIC SCATTERING EXCITING DISCRETE LEVELS 2631 1451 104 FROM BRANCHING RATIOS USED IN THE TNG ANALYSIS OF DA70,DI73, 2631 1451 105 CH76, LA85 2631 1451 106 SECTION 102 RADIATIVE CAPTURE 2631 1451 107 FROM EVALUATION BY WHITE, FU, AND YOST (WH73) 2631 1451 108 THESE GAMMA RAYS ARE REPRESENTATIVE OF NEUTRON ENERGY RANGES 2631 1451 109 AND EACH RANGE CONTAIN CONTRIBUTIONS OF S- AND P-WAVE 2631 1451 110 COMPONENTS OF FE-54 AND FE-56. THESE RESULTS ARE RETAINED 2631 1451 111 HERE AS WELL AS IN THE EVALUATIONS FOR FE-54, -57, AND -58. 2631 1451 112 FILE 14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA RAYS 2631 1451 113 SECTIONS 51-75 AND 102 -- ASSUMED ISOTROPIC. 2631 1451 114 FILE 15 ENERGY DISTRIBUTIONS OF SECONDARY GAMMA RAYS 2631 1451 115 SECTION 102 RADIATIVE CAPTURE (WH73) 2631 1451 116 FILE 33 COVARIANCES FOR FILE-3 DATA 2631 1451 117 SECTION 103 WAS FROM GLUCS RUN OF 1989 (SEE 3-103) 2631 1451 118 2631 1451 119 REFERENCES 2631 1451 120 AL61 D. L. ALLAN, NUCL. PHYS. 24, 274(1961). 2631 1451 121 AL76 B.J.ALLEN ET AL.NUCL. PHYS. A269,408(1976). 2631 1451 122 AR80 E.D.ARTHUR AND P.G.YOUNG, LA-8626 (1980). 2631 1451 123 BA66 R. H. BASSEL ET. AL., COMPUTER CODE JULIE, ORNL(1966). 2631 1451 124 BA68 E. BARNARD ET. AL., PEL-180, PELINDABA, PRETORIA(1968). 2631 1451 125 BE56 J. R. BEYSTER ET. AL., PHYS. REV. 104, 1319(1956). 2631 1451 126 BE66 R. L. BECKER ET. AL., NUCL. PHYS. 89,154(1966). 2631 1451 127 BO59 N. A. 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SHIBATA, COMPUTER CODE TNG, ORNL (TO BE 2631 1451 142 PUBLISHED). 2631 1451 143 GA76 D.I.GARBER AND R.R.KINSEY,BNL-325,THIRD EDITION,VOL. 2(1976)2631 1451 144 GI65 W. B. GILBOY AND J. B. TOWLE, NUCL. PHYS. 64, 130(1965). 2631 1451 145 GR79 S. M. GRIMES ET AL., PHYS.REV. C19, 2127 (1979). 2631 1451 146 HA89 J. A. HARVEY, ORNL, PRIVATE COMMUNICATION (1989). 2631 1451 147 HA73 L. F. HANSEN ET. AL., NSE 51, 278(1973). 2631 1451 148 HE75 D. HERMSDORF ET AL., ZFK-277 (1975). 2631 1451 149 HO68 B. HOLMQVIST, ARKIV FYSIK 38, 403(1968). 2631 1451 150 HO69 R. W. HOCKENBURY ET. AL., PHYS. REV. 178, 1746(1969). 2631 1451 151 JO75 R. H. JOHNSON ET AL., TRANS. AM. NUCL. SOC. 22, 799 (1975). 2631 1451 152 KA72 J. L. KAMMERDIENER, UCRL-51232(1972). 2631 1451 153 KI70 W. E. KINNEY AND F. G. PEREY, ORNL-4515(1970). 2631 1451 154 KI72 G. J. KIROUAC AND C. J. SLAVIK, PRIVATE COMMUNICATION(1972).2631 1451 155 KI73 W. E. KINNEY AND F. G. PEREY, ORNL-4907(1973). 2631 1451 156 KI77 W.E.KINNEY AND F.G.PEREY,NUCL.SCI.ENGR. 63,418(1977). 2631 1451 157 KO63 I. O. KORZH AND M. T. SKYLAR, UKR. FIZ. ZH. 8, 1389(1963). 2631 1451 158 KP77 W.E.KINNEY AND F.G.PEREY,PRIVATE COMMUNICATION(1977). 2631 1451 159 LA85 D. C. LARSON, INT. CONF. NUCL. DATA., SANTA FE (1985). 2631 1451 160 LE76 C.LE REGOLEUR ET AL.,CEA-R-4788(1976) 2631 1451 161 MA69 S. C. MATHUR ET. AL., PHYS. REV. 186, 1038(1969). 2631 1451 162 MA71 G. S. MANI, NUCL. PHYS. A165, 225(1971). 2631 1451 163 MA83 A. MARCINKOWSKI ET AL., NUCL. SCI. ENG. 83,13 (1983). 2631 1451 164 MA85 R. E. MAERKER ET AL., CONF. NUCL. DATA, SANTA FE (1985). 2631 1451 165 PA64 M. V. PASECHNIK ET. AL., AT. EN. USSR 16, 207(1964). 2631 1451 166 PA85 J. V. PACE, ORNL, PRIVATE COMM. (1985). 2631 1451 167 PA88 A, PAVLIK AND H. VONACH, UNIV. WIEN (TO BE PUBLISHED). 2631 1451 168 PE69 R. J. PETERSON, ANNALS OF PHYSICS 53, 40(1969). 2631 1451 169 PE70 F. G. 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AL., NSE 51, 496(1973). 2631 1451 181 2631 1451 182 1 451 187 12631 1451 183 3 16 12 12631 1451 184 3 103 19 12631 1451 185 33 16 14 12631 1451 186 33 103 125 12631 1451 187 2631 1 0 188 2631 0 0 189 2.605600+4 5.545400+1 0 0 0 02631 3 16 190 -1.120000+7-1.120000+7 0 0 1 262631 3 16 191 26 2 0 0 0 02631 3 16 192 1.140200+7 0.000000+0 1.150000+7 2.240400-3 1.160000+7 7.593600-32631 3 16 193 1.170000+7 1.521000-2 1.180000+7 2.504200-2 1.190000+7 3.747700-22631 3 16 194 1.200000+7 4.993300-2 1.220000+7 7.865300-2 1.240000+7 1.115900-12631 3 16 195 1.260000+7 1.465600-1 1.280000+7 1.881600-1 1.300000+7 2.229300-12631 3 16 196 1.350000+7 3.176800-1 1.400000+7 4.020400-1 1.450000+7 4.678000-12631 3 16 197 1.500000+7 5.198900-1 1.550000+7 5.565200-1 1.600000+7 5.827100-12631 3 16 198 1.650000+7 6.010700-1 1.700000+7 6.107800-1 1.750000+7 6.114500-12631 3 16 199 1.800000+7 6.099200-1 1.850000+7 6.047900-1 1.900000+7 5.975900-12631 3 16 200 1.950000+7 5.878800-1 2.000000+7 5.754000-1 0.000000+0 0.000000+02631 3 16 201 2631 3 0 202 2.605600+4 5.545400+1 0 0 0 02631 3103 203 -2.913000+6-2.913000+6 0 0 3 472631 3103 204 2 2 12 4 47 22631 3103 205 2.965500+6 0.000000+0 3.000000+6 7.001900-9 4.000000+6 6.001600-62631 3103 206 4.250000+6 3.201000-5 4.500000+6 1.403800-4 4.600000+6 2.406500-42631 3103 207 4.800000+6 5.775600-4 5.000000+6 1.069500-3 5.250000+6 2.294100-32631 3103 208 5.500000+6 4.798200-3 5.750000+6 8.479100-3 6.000000+6 1.273100-22631 3103 209 6.200000+6 1.645300-2 6.400000+6 1.917500-2 6.600000+6 2.375600-22631 3103 210 6.800000+6 2.758300-2 7.000000+6 2.728100-2 7.500000+6 3.534700-22631 3103 211 8.000000+6 4.173200-2 8.500000+6 4.767000-2 9.000000+6 5.514500-22631 3103 212 9.500000+6 5.907100-2 1.000000+7 6.690700-2 1.050000+7 7.572400-22631 3103 213 1.100000+7 8.241000-2 1.150000+7 9.069500-2 1.200000+7 1.033500-12631 3103 214 1.220000+7 1.056500-1 1.240000+7 1.093000-1 1.260000+7 1.116300-12631 3103 215 1.280000+7 1.143600-1 1.300000+7 1.152300-1 1.340000+7 1.169200-12631 3103 216 1.380000+7 1.166700-1 1.420000+7 1.135900-1 1.460000+7 1.093400-12631 3103 217 1.500000+7 1.042200-1 1.550000+7 9.512100-2 1.600000+7 8.625100-22631 3103 218 1.650000+7 7.978800-2 1.700000+7 7.162500-2 1.750000+7 6.627600-22631 3103 219 1.800000+7 6.129600-2 1.850000+7 5.681200-2 1.900000+7 5.264800-22631 3103 220 1.950000+7 5.096800-2 2.000000+7 5.055300-2 0.000000+0 0.000000+02631 3103 221 2631 3 0 222 2631 0 0 223 2.605600+4 5.545400+1 0 0 0 1263133 16 224 0.000000+0 0.000000+0 0 16 0 4263133 16 225 0.000000+0 0.000000+0 0 0 6 3263133 16 226 1.000000-5 0.000000+0 1.140200+7 4.000000-5 2.000000+7 0.000000+0263133 16 227 0.000000+0 0.000000+0 0 1 6 3263133 16 228 1.000000-5 0.000000+0 1.140200+7 5.000000-3 2.000000+7 0.000000+0263133 16 229 0.000000+0 0.000000+0 0 1 14 7263133 16 230 1.000000-5 0.000000+0 1.140200+7 4.500000-3 1.200000+7 4.500000-3263133 16 231 1.400000+7 4.500000-3 1.600000+7 4.500000-3 1.800000+7 4.500000-3263133 16 232 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0263133 16 233 0.000000+0 0.000000+0 0 8 14 7263133 16 234 1.000000-5 0.000000+0 1.140200+7 2.509700-9 1.200000+7 1.246700-6263133 16 235 1.400000+7 8.081800-5 1.600000+7 1.697800-4 1.800000+7 1.860000-4263133 16 236 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0263133 16 237 263133 0 238 2.605600+4 5.545400+1 0 0 0 1263133103 239 0.000000+0 0.000000+0 0 103 0 4263133103 240 0.000000+0 0.000000+0 1 5 406 28263133103 241 1.000000-5 2.965500+6 3.000000+6 4.500000+6 4.600000+6 4.800000+6263133103 242 5.000000+6 5.750000+6 6.000000+6 6.200000+6 6.400000+6 6.600000+6263133103 243 6.800000+6 8.000000+6 8.500000+6 9.000000+6 9.500000+6 1.100000+7263133103 244 1.200000+7 1.300000+7 1.340000+7 1.380000+7 1.500000+7 1.550000+7263133103 245 1.700000+7 1.750000+7 1.800000+7 2.000000+7 0.000000+0 0.000000+0263133103 246 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0263133103 247 0.000000+0 0.000000+0 0.000000+0 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1.20500-10 4.800000+6 3.13330-11 5.000000+6 1.478900-9263133103 350 5.250000+6 6.804700-9 5.500000+6 2.976700-8 5.750000+6 7.184900-9263133103 351 6.000000+6 8.839300-8 6.200000+6 1.639000-7 6.400000+6 6.500000-8263133103 352 6.600000+6 1.021900-7 6.800000+6 1.014400-7 7.000000+6 9.922900-8263133103 353 7.500000+6 1.665800-7 8.000000+6 2.011400-7 8.500000+6 1.840800-7263133103 354 9.000000+6 2.467200-7 9.500000+6 1.567000-7 1.000000+7 2.010300-7263133103 355 1.050000+7 2.575000-7 1.100000+7 6.640700-7 1.150000+7 8.043000-7263133103 356 1.200000+7 9.798800-7 1.220000+7 1.024000-6 1.240000+7 1.095900-6263133103 357 1.260000+7 1.143200-6 1.280000+7 1.199800-6 1.300000+7 1.341300-6263133103 358 1.340000+7 7.077800-7 1.380000+7 4.322200-7 1.420000+7 4.097000-7263133103 359 1.460000+7 3.796200-7 1.500000+7 3.562500-7 1.550000+7 9.255400-8263133103 360 1.600000+7 7.609800-8 1.650000+7 6.512000-8 1.700000+7 1.110900-7263133103 361 1.750000+7 1.203900-7 1.800000+7 5.679600-8 1.850000+7 4.879100-8263133103 362 1.900000+7 4.190100-8 1.950000+7 3.926900-8 2.000000+7 0.000000+0263133103 363 263133 0 364 2631 0 0 365 0 0 0 366 2.605800+4 5.743600+1 1 0 0 12637 1451 1 0.000000+0 0.000000+0 0 0 0 62637 1451 2 1.000000+0 0.000000+0 0 0 10 62637 1451 3 0.000000+0 0.000000+0 0 0 154 32637 1451 4 26-FE- 58 ORNL EVAL-NOV89 HETRICK,FU,N.M.LARSON 2637 1451 5 ORNL/TM- DIST-APR90 900417 2637 1451 6 ----ENDF/B-VI MATERIAL 2637 2637 1451 7 -----INCIDENT NEUTRON DATA 2637 1451 8 ------ENDF-6 FORMAT 2637 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2637 1451 10 ACTIVATION I 2637 1451 11 ******************************************************************2637 1451 12 THIS WORK EMPLOYED THE HAUSER-FESHBACH CODE TNG (1,2,3). 2637 1451 13 THE TNG CODE PROVIDES ENERGY AND ANGULAR DISTRIBUTIONS OF 2637 1451 14 PARTICLES EMITTED IN THE COMPOUND AND PRE-COMPOUND REACTIONS, 2637 1451 15 ENSURES CONSISTENCY AMONG ALL REACTIONS, AND MAINTAINS ENERGY 2637 1451 16 BALANCE. DETAILS PERTINENT TO THE CONTENTS OF THIS EVALUATION 2637 1451 17 WILL BE PUBLISHED AT A LATER DATE. 2637 1451 18 RESONANCE PARAMETERS AND THERMAL CAPTURE CROSS SECTION WERE 2637 1451 19 TAKEN FROM (4), AND ADJUSTED TO THE DATA OF BEER ET AL. (5) 2637 1451 20 THROUGH THE SAMMY CODE BY N.M. LARSON. SOME CAPTURE 2637 1451 21 WIDTHS WERE ADJUSTED DOWNWARD TO COMPROMISE WITH THE AVERAGED 2637 1451 22 DATA OF (6). AVERAGE CAPTURE DATA OF (7) WERE USED TO GENERATE 2637 1451 23 CAPTURE BACKGROUND BELOW 400 KEV AND FOR THE POINTWISE CROSS 2637 1451 24 SECTION'S FROM 400 KEV TO 2 MEV. THERMAL CAPTURE AND CAPTURE IN 2637 1451 25 THE 10.4 KEV RESONANCE WERE FURTHER ADJUSTED BY SAMMY TO AGREE 2637 1451 26 WITH THE ENDF/B-V DOSIMETRY EVALUATION (F. MANN ET AL.), WHICH WAS2637 1451 27 ADJUSTED TO AGREE WITH INTEGRAL DATA. LOW KEV SCATTERING 2637 1451 28 CROSS SECTIONS WERE BASED ON AP=0.72 GIVEN BY (8). 2637 1451 29 FOR TOTAL CROSS SECTIONS ABOVE 400 KEV AND CAPTURE CROSS 2637 1451 30 SECTIONS ABOVE 2 MEV, NATURAL FE DATA OF ENDF/B-V WERE USED FOR 2637 1451 31 THE PURPOSE OF MAKING SURE THAT THE TOTAL CROSS SECTION MINIMA 2637 1451 32 IN NAT FE IS MAINTAINED. 2637 1451 33 2637 1451 34 ----- DESCRIPTION OF FILES 2637 1451 35 (MF-MT) 2637 1451 36 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2637 1451 37 2-151 RESONANCE PARAMETERS; SEE ABOVE. 2637 1451 38 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2637 1451 39 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2637 1451 40 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2637 1451 41 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2637 1451 42 3-1 TOTAL CROSS SECTION; SEE ABOVE 2637 1451 43 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2637 1451 44 SUBTRACTING THE NONELASTIC FROM THE TOTAL. 2637 1451 45 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 3-28, 2637 1451 46 3-102, 3-103, AND 3-107. 2637 1451 47 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, AND 2637 1451 48 3-91. 2637 1451 49 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2637 1451 50 CODE (1,2,3). 2637 1451 51 3-22 (N,NA)+(N,AN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2637 1451 52 CODE (1,2,3). 2637 1451 53 3-28 (N,NP)+(N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2637 1451 54 CODE (1,2,3). 2637 1451 55 3-51 TO 3-52 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2637 1451 56 FROM TNG (1,2,3). 2637 1451 57 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2637 1451 58 CALCULATED). 2637 1451 59 3-102 (N,G) CAPTURE CROSS SECTION; SEE ABOVE 2637 1451 60 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2637 1451 61 CODE (1,2,3), BUT RENORMALIZED TO FIT THE DATA OF DYER 2637 1451 62 & HAMILTON (9) AND BAHAL & PEPELNIK (10) AT EN=14.5 MEV. 2637 1451 63 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2637 1451 64 TNG CODE (1,2,3), BUT RENORMALIZED TO FIT THE DATA OF 2637 1451 65 KNEFF ET AL. (11) AT EN = 14.8 MEV. 2637 1451 66 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2637 1451 67 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2637 1451 68 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2637 1451 69 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2637 1451 70 PARAMETERS IN 2/151. 2637 1451 71 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2637 1451 72 NEUTRON AND 57FE RESIDUAL, AND ENERGY DEPENDENT YIELD 2637 1451 73 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2637 1451 74 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2637 1451 75 EACH PRODUCT. ISOTROPY IS ASSUMED. 2637 1451 76 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2637 1451 77 NEUTRON, ALPHA, AND 54CR RESIDUAL, AND ENERGY DEPENDENT 2637 1451 78 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2637 1451 79 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2637 1451 80 FOR EACH PRODUCT (ISOTROPY IS ASSUMED). 2637 1451 81 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2637 1451 82 NEUTRON, P, AND 57MN RESIDUAL, AND ENERGY DEPENDENT YIELD 2637 1451 83 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2637 1451 84 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2637 1451 85 EACH PRODUCT (ISOTROPY IS ASSUMED). 2637 1451 86 6-51 THROUGH 6-52 INELASTIC SCATTERING EXCITING LEVELS; 2637 1451 87 ASSUMED ISOTROPIC. 2637 1451 88 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2637 1451 89 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 58FE 2637 1451 90 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2637 1451 91 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2637 1451 92 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2637 1451 93 FOR EACH. ISOTROPY IS ASSUMED. 2637 1451 94 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2637 1451 95 AND 58MN RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2637 1451 96 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2637 1451 97 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2637 1451 98 PRODUCT. ISOTROPY IS ASSUMED. 2637 1451 99 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2637 1451 100 AND 55CR RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2637 1451 101 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2637 1451 102 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2637 1451 103 PRODUCT. ISOTROPY IS ASSUMED. 2637 1451 104 12-51 THROUGH 12-52 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2637 1451 105 12-102 (N,G) CAPTURE; BELOW 1 MEV FROM ENDF/B-V FOR NAT FE, BUT 2637 1451 106 ADJUSTED FOR ENERGY BALANCE. ABOVE 1 MEV FROM TNG 2637 1451 107 CALCULATIONS. 2637 1451 108 14-51 THROUGH 14-52 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2637 1451 109 ASSUMED TO BE ISOTROPIC. 2637 1451 110 15-102 (N,G) CAPTURE; AS IN 12-102. 2637 1451 111 2637 1451 112 -------------------------------------------------------------- 2637 1451 113 UNCERTAINTY FILES 2637 1451 114 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2637 1451 115 REQUIRED BY ENDF/B-VI. 2637 1451 116 2637 1451 117 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2637 1451 118 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2637 1451 119 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2637 1451 120 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2637 1451 121 20 MEV THE FILES ARE DERIVED. 2637 1451 122 33-3 FROM 1.E-5 TO 400 KEV UNCERTAINTIES ARE DERIVED. FROM 4002637 1451 123 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82637 1451 124 33-4 UNCERTAINTIES ARE ALL DERIVED. 2637 1451 125 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG 2637 1451 126 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2637 1451 127 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2637 1451 128 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2637 1451 129 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2637 1451 130 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2637 1451 131 ENERGIES, DATA OF (7) FOR ENERGIES UP TO 2.0 MEV, AND 2637 1451 132 TNG AT ENERGIES ABOVE 2.0 MEV. 2637 1451 133 33-103 (N,P) COVARIANCES WERE ESTIMATED FROM DATA AND TNG. 2637 1451 134 33-107 UNCERTAINTIES ESTIMATED FROM DATA AND TNG. 2637 1451 135 2637 1451 136 REFERENCES: 2637 1451 137 (1) C.Y. FU, NSE 100, 61 (1988). 2637 1451 138 (2) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2637 1451 139 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2637 1451 140 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2637 1451 141 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2637 1451 142 NATIONAL LAB. 2637 1451 143 (3) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2637 1451 144 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2637 1451 145 (4) S. F. MUGHABGHAB ET AL, NEUTRON RESONANCE PARAMETERS AND 2637 1451 146 THERMAL CROSS SECTIONS, ACADEMIC PRESS, 1981 2637 1451 147 (5) H. BEER, LY DI HONG, AND F. KAPPELER, NUCL. SCI. ENG., 67, 2637 1451 148 184-189 (1978). 2637 1451 149 (6) B. J. ALLEN, J. OF PHYS. G6,381 (1980). 2637 1451 150 (7) TROFIMOV, ATOMNAYA ENERGIYA 58, 278 (1985). DATA TAKEN 2637 1451 151 FROM V. MCLANE, NEUTRON CROSS SECTION CURVES 2637 1451 152 (8) J. B. GARG, PHYS. REV. C18, 1141 (1978). 2637 1451 153 (9) N.C. DYER AND J.H. HAMILTON, J. INORG. NUCL. CHEM., 34, 1119-2637 1451 154 1120 (1972). 2637 1451 155 (10) B.M. BAHAL AND R. PEPELNIK, REPORT GKSS-84-E (1984). 2637 1451 156 (11) D.W. KNEFF, B.M. OLIVER, AND H. FARRAR,IV, NUCL. SCI. ENG., 2637 1451 157 92, 491-524 (1986). 2637 1451 158 1 451 161 12637 1451 159 2 151 75 12637 1451 160 3 102 11 12637 1451 161 2637 1 0 162 2637 0 0 163 2.605800+4 5.743600+1 0 0 1 02637 2151 164 2.605800+4 1.000000+0 0 0 1 02637 2151 165 1.000000-5 4.000000+5 1 3 0 12637 2151 166 0.000000+0 7.200000-1 1 0 3 32637 2151 167 5.743600+1 7.200000-1 0 0 96 162637 2151 168 -4.000000+4 5.000000-1 7.995702+3 6.495400+0 0.000000+0 0.000000+02637 2151 169 -9.998600+1 5.000000-1 1.095900-2 1.096400-2 0.000000+0 0.000000+02637 2151 170 1.038000+4 5.000000-1 2.482000+2 1.246400+0 0.000000+0 0.000000+02637 2151 171 4.355000+4 5.000000-1 6.130400+3 2.200000+0 0.000000+0 0.000000+02637 2151 172 6.720000+4 5.000000-1 8.648700+2 3.000000-1 0.000000+0 0.000000+02637 2151 173 9.149900+4 5.000000-1 9.095600+3 7.740000+0 0.000000+0 0.000000+02637 2151 174 1.212100+5 5.000000-1 2.398900+3 2.300000+0 0.000000+0 0.000000+02637 2151 175 1.786900+5 5.000000-1 2.676800+3 3.000000+0 0.000000+0 0.000000+02637 2151 176 2.414300+5 5.000000-1 1.475300+4 3.000000+0 0.000000+0 0.000000+02637 2151 177 2.650000+5 5.000000-1 1.094800+4 3.000000+0 0.000000+0 0.000000+02637 2151 178 3.102000+5 5.000000-1 4.499400+3 3.000000+0 0.000000+0 0.000000+02637 2151 179 3.119000+5 5.000000-1 3.650100+2 3.000000+0 0.000000+0 0.000000+02637 2151 180 3.238200+5 5.000000-1 3.817900+2 3.000000+0 0.000000+0 0.000000+02637 2151 181 3.481100+5 5.000000-1 4.292400+3 3.000000+0 0.000000+0 0.000000+02637 2151 182 5.000000+5 5.000000-1 1.160300+5 3.000000+0 0.000000+0 0.000000+02637 2151 183 1.000000+6 5.000000-1 1.148600+4 3.000000+0 0.000000+0 0.000000+02637 2151 184 5.743600+1 7.200000-1 1 0 264 442637 2151 185 2.300000+2 1.500000+0 1.000000-3 4.000000-1 0.000000+0 0.000000+02637 2151 186 3.590000+2 1.500000+0 1.100000-2 4.000000-1 0.000000+0 0.000000+02637 2151 187 2.820000+3 5.000000-1 2.000000-3 4.000000-1 0.000000+0 0.000000+02637 2151 188 6.199000+3 1.500000+0 1.000000+0 1.000000-1 0.000000+0 0.000000+02637 2151 189 1.874000+4 1.500000+0 1.602300-1 2.000000-1 0.000000+0 0.000000+02637 2151 190 1.935000+4 1.500000+0 2.816700-1 1.696000-1 0.000000+0 0.000000+02637 2151 191 2.607000+4 5.000000-1 5.608600+0 2.000000-1 0.000000+0 0.000000+02637 2151 192 3.150000+4 1.500000+0 6.000000-1 2.000000-1 0.000000+0 0.000000+02637 2151 193 3.465000+4 5.000000-1 1.674300+1 2.000000-1 0.000000+0 0.000000+02637 2151 194 3.766000+4 5.000000-1 2.831400+1 4.000000-1 0.000000+0 0.000000+02637 2151 195 4.198000+4 1.500000+0 1.740500+0 1.000000+0 0.000000+0 0.000000+02637 2151 196 4.594000+4 1.500000+0 1.299900-1 1.000000+0 0.000000+0 0.000000+02637 2151 197 5.490000+4 5.000000-1 5.036500+1 4.000000-1 0.000000+0 0.000000+02637 2151 198 6.200000+4 5.000000-1 2.262200+1 1.000000+0 0.000000+0 0.000000+02637 2151 199 6.840000+4 1.500000+0 3.177600+0 3.000000-1 0.000000+0 0.000000+02637 2151 200 6.858000+4 1.500000+0 5.020700+0 2.000000-1 0.000000+0 0.000000+02637 2151 201 7.344000+4 1.500000+0 2.390000+0 3.000000-1 0.000000+0 0.000000+02637 2151 202 7.934000+4 5.000000-1 1.375100+1 2.000000-1 0.000000+0 0.000000+02637 2151 203 8.848500+4 5.000000-1 1.034400+1 2.000000-1 0.000000+0 0.000000+02637 2151 204 9.173000+4 1.500000+0 1.040000+0 3.000000-1 0.000000+0 0.000000+02637 2151 205 1.031500+5 1.500000+0 2.270000+0 4.000000-1 0.000000+0 0.000000+02637 2151 206 1.092600+5 5.000000-1 9.951800-1 4.000000-1 0.000000+0 0.000000+02637 2151 207 1.120000+5 1.500000+0 8.035600+0 1.000000+0 0.000000+0 0.000000+02637 2151 208 1.196000+5 1.500000+0 3.487900+0 4.000000-1 0.000000+0 0.000000+02637 2151 209 1.234200+5 1.500000+0 9.976500-3 4.000000-1 0.000000+0 0.000000+02637 2151 210 1.440000+5 1.500000+0 1.802100+1 4.000000-1 0.000000+0 0.000000+02637 2151 211 1.526500+5 1.500000+0 1.935700+2 2.700000+0 0.000000+0 0.000000+02637 2151 212 1.594200+5 1.500000+0 3.335400+1 4.000000-1 0.000000+0 0.000000+02637 2151 213 1.662200+5 5.000000-1 1.000000+1 4.000000-1 0.000000+0 0.000000+02637 2151 214 1.874000+5 1.500000+0 2.410000+1 4.000000-1 0.000000+0 0.000000+02637 2151 215 1.957000+5 1.500000+0 8.829800+0 4.000000-1 0.000000+0 0.000000+02637 2151 216 2.060300+5 5.000000-1 2.267700+1 4.000000-1 0.000000+0 0.000000+02637 2151 217 2.069000+5 1.500000+0 2.119400+1 4.000000-1 0.000000+0 0.000000+02637 2151 218 2.102000+5 1.500000+0 3.392700+0 4.000000-1 0.000000+0 0.000000+02637 2151 219 2.286400+5 1.500000+0 3.285500+1 4.000000-1 0.000000+0 0.000000+02637 2151 220 2.387900+5 5.000000-1 1.149400+2 4.000000-1 0.000000+0 0.000000+02637 2151 221 2.430000+5 1.500000+0 3.967800+1 4.000000-1 0.000000+0 0.000000+02637 2151 222 2.555700+5 1.500000+0 2.537900+1 4.000000-1 0.000000+0 0.000000+02637 2151 223 2.756000+5 5.000000-1 1.364800+2 4.000000-1 0.000000+0 0.000000+02637 2151 224 2.774000+5 1.500000+0 3.941300+1 4.000000-1 0.000000+0 0.000000+02637 2151 225 2.821300+5 1.500000+0 1.000000+1 4.000000-1 0.000000+0 0.000000+02637 2151 226 3.397500+5 1.500000+0 2.000000+2 4.000000-1 0.000000+0 0.000000+02637 2151 227 3.422300+5 5.000000-1 3.000000+2 4.000000-1 0.000000+0 0.000000+02637 2151 228 3.449200+5 1.500000+0 7.500000+1 4.000000-1 0.000000+0 0.000000+02637 2151 229 5.743600+1 7.200000-1 2 0 48 82637 2151 230 1.308800+5 1.500000+0 7.365100+1 1.800000+0 0.000000+0 0.000000+02637 2151 231 1.355900+5 1.500000+0 1.247100+1 4.000000-1 0.000000+0 0.000000+02637 2151 232 2.183200+5 1.500000+0 4.219500+1 4.000000-1 0.000000+0 0.000000+02637 2151 233 2.217300+5 1.500000+0 4.491900+1 4.000000-1 0.000000+0 0.000000+02637 2151 234 2.658000+5 1.500000+0 1.997300+1 4.000000-1 0.000000+0 0.000000+02637 2151 235 2.710600+5 1.500000+0 4.241400+1 4.000000-1 0.000000+0 0.000000+02637 2151 236 2.893800+5 1.500000+0 3.232100+1 4.000000-1 0.000000+0 0.000000+02637 2151 237 3.338000+5 1.500000+0 2.000000+2 4.000000-1 0.000000+0 0.000000+02637 2151 238 2637 2 0 239 2637 0 0 240 2.605800+4 5.743600+1 0 99 0 02637 3102 241 6.581000+6 6.581000+6 0 0 2 232637 3102 242 6 5 23 2 0 02637 3102 243 1.000000-5 3.120000+0 2.530000-2 4.600000-2 1.660000+2 7.660000-42637 3102 244 4.000000+3 7.660000-4 2.300000+4 1.000000-3 3.500000+5 1.000000-32637 3102 245 4.000000+5 1.500000-3 4.000000+5 1.520000-3 4.010000+5 3.200000-32637 3102 246 1.000000+6 2.700000-3 2.000000+6 2.520000-3 2.500000+6 1.800000-32637 3102 247 3.000000+6 1.090000-3 4.000000+6 8.600000-4 5.000000+6 7.500000-42637 3102 248 7.000000+6 6.600000-4 9.000000+6 6.300000-4 1.100000+7 6.400000-42637 3102 249 1.300000+7 7.200000-4 1.500000+7 8.700000-4 1.700000+7 1.000000-32637 3102 250 1.800000+7 1.000000-3 2.000000+7 9.000000-4 0.000000+0 0.000000+02637 3102 251 2637 3 0 252 2637 0 0 253 0 0 0 254 2.705900+4 5.842690+1 1 0 0 12725 1451 1 0.000000+0 0.000000+0 0 0 0 62725 1451 2 1.000000+0 0.000000+0 0 0 10 62725 1451 3 0.000000+0 0.000000+0 0 0 12 92725 1451 4 27-CO- 59 ANL EVAL-JUL89 A.+D.SMITH,P.GUENTHER,J.MEADOWS, 2725 1451 5 ANL/NDM-107 DIST-JAN90 891211 2725 1451 6 ----ENDF/B-VI MATERIAL 2725 2725 1451 7 -----INCIDENT NEUTRON DATA 2725 1451 8 ------ENDF-6 FORMAT 2725 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2725 1451 10 ACTIVATION I 2725 1451 11 ******************************************************************2725 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2725 1451 13 * * * * * * *2725 1451 14 R.LAWSON(ANL),R.HOWERTON(LLNL),M.SUGIMOTO(JAERI) 2725 1451 15 2725 1451 16 1 451 25 12725 1451 17 2 151 124 12725 1451 18 3 16 10 12725 1451 19 3 102 15 12725 1451 20 3 103 15 12725 1451 21 3 107 18 12725 1451 22 33 16 38 12725 1451 23 33 103 71 12725 1451 24 33 107 108 12725 1451 25 2725 1 0 26 2725 0 0 27 2.705900+4 5.842690+1 0 0 1 02725 2151 28 2.705900+4 1.000000+0 0 0 1 02725 2151 29 1.000000-5 1.000000+5 1 2 0 02725 2151 30 3.500000+0 6.200000-1 0 0 2 02725 2151 31 5.842700+1 0.000000+0 0 0 702 1172725 2151 32 -5.000000+2 3.000000+0 4.819400+1 4.774700+1 4.470000-1 0.000000+02725 2151 33 -4.750000+2 4.000000+0 2.970600+0 2.523600+0 4.470000-1 0.000000+02725 2151 34 1.320000+2 4.000000+0 5.616700+0 5.146700+0 4.700000-1 0.000000+02725 2151 35 1.380000+3 3.000000+0 4.556000-1 5.600000-3 4.500000-1 0.000000+02725 2151 36 2.860000+3 3.000000+0 3.607100+0 3.497100+0 1.100000-1 0.000000+02725 2151 37 3.986000+3 4.000000+0 3.136700-1 1.066700-1 2.070000-1 0.000000+02725 2151 38 4.320000+3 4.000000+0 1.115100+2 1.111100+2 4.000000-1 0.000000+02725 2151 39 5.000000+3 3.000000+0 6.751900+2 6.742900+2 9.000000-1 0.000000+02725 2151 40 5.521000+3 4.000000+0 4.588900-1 8.888900-3 4.500000-1 0.000000+02725 2151 41 6.618000+3 4.000000+0 4.802200-1 3.022200-2 4.500000-1 0.000000+02725 2151 42 7.029000+3 3.000000+0 5.082900-1 5.828600-2 4.500000-1 0.000000+02725 2151 43 7.327000+3 4.000000+0 4.551600-1 5.155600-3 4.500000-1 0.000000+02725 2151 44 8.050000+3 3.000000+0 3.692600+1 3.657100+1 3.550000-1 0.000000+02725 2151 45 8.750000+3 4.000000+0 2.836700+0 2.666700+0 1.700000-1 0.000000+02725 2151 46 9.493000+3 3.000000+0 4.740000-1 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2.403100-3 2.399100-3272533107 431 2.383700-3 2.417900-3 2.388800-3 3.249000-3 3.251200-3 3.264300-3272533107 432 3.271800-3 3.223900-3 3.257500-3 3.844000-3 3.251200-3 3.253700-3272533107 433 3.256200-3 3.228300-3 4.761000-3 3.225000-3 3.275400-3 3.242300-3272533107 434 6.724000-3 3.229900-3 3.228300-3 1.020100-2 3.206700-3 1.612900-2272533107 435 272533 0 436 2725 0 0 437 0 0 0 438 2.805800+4 5.743800+1 1 0 0 12825 1451 1 0.000000+0 0.000000+0 0 0 0 62825 1451 2 1.000000+0 0.000000+0 0 0 10 62825 1451 3 0.000000+0 0.000000+0 0 0 225 132825 1451 4 28-NI- 58 ORNL EVAL-OCT89 LARSON, CM PEREY, HETRICK, FU 2825 1451 5 ORNL/TM10219,ENDF-344 DIST-APR90 900216 2825 1451 6 ----ENDF/B-VI MATERIAL 2825 2825 1451 7 -----INCIDENT NEUTRON DATA 2825 1451 8 ------ENDF-6 FORMAT 2825 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2825 1451 10 ACTIVATION I 2825 1451 11 ******************************************************************2825 1451 12 THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE 2825 1451 13 DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1) 2825 1451 14 AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES 2825 1451 15 ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE 2825 1451 16 COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL2825 1451 17 REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE 2825 1451 18 CONTENTS OF THIS EVALUATION AND EXTENSIVE COMPARISONS OF 2825 1451 19 CALCULATIONS WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5).2825 1451 20 2825 1451 21 ----- DESCRIPTION OF FILES 2825 1451 22 (MF-MT) 2825 1451 23 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2825 1451 24 2-151 RESONANCE PARAMETERS ARE USED EXCLUSIVELY TO PROVIDE THE 2825 1451 25 TOTAL, SCATTERING AND CAPTURE CROSS SECTIONS FROM 1.E-5 EV2825 1451 26 TO 812 KEV, EXCEPT FOR CAPTURE FROM 450-812 KEV. THE 2825 1451 27 RESONANCE PARAMETERS ARE TAKEN FROM AN 2825 1451 28 EXTENSIVE RESONANCE PARAMETER ANALYSIS OF TRANSMISSION, 2825 1451 29 SCATTERING AND CAPTURE DATA (6). NEGATIVE ENERGY 2825 1451 30 RESONANCES HAVE BEEN USED TO GIVE THE CORRECT THERMAL 2825 1451 31 VALUES. THE SCATTERING CROSS SECTION IS GIVEN COMPLETELY 2825 1451 32 BY THE RESONANCE PARAMETERS FROM 1.E-5 TO 812 KEV, BUT FOR2825 1451 33 THE CAPTURE CROSS SECTION, AVERAGE RESONANCE PARAMETERS 2825 1451 34 USED FROM 450 TO 812 KEV. THUS, THERE IS A BACKGROUND 2825 1451 35 CONTRIBUTION IN 3/102 FROM 450 TO 812 KEV TO ACCOUNT FOR 2825 1451 36 THE SMALL DIFFERENCE IN CAPTURE CROSS SECTION FROM THE 2825 1451 37 AVERAGE RESONANCE PARAMETERS AND THE AVERAGED EXPERIMENTAL2825 1451 38 DATA (6). THE REICH-MOORE CODE SAMMY (7) WAS USED FOR THE2825 1451 39 RESONANCE PARAMETER ANALYSIS. 2825 1451 40 THUS, THE THERMAL CROSS SECTIONS ARE GIVEN BY THE 2825 1451 41 RESONANCE PARAMETERS AND HAVE VALUES: TOTAL 29.4 B, 2825 1451 42 ELASTIC SCATTERING 24.8 B, AND CAPTURE 4.62 B. 2825 1451 43 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2825 1451 44 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2825 1451 45 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2825 1451 46 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2825 1451 47 3-1 THE TOTAL CROSS SECTION WAS OBTAINED FROM .812 TO 20 MEV 2825 1451 48 BY ANALYSIS OF THE SAME HIGH RESOLUTION MEASUREMENT 2825 1451 49 USED FOR THE RESONANCE PARAMETER ANALYSIS IN 2/151. DATA 2825 1451 50 WERE BINNED AND COMPARED WITH ENERGY AVERAGED DATA FROM 2825 1451 51 ARGONNE (8) AND OTHER DATA FROM CSISRS, AND GOOD 2825 1451 52 AGREEMENT WAS FOUND. 2825 1451 53 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2825 1451 54 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2825 1451 55 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2825 1451 56 3-28, 3-102, 3-103, 3-104, AND 3-107. 2825 1451 57 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2825 1451 58 .., 3-58, AND 3-91 2825 1451 59 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE EVALUATION 2825 1451 60 OF 58NI(N,2N)57NI CROSS SECTIONS BY PAVLIK AND 2825 1451 61 WINKLER (9). THESE CROSS SECTIONS WERE SLIGHTLY LARGER 2825 1451 62 THAN THE TNG CALCULATIONS. (SEE (N,NP) BELOW). 2825 1451 63 3-22 (N,NA) + (N,AN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2825 1451 64 CODE (2,3,4,5). NO DATA AVAILABLE OTHER THAN A EMISSION. 2825 1451 65 3-28 (N,NP) + (N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2825 1451 66 CODE (2,3,4,5) BUT MODIFIED ABOVE EINC OF 13.0 MEV TO FIT 2825 1451 67 THE DATA OF PAVLIK ET AL. (10). THE MODIFICATION OF THE 2825 1451 68 TNG CALCULATION FOR (N,NP) CANCELED OUT THE DIFFERENCE 2825 1451 69 BETWEEN THE TNG CALCULATION FOR (N,2N) AND THE ACTUAL 2825 1451 70 (N,2N) USED (SEE ABOVE) SO THAT THE TNG CALCULATED 2825 1451 71 NONELASTIC CROSS DID NOT CHANGE. 2825 1451 72 3-51 TO 3-58 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2825 1451 73 FROM TNG (2,3,4,5) WHICH INCLUDES DIRECT INTERACTION 2825 1451 74 CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. EXTENSIVE 2825 1451 75 COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION 2825 1451 76 PROCESS ARE SHOWN IN (5). 2825 1451 77 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2825 1451 78 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA (5). 2825 1451 79 3-102 (N,G) CAPTURE CROSS SECTION IS PROVIDED ONLY BY RESONANCE 2825 1451 80 PARAMETERS FROM 1.E-5 EV TO 450 KEV. FROM 450 TO 812 KEV 2825 1451 81 A SMALL BACKGROUND FILE IS GIVEN IN 3/102 TO COMBINE WITH 2825 1451 82 THE 2/151 RESULTS. TNG CALCULATIONS WERE NORMALIZED 2825 1451 83 TO THE RESONANCE REGION RESULTS BETWEEN 100-812 KEV, 2825 1451 84 AND USED FROM 812 KEV TO 20 MEV. 2825 1451 85 3-103 (N,P) CROSS SECTIONS UP TO 6 MEV WERE TAKEN FROM THE 2825 1451 86 GLUCS (12) CALCULATION IN WHICH THIS REACTION WAS STUDIED 2825 1451 87 SIMULTANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2825 1451 88 SECTIONS (13). FROM 6 TO 13 MEV A LINE WAS DRAWN 2825 1451 89 THROUGH DATA (SEVERAL MEASURED DATA SETS DISAGREE AND A 2825 1451 90 COMPROMISE WAS CHOSEN). ABOVE 13 MEV, TNG CALC. WERE USED 2825 1451 91 WHICH COMPARED VERY WELL WITH RECENT MEASUREMENTS (5). 2825 1451 92 3-104 (N,D) CROSS SECTION - TAKEN FROM ENDF/B-V (11) WHICH 2825 1451 93 AGREED WELL WITH AVAILABLE DATA. 2825 1451 94 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2825 1451 95 TNG CODE (2,3,4,5) AND MODIFIED BETWEEN EINC FROM 7.0 TO 2825 1451 96 13 MEV TO BETTER FIT THE RATIO DATA OF WATTECAMPS (14). 2825 1451 97 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS FOR ELASTIC 2825 1451 98 SCATTERING WERE REVIEWED AND ADOPTED FROM ENDF/B-V (11). 2825 1451 99 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2825 1451 100 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2825 1451 101 PARAMETERS IN 2/151. 2825 1451 102 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2825 1451 103 NEUTRON AND 57NI RESIDUAL, AND ENERGY DEPENDENT YIELDS 2825 1451 104 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2825 1451 105 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2825 1451 106 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2825 1451 107 THE OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY 2825 1451 108 USED TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 109 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2825 1451 110 NEUTRON, ALPHA, AND 54FE RESIDUAL, AND ENERGY DEPENDENT 2825 1451 111 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2825 1451 112 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2825 1451 113 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2825 1451 114 FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2825 1451 115 ALPHA AND RESIDUAL). (N,XA) D-D EMISSION DATA HEAVILY USED2825 1451 116 TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 117 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2825 1451 118 NEUTRON, P, AND 57CO RESIDUAL, AND ENERGY DEPENDENT YIELD 2825 1451 119 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2825 1451 120 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2825 1451 121 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2825 1451 122 THE OUTGOING NEUTRON). (N,XP) D-D EMISSION DATA HEAVILY 2825 1451 123 USED TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 124 6-51 THROUGH 6-58 INELASTIC SCATTERING EXCITING LEVELS; EACH 2825 1451 125 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2825 1451 126 AND 58NI RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2825 1451 127 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2825 1451 128 BY DWUCK (1) AND TNG (2,3,4,5)). EXTENSIVE COMPARISONS 2825 1451 129 WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN (5). 2825 1451 130 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2825 1451 131 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 58NI 2825 1451 132 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2825 1451 133 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2825 1451 134 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2825 1451 135 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2825 1451 136 OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY USED 2825 1451 137 TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 138 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2825 1451 139 AND 58CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2825 1451 140 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2825 1451 141 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2825 1451 142 PRODUCT. (N,XP) D-D EMISSION DATA HEAVILY USED TO BENCH- 2825 1451 143 MARK THE TNG CALCULATIONS (5). 2825 1451 144 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2825 1451 145 AND 55FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2825 1451 146 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2825 1451 147 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2825 1451 148 PRODUCT. (N,XA) D-D EMISSION DATA HEAVILY USED TO BENCH- 2825 1451 149 MARK THE TNG CALCULATIONS (5). 2825 1451 150 12-51 THROUGH 12-58 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2825 1451 151 BY HETRICK ET AL. (5), ARE GIVEN. 2825 1451 152 12-102 (N,G) CAPTURE; MULTIPLICITIES WERE TNG CALCULATED. 2825 1451 153 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2825 1451 154 ASSUMED TO BE ISOTROPIC. 2825 1451 155 15-102 (N,G) CAPTURE; TNG CALCULATED. 2825 1451 156 -------------------------------------------------------------- 2825 1451 157 UNCERTAINTY FILES 2825 1451 158 ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS 2825 1451 159 REQUIRED BY ENDF/B-VI FORMATS 2825 1451 160 2825 1451 161 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 100 EV 2825 1451 162 EXPLICIT FROM 100 EV TO 20 MEV, USING LB=0,1 AND 8. 2825 1451 163 33-2 EXPLICIT FROM 1E-5 10 100 EV, DERIVED FROM 100EV TO 20 MEV2825 1451 164 33-3 DERIVED FROM 1.E-5 TO 450 KEV, EXPLICIT USING LB=1,8 FROM 2825 1451 165 450 KEV TO 20 MEV 2825 1451 166 33-4 DERIVED FROM THRESHOLD TO 20 MEV. 2825 1451 167 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE EVALUATION OF 2825 1451 168 PAVLIK AND WINKLER (9). 2825 1451 169 33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM CALCULATION AND DATA 2825 1451 170 33-28 (N,NP) COVARIANCES - PAVLIK ET AL.'S (10) DATA USED AS A 2825 1451 171 GUIDE. 2825 1451 172 33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA 2825 1451 173 AND CALCULATIONS. 2825 1451 174 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2825 1451 175 ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CALCU- 2825 1451 176 LATIONS FROM TNG FROM 450 KEV TO 20 MEV. 2825 1451 177 33-103 (N,P) COVARIANCES WERE TAKEN FROM THE GLUCS (12) 2825 1451 178 CALCULATION IN WHICH THIS REACTION WAS STUDIED 2825 1451 179 SIMULTANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2825 1451 180 SECTIONS (13). 2825 1451 181 33-104 (N,D) COVARIANCES - CSISRS DATA USED AS A GUIDE. 2825 1451 182 33-107 (N,A) COVARIANCES - CSISRS DATA USED AS A GUIDE. 2825 1451 183 REFERENCES: 2825 1451 184 (1) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2825 1451 185 COLORADO, UNPUBLISHED (1972). 2825 1451 186 (2) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2825 1451 187 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2825 1451 188 MOMENTUM," ORNL/TM-7042 (1980). 2825 1451 189 (3) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2825 1451 190 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2825 1451 191 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2825 1451 192 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2825 1451 193 NATIONAL LAB. 2825 1451 194 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2825 1451 195 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2825 1451 196 (5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2825 1451 197 -INDUCED CROSS SECTIONS FOR 58,60NI FROM 1 TO 20 MEV AND 2825 1451 198 COMPARISONS WITH EXPERIMENT," ORNL/TM-10219,ENDF-344 (1987). 2825 1451 199 (6) C.M. PEREY, F.G. PEREY, J.A. HARVEY, N.W. HILL, N.M. LARSON, 2825 1451 200 AND R.L. MACKLIN,"58NI+N TRANSMISSION, DIFFERENTIAL ELASTIC 2825 1451 201 SCATTERING AND CAPTURE MEASUREMENTS AND ANALYSIS FROM 5 TO 2825 1451 202 813 KEV", REPORT ORNL/TM-10841, IN PREPARATION 2825 1451 203 (7) N.M. LARSON AND F.G. PEREY,"USERS GUIDE FOR SAMMY:A COMPUTER 2825 1451 204 MODEL FOR MULTILEVEL R-MATRIX FITS TO NEUTRON DATA USING 2825 1451 205 BAYES' EQUATIONS", ORNL/TM-7485, OAK RIDGE NATIONAL LAB, 19802825 1451 206 "UPDATED USERS'GUIDE FOR SAMMY", ORNL/TM-9179, 1984, 2825 1451 207 ORNL/TM-9179R1, 1985, AND ORNL/TM-9179/R2, 1988. 2825 1451 208 (8) C. BUDTZ-JORGENSEN, P.T. GUENTHER, A.B. SMITH AND J.F. WHALEN2825 1451 209 "FAST-NEUTRON TOTAL AND SCATTERING CROSS SECTIONS OF 58NI", 2825 1451 210 ZEIT. PHYS A306,265,1982 AND REPORT ANL/NDM-61, 1982. 2825 1451 211 (9) A. PAVLIK AND G. WINKLER, "EVALUATION OF THE 58NI(N,2N)57NI 2825 1451 212 CROSS SECTIONS," INDC(AUS)-9/L, INTERNATIONAL NUCLEAR DATA 2825 1451 213 COMMITTEE, INTERNATIONAL ATOMIC ENERGY AGENCY, NUCLEAR DATA 2825 1451 214 SECTION (1983). 2825 1451 215 (10) A. PAVLIK, G. WINKLER, AND M. UHL, NUCL. SCI. ENG. 90, 2825 1451 216 186-202 (1985). 2825 1451 217 (11) M. DIVADEENAM,"NI ELEMENTAL NEUTRON INDUCED REACTION CROSS- 2825 1451 218 SECTION EVALUATION", BNL-NCS-51346, ENDF-294, MARCH 1979. 2825 1451 219 (12) D.M. HETRICK AND C.Y. FU, "GLUCS: A GENERALIZED LEAST SQUARES2825 1451 220 PROGRAM FOR UPDATING CROSS SECTION EVALUATIONS WITH 2825 1451 221 CORRELATED DATA SETS," ORNL/TM-7341, ENDF-303 (OCT,1980). 2825 1451 222 (13) C.Y. FU AND D.M. HETRICK, "EXPERIENCE IN USING THE 2825 1451 223 COVARIANCES OF SOME ENDF/B-V DOSIMETRY CROSS SECTIONS: 2825 1451 224 PROPOSED IMPROVEMENTS AND ADDITIONS OF CROSS-REACTION 2825 1451 225 COVARIANCES," PROC. FOURTH ASTM-EURATOM SYMP. ON REACTOR 2825 1451 226 DOSIMETRY, GAITHERSBURG, MARYLAND, MARCH 22-26,1982, P877, 2825 1451 227 US NATIONAL BUREAU OF STANDARDS. 2825 1451 228 (14) E. WATTECAMPS, GEEL, BELGIUM, PRIVATE COMMUNICATION (1987). 2825 1451 229 1 451 242 12825 1451 230 2 151 489 12825 1451 231 3 16 9 12825 1451 232 3 28 7 12825 1451 233 3 102 11 12825 1451 234 3 103 17 12825 1451 235 3 104 12 12825 1451 236 3 107 15 12825 1451 237 33 16 39 12825 1451 238 33 28 12 12825 1451 239 33 103 87 12825 1451 240 33 104 12 12825 1451 241 33 107 16 12825 1451 242 2825 1 0 243 2825 0 0 244 2.805800+4 5.743800+1 0 0 1 02825 2151 245 2.805800+4 1.000000+0 0 0 1 02825 2151 246 1.000000-5 8.120000+5 1 3 0 12825 2151 247 0.000000+0 6.400000-1 1 0 3 32825 2151 248 5.743800+1 6.303500-1 0 0 402 672825 2151 249 -7.831800+4 5.000000-1 4.068500+4 4.000000+0 0.000000+0 0.000000+02825 2151 250 -1.167400+4 5.000000-1 4.262700+3 3.200000+0 0.000000+0 0.000000+02825 2151 251 1.530600+4 5.000000-1 1.332400+3 9.700000-1 0.000000+0 0.000000+02825 2151 252 3.613300+4 5.000000-1 1.836400+1 1.720000+0 0.000000+0 0.000000+02825 2151 253 6.334300+4 5.000000-1 3.855000+3 3.500000+0 0.000000+0 0.000000+02825 2151 254 8.339100+4 5.000000-1 3.959200+0 1.160000+0 0.000000+0 0.000000+02825 2151 255 1.083500+5 5.000000-1 1.094300+3 4.800000+0 0.000000+0 0.000000+02825 2151 256 1.240000+5 5.000000-1 4.631300+2 1.560000+0 0.000000+0 0.000000+02825 2151 257 1.376200+5 5.000000-1 2.035000+3 2.900000+0 0.000000+0 0.000000+02825 2151 258 1.403000+5 5.000000-1 3.119500+3 9.000000-1 0.000000+0 0.000000+02825 2151 259 1.581100+5 5.000000-1 5.281700+3 3.300000+0 0.000000+0 0.000000+02825 2151 260 1.689500+5 5.000000-1 4.240200+2 1.300000+0 0.000000+0 0.000000+02825 2151 261 1.761400+5 5.000000-1 4.800000+0 5.600000-1 0.000000+0 0.000000+02825 2151 262 1.919100+5 5.000000-1 2.506700+3 3.300000+0 0.000000+0 0.000000+02825 2151 263 2.065800+5 5.000000-1 7.460400+3 6.900000+0 0.000000+0 0.000000+02825 2151 264 2.110400+5 5.000000-1 5.691600+1 7.600000-1 0.000000+0 0.000000+02825 2151 265 2.330400+5 5.000000-1 5.628600+3 5.300000+0 0.000000+0 0.000000+02825 2151 266 2.423600+5 5.000000-1 3.000000+0 7.700000-1 0.000000+0 0.000000+02825 2151 267 2.455500+5 5.000000-1 2.355900+2 5.500000-1 0.000000+0 0.000000+02825 2151 268 2.619300+5 5.000000-1 1.422000+1 1.050000+0 0.000000+0 0.000000+02825 2151 269 2.725000+5 5.000000-1 5.402000+3 5.400000+0 0.000000+0 0.000000+02825 2151 270 2.815900+5 5.000000-1 1.949200+3 1.750000+0 0.000000+0 0.000000+02825 2151 271 2.853800+5 5.000000-1 4.000000+0 9.600000-1 0.000000+0 0.000000+02825 2151 272 2.980900+5 5.000000-1 4.000000+0 5.600000-1 0.000000+0 0.000000+02825 2151 273 3.054100+5 5.000000-1 6.508700+2 2.800000+0 0.000000+0 0.000000+02825 2151 274 3.260300+5 5.000000-1 1.582500+3 4.000000-1 0.000000+0 0.000000+02825 2151 275 3.351900+5 5.000000-1 1.415200+2 2.540000+0 0.000000+0 0.000000+02825 2151 276 3.496600+5 5.000000-1 1.779300+3 8.000000-1 0.000000+0 0.000000+02825 2151 277 3.677400+5 5.000000-1 1.259100+2 4.000000-1 0.000000+0 0.000000+02825 2151 278 3.950300+5 5.000000-1 6.935200+2 5.000000-1 0.000000+0 0.000000+02825 2151 279 4.174900+5 5.000000-1 9.361206+3 2.600000+0 0.000000+0 0.000000+02825 2151 280 4.246200+5 5.000000-1 7.714800+3 3.300000+0 0.000000+0 0.000000+02825 2151 281 4.280500+5 5.000000-1 1.083600+3 9.000000-1 0.000000+0 0.000000+02825 2151 282 4.555000+5 5.000000-1 1.787000+3 2.000000+0 0.000000+0 0.000000+02825 2151 283 4.622500+5 5.000000-1 4.370000+2 2.000000+0 0.000000+0 0.000000+02825 2151 284 4.704100+5 5.000000-1 4.690400+2 2.000000+0 0.000000+0 0.000000+02825 2151 285 4.918100+5 5.000000-1 1.782000+2 1.000000+0 0.000000+0 0.000000+02825 2151 286 4.963200+5 5.000000-1 1.383800+3 2.000000+0 0.000000+0 0.000000+02825 2151 287 5.077800+5 5.000000-1 1.496300+3 2.000000+0 0.000000+0 0.000000+02825 2151 288 5.235200+5 5.000000-1 1.276100+3 2.000000+0 0.000000+0 0.000000+02825 2151 289 5.292500+5 5.000000-1 1.957200+2 1.000000+0 0.000000+0 0.000000+02825 2151 290 5.412100+5 5.000000-1 5.063100+2 2.000000+0 0.000000+0 0.000000+02825 2151 291 5.537100+5 5.000000-1 2.390200+3 2.000000+0 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5.94300-13 1.000000+6 3.46940-12282533107 980 2.000000+6 1.818900-9 3.000000+6 1.171100-7 4.000000+6 6.787600-7282533107 981 5.000000+6 3.539200-6 8.500000+6 3.767000-5 1.300000+7 4.830600-5282533107 982 1.600000+7 2.994600-5 1.750000+7 1.396900-5 2.000000+7 0.000000+0282533107 983 282533 0 984 2825 0 0 985 0 0 0 986 2.805900+4 5.861000+1 0 0 0 12828 1451 1 0.000000+0 0.000000+0 0 0 0 62828 1451 2 1.000000+0 0.000000+0 0 0 10 62828 1451 3 0.000000+0 0.000000+0 0 0 15 52828 1451 4 28-NI- 59 HEDL EVAL-JAN83 F.M.MANN 2828 1451 5 DIST-APR90 900119 2828 1451 6 ----ENDF/B-VI MATERIAL 2828 2828 1451 7 -----INCIDENT NEUTRON DATA 2828 1451 8 ------ENDF-6 FORMAT 2828 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2828 1451 10 ACTIVATION I 2828 1451 11 ******************************************************************2828 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 2828 1451 13 * * * * * * *2828 1451 14 BASED ON RESONANCE PARAMETERS FROM NEUTRON CROSS SECTIONS, 2828 1451 15 VOLUME 1, NEUTRON RESONANCE PARAMETERS... BY S. F. MUGHABGHAB 2828 1451 16 (UP TO 10 KEV) 2828 1451 17 BASED ON HAUSER-FESHBACH CALCULATIONS WHICH AGREE WITH FE-56 2828 1451 18 (ALPHA,N-0) MEASUREMENTS BY R. W. KAVANAGH (CAL TECH) 2828 1451 19 1 451 24 02828 1451 20 2 151 4 02828 1451 21 3 102 74 02828 1451 22 3 103 74 02828 1451 23 3 107 74 02828 1451 24 2828 1 0 25 2828 0 0 26 2.805900+4 5.861000+1 0 0 1 02828 2151 27 2.805900+4 1.000000+0 0 0 1 02828 2151 28 1.000000-5 1.000000+4 0 0 0 02828 2151 29 1.500000+0 7.000000-1 0 0 0 02828 2151 30 2828 2 0 31 2828 0 0 32 2.805900+4 5.861000+1 0 0 0 02828 3102 33 1.138850+7 1.138850+7 0 0 2 2132828 3102 34 5 5 213 2 0 02828 3102 35 1.000000-5 4.051100+3 2.500000-2 8.104100+1 1.000000+0 1.293600+12828 3102 36 1.000000+1 4.477800+0 3.000000+1 3.212100+0 5.000000+1 3.175300+02828 3102 37 1.000000+2 4.924100+0 1.200000+2 6.893200+0 1.400000+2 1.099500+12828 3102 38 1.500000+2 1.491200+1 1.600000+2 2.170100+1 1.700000+2 3.503400+12828 3102 39 1.750000+2 4.711300+1 1.800000+2 6.687200+1 1.840000+2 9.320500+12828 3102 40 1.870000+2 1.243500+2 1.900000+2 1.730200+2 1.930000+2 2.528200+22828 3102 41 1.960000+2 3.876400+2 1.990000+2 6.008600+2 2.010000+2 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80 6.540000+3 1.800100-1 6.575000+3 1.469600-1 6.625000+3 1.129400-12828 3102 81 6.675000+3 8.918800-2 6.750000+3 6.528300-2 6.850000+3 4.581500-22828 3102 82 6.950000+3 3.393200-2 7.050000+3 2.619200-2 7.210000+3 1.848200-22828 3102 83 7.550000+3 1.069100-2 7.900000+3 7.573900-3 8.300000+3 7.166800-32828 3102 84 8.500000+3 8.875400-3 8.700000+3 1.504300-2 8.800000+3 2.400200-22828 3102 85 8.830000+3 2.878900-2 8.870000+3 3.822900-2 8.910000+3 5.394700-22828 3102 86 8.950000+3 8.285300-2 8.995000+3 1.567100-1 9.010000+3 2.044600-12828 3102 87 9.020000+3 2.490600-1 9.030000+3 3.091000-1 9.038000+3 3.729600-12828 3102 88 9.050000+3 5.080900-1 9.060000+3 6.742500-1 9.075000+3 1.059700+02828 3102 89 9.090000+3 1.583100+0 9.103000+3 1.829600+0 9.115000+3 1.609700+02828 3102 90 9.130000+3 1.085000+0 9.140000+3 8.002000-1 9.150000+3 5.953600-12828 3102 91 9.160000+3 4.522400-1 9.168000+3 3.691000-1 9.175000+3 3.127000-12828 3102 92 9.185000+3 2.511700-1 9.200000+3 1.871700-1 9.230000+3 1.146000-12828 3102 93 9.270000+3 6.865900-2 9.310000+3 4.577100-2 9.350000+3 3.280500-22828 3102 94 9.400000+3 2.324100-2 9.500000+3 1.366400-2 9.600000+3 9.190200-32828 3102 95 9.700000+3 6.731600-3 9.800000+3 5.226700-3 1.000000+4 3.534500-32828 3102 96 1.000000+4 1.259100-1 3.000000+4 5.834900-2 6.000000+4 3.422900-22828 3102 97 1.000000+5 2.684600-2 1.500000+5 1.982500-2 2.000000+5 1.676700-22828 3102 98 3.000000+5 1.374500-2 4.000000+5 8.429300-3 6.000000+5 4.947100-32828 3102 99 8.000000+5 4.315300-3 1.000000+6 4.371900-3 1.200000+6 3.507900-32828 3102 100 1.400000+6 2.967600-3 1.600000+6 2.873200-3 1.800000+6 2.797100-32828 3102 101 2.000000+6 2.703100-3 2.250000+6 2.321200-3 2.500000+6 2.295000-32828 3102 102 2.750000+6 2.202200-3 3.000000+6 2.103500-3 3.500000+6 1.837000-32828 3102 103 4.000000+6 1.654800-3 4.500000+6 1.487600-3 5.000000+6 1.385500-32828 3102 104 6.000000+6 1.235300-3 7.000000+6 1.064300-3 8.000000+6 9.948900-42828 3102 105 9.000000+6 2.213400-4 1.000000+7 5.897700-6 2.000000+7 5.897700-62828 3102 106 2828 3 0 107 2.805900+4 5.861000+1 0 0 0 02828 3103 108 1.855300+6 1.855300+6 0 0 2 2132828 3103 109 5 5 213 2 0 02828 3103 110 1.000000-5 9.819100+1 2.500000-2 1.964300+0 1.000000+0 3.135500-12828 3103 111 1.000000+1 1.085200-1 3.000000+1 7.781900-2 5.000000+1 7.690600-22828 3103 112 1.000000+2 1.191900-1 1.200000+2 1.668300-1 1.400000+2 2.660600-12828 3103 113 1.500000+2 3.608200-1 1.600000+2 5.250800-1 1.700000+2 8.476400-12828 3103 114 1.750000+2 1.139900+0 1.800000+2 1.617900+0 1.840000+2 2.255000+02828 3103 115 1.870000+2 3.008600+0 1.900000+2 4.186000+0 1.930000+2 6.116800+02828 3103 116 1.960000+2 9.378400+0 1.990000+2 1.453700+1 2.010000+2 1.839700+12828 3103 117 2.020000+2 1.982900+1 2.034000+2 2.055200+1 2.050000+2 1.923000+12828 3103 118 2.080000+2 1.352300+1 2.110000+2 8.568200+0 2.140000+2 5.533400+02828 3103 119 2.160000+2 4.248000+0 2.180000+2 3.335000+0 2.210000+2 2.409200+02828 3103 120 2.250000+2 1.655700+0 2.300000+2 1.113300+0 2.350000+2 7.945300-12828 3103 121 2.400000+2 5.927600-1 2.500000+2 3.630100-1 2.600000+2 2.430200-12828 3103 122 2.700000+2 1.729900-1 2.800000+2 1.288000-1 3.000000+2 7.855000-22828 3103 123 3.150000+2 5.755500-2 3.400000+2 3.708100-2 3.700000+2 2.397100-22828 3103 124 4.000000+2 1.660900-2 4.400000+2 1.098600-2 5.000000+2 6.614900-32828 3103 125 6.100000+2 3.256100-3 7.300000+2 1.834700-3 8.500000+2 1.179800-32828 3103 126 1.000000+3 7.724000-4 1.200000+3 5.157800-4 1.650000+3 3.333600-42828 3103 127 2.000000+3 3.349500-4 2.500000+3 5.650300-4 2.700000+3 9.130100-42828 3103 128 2.800000+3 1.303100-3 2.900000+3 2.129000-3 2.950000+3 2.947700-32828 3103 129 3.000000+3 4.437800-3 3.050000+3 7.610400-3 3.075000+3 1.075600-22828 3103 130 3.100000+3 1.645400-2 3.125000+3 2.844600-2 3.140000+3 4.336400-22828 3103 131 3.150000+3 6.098400-2 3.165000+3 1.171800-1 3.175000+3 2.116500-12828 3103 132 3.182000+3 3.643700-1 3.186000+3 5.355900-1 3.189000+3 7.516200-12828 3103 133 3.191000+3 9.704200-1 3.193000+3 1.287300+0 3.195000+3 1.756400+02828 3103 134 3.198000+3 2.900500+0 3.201000+3 4.461900+0 3.203000+3 4.966500+02828 3103 135 3.205000+3 4.450900+0 3.208000+3 2.890300+0 3.211000+3 1.752300+02828 3103 136 3.213000+3 1.285600+0 3.215000+3 9.701000-1 3.217000+3 7.521600-12828 3103 137 3.220000+3 5.367500-1 3.224000+3 3.658000-1 3.230000+3 2.283600-12828 3103 138 3.240000+3 1.247200-1 3.250000+3 7.835500-2 3.260000+3 5.379600-22828 3103 139 3.270000+3 3.926100-2 3.290000+3 2.365800-2 3.310000+3 1.591100-22828 3103 140 3.370000+3 6.988900-3 3.430000+3 4.173400-3 3.550000+3 2.422400-32828 3103 141 3.675000+3 2.122800-3 3.765000+3 2.365100-3 3.860000+3 3.128100-32828 3103 142 3.910000+3 3.892300-3 3.950000+3 4.825000-3 3.990000+3 6.227300-32828 3103 143 4.030000+3 8.415100-3 4.060000+3 1.090400-2 4.095000+3 1.528800-22828 3103 144 4.135000+3 2.314100-2 4.175000+3 3.321100-2 4.211000+3 3.773900-22828 3103 145 4.245000+3 3.291800-2 4.285000+3 2.269900-2 4.325000+3 1.482800-22828 3103 146 4.360000+3 1.045900-2 4.400000+3 7.344300-3 4.430000+3 5.812800-32828 3103 147 4.470000+3 4.415200-3 4.510000+3 3.476600-3 4.550000+3 2.821700-32828 3103 148 4.650000+3 1.860300-3 4.890000+3 1.042400-3 5.140000+3 8.707500-42828 3103 149 5.400000+3 1.018100-3 5.680000+3 1.738800-3 5.800000+3 2.515200-32828 3103 150 5.875000+3 3.354700-3 5.925000+3 4.190000-3 5.975000+3 5.385700-32828 3103 151 6.010000+3 6.546100-3 6.040000+3 7.845600-3 6.075000+3 9.854500-32828 3103 152 6.125000+3 1.403700-2 6.175000+3 2.024200-2 6.225000+3 2.759300-22828 3103 153 6.276000+3 3.128800-2 6.325000+3 2.725900-2 6.375000+3 1.979400-22828 3103 154 6.425000+3 1.360500-2 6.475000+3 9.467400-3 6.510000+3 7.488600-32828 3103 155 6.540000+3 6.211400-3 6.575000+3 5.072900-3 6.625000+3 3.901300-32828 3103 156 6.675000+3 3.083400-3 6.750000+3 2.260200-3 6.850000+3 1.590000-32828 3103 157 6.950000+3 1.181100-3 7.050000+3 9.148500-4 7.210000+3 6.501500-42828 3103 158 7.550000+3 3.846400-4 7.900000+3 2.835000-4 8.300000+3 2.895100-42828 3103 159 8.500000+3 3.764700-4 8.700000+3 6.683500-4 8.800000+3 1.086100-32828 3103 160 8.830000+3 1.308800-3 8.870000+3 1.747300-3 8.910000+3 2.476900-32828 3103 161 8.950000+3 3.817900-3 8.995000+3 7.242900-3 9.010000+3 9.457100-32828 3103 162 9.020000+3 1.152500-2 9.030000+3 1.430900-2 9.038000+3 1.727000-22828 3103 163 9.050000+3 2.353500-2 9.060000+3 3.123900-2 9.075000+3 4.911300-22828 3103 164 9.090000+3 7.337900-2 9.103000+3 8.480700-2 9.115000+3 7.461100-22828 3103 165 9.130000+3 5.028300-2 9.140000+3 3.708000-2 9.150000+3 2.758300-22828 3103 166 9.160000+3 2.094800-2 9.168000+3 1.709300-2 9.175000+3 1.447800-22828 3103 167 9.185000+3 1.162600-2 9.200000+3 8.658600-3 9.230000+3 5.294400-32828 3103 168 9.270000+3 3.164900-3 9.310000+3 2.104300-3 9.350000+3 1.503700-32828 3103 169 9.400000+3 1.060900-3 9.500000+3 6.180100-4 9.600000+3 4.116200-42828 3103 170 9.700000+3 2.985800-4 9.800000+3 2.296800-4 1.000000+4 1.527500-42828 3103 171 1.000000+4 3.805600-2 3.000000+4 2.815700-2 6.000000+4 2.417500-22828 3103 172 1.000000+5 3.284300-2 1.500000+5 3.517300-2 2.000000+5 3.574500-22828 3103 173 3.000000+5 4.000200-2 4.000000+5 2.842300-2 6.000000+5 2.720600-22828 3103 174 8.000000+5 3.785100-2 1.000000+6 6.238100-2 1.200000+6 7.229600-22828 3103 175 1.400000+6 7.301400-2 1.600000+6 8.652400-2 1.800000+6 1.017800-12828 3103 176 2.000000+6 1.179700-1 2.250000+6 1.312700-1 2.500000+6 1.522600-12828 3103 177 2.750000+6 1.673300-1 3.000000+6 1.885700-1 3.500000+6 2.132400-12828 3103 178 4.000000+6 2.448100-1 4.500000+6 2.609100-1 5.000000+6 3.038100-12828 3103 179 6.000000+6 3.713800-1 7.000000+6 4.367100-1 8.000000+6 5.367700-12828 3103 180 9.000000+6 6.291000-1 1.000000+7 7.438100-1 2.000000+7 9.000000-12828 3103 181 2828 3 0 182 2.805900+4 5.861000+1 0 0 0 02828 3107 183 5.096900+6 5.096900+6 0 0 2 2132828 3107 184 5 5 213 2 0 02828 3107 185 1.000000-5 5.995700+2 2.500000-2 1.199400+1 1.000000+0 1.914700+02828 3107 186 1.000000+1 6.628900-1 3.000000+1 4.757200-1 5.000000+1 4.704700-12828 3107 187 1.000000+2 7.301700-1 1.200000+2 1.022400+0 1.400000+2 1.631100+02828 3107 188 1.500000+2 2.212300+0 1.600000+2 3.219800+0 1.700000+2 5.198200+02828 3107 189 1.750000+2 6.990600+0 1.800000+2 9.922600+0 1.840000+2 1.383000+12828 3107 190 1.870000+2 1.845200+1 1.900000+2 2.567300+1 1.930000+2 3.751500+12828 3107 191 1.960000+2 5.752000+1 1.990000+2 8.915900+1 2.010000+2 1.128300+22828 3107 192 2.020000+2 1.216200+2 2.034000+2 1.260500+2 2.050000+2 1.179400+22828 3107 193 2.080000+2 8.293900+1 2.110000+2 5.255100+1 2.140000+2 3.393800+12828 3107 194 2.160000+2 2.605400+1 2.180000+2 2.045400+1 2.210000+2 1.477600+12828 3107 195 2.250000+2 1.015400+1 2.300000+2 6.827900+0 2.350000+2 4.872500+02828 3107 196 2.400000+2 3.635000+0 2.500000+2 2.225800+0 2.600000+2 1.489900+02828 3107 197 2.700000+2 1.060400+0 2.800000+2 7.893900-1 3.000000+2 4.811900-12828 3107 198 3.150000+2 3.524300-1 3.400000+2 2.268700-1 3.700000+2 1.464800-12828 3107 199 4.000000+2 1.013300-1 4.400000+2 6.686000-2 5.000000+2 4.006200-22828 3107 200 6.100000+2 1.947500-2 7.300000+2 1.076100-2 8.500000+2 6.738800-32828 3107 201 1.000000+3 4.223800-3 1.200000+3 2.611300-3 1.650000+3 1.315100-32828 3107 202 2.000000+3 1.019100-3 2.500000+3 1.000000-3 2.700000+3 1.104700-32828 3107 203 2.800000+3 1.188500-3 2.900000+3 1.299700-3 2.950000+3 1.368000-32828 3107 204 3.000000+3 1.446200-3 3.050000+3 1.536100-3 3.075000+3 1.586100-32828 3107 205 3.100000+3 1.639700-3 3.125000+3 1.697300-3 3.140000+3 1.733900-32828 3107 206 3.150000+3 1.759200-3 3.165000+3 1.798600-3 3.175000+3 1.825900-32828 3107 207 3.182000+3 1.845500-3 3.186000+3 1.856900-3 3.189000+3 1.865500-32828 3107 208 3.191000+3 1.871300-3 3.193000+3 1.877200-3 3.195000+3 1.883000-32828 3107 209 3.198000+3 1.891900-3 3.201000+3 1.900800-3 3.203000+3 1.906800-32828 3107 210 3.205000+3 1.912900-3 3.208000+3 1.922000-3 3.211000+3 1.931300-32828 3107 211 3.213000+3 1.937500-3 3.215000+3 1.943700-3 3.217000+3 1.950000-32828 3107 212 3.220000+3 1.959500-3 3.224000+3 1.972300-3 3.230000+3 1.991800-32828 3107 213 3.240000+3 2.025100-3 3.250000+3 2.059400-3 3.260000+3 2.094900-32828 3107 214 3.270000+3 2.131500-3 3.290000+3 2.208500-3 3.310000+3 2.290600-32828 3107 215 3.370000+3 2.573400-3 3.430000+3 2.923500-3 3.550000+3 3.925400-32828 3107 216 3.675000+3 5.735100-3 3.765000+3 8.024600-3 3.860000+3 1.241600-22828 3107 217 3.910000+3 1.636200-2 3.950000+3 2.103200-2 3.990000+3 2.794000-22828 3107 218 4.030000+3 3.861800-2 4.060000+3 5.070600-2 4.095000+3 7.194800-22828 3107 219 4.135000+3 1.099300-1 4.175000+3 1.586000-1 4.211000+3 1.805100-12828 3107 220 4.245000+3 1.572700-1 4.285000+3 1.079700-1 4.325000+3 6.999200-22828 3107 221 4.360000+3 4.891700-2 4.400000+3 3.389300-2 4.430000+3 2.650500-22828 3107 222 4.470000+3 1.975800-2 4.510000+3 1.522200-2 4.550000+3 1.205100-22828 3107 223 4.650000+3 7.359300-3 4.890000+3 3.137800-3 5.140000+3 1.701600-32828 3107 224 5.400000+3 1.073200-3 5.680000+3 7.712700-4 5.800000+3 7.194000-42828 3107 225 5.875000+3 7.156400-4 5.925000+3 7.309800-4 5.975000+3 7.674500-42828 3107 226 6.010000+3 8.110400-4 6.040000+3 8.649600-4 6.075000+3 9.541900-42828 3107 227 6.125000+3 1.151000-3 6.175000+3 1.453700-3 6.225000+3 1.817200-32828 3107 228 6.276000+3 1.993100-3 6.325000+3 1.772200-3 6.375000+3 1.374800-32828 3107 229 6.425000+3 1.044300-3 6.475000+3 8.206800-4 6.510000+3 7.120900-42828 3107 230 6.540000+3 6.409700-4 6.575000+3 5.765400-4 6.625000+3 5.086700-42828 3107 231 6.675000+3 4.598500-4 6.750000+3 4.088400-4 6.850000+3 3.653800-42828 3107 232 6.950000+3 3.381100-4 7.050000+3 3.208700-4 7.210000+3 3.073000-42828 3107 233 7.550000+3 3.214400-4 7.900000+3 4.097100-4 8.300000+3 7.469300-42828 3107 234 8.500000+3 1.235200-3 8.700000+3 2.624700-3 8.800000+3 4.539000-32828 3107 235 8.830000+3 5.551400-3 8.870000+3 7.539900-3 8.910000+3 1.084000-22828 3107 236 8.950000+3 1.689800-2 8.995000+3 3.235400-2 9.010000+3 4.234400-22828 3107 237 9.020000+3 5.167200-2 9.030000+3 6.422800-2 9.038000+3 7.758400-22828 3107 238 9.050000+3 1.058400-1 9.060000+3 1.405900-1 9.075000+3 2.212000-12828 3107 239 9.090000+3 3.306300-1 9.103000+3 3.821800-1 9.115000+3 3.362000-12828 3107 240 9.130000+3 2.264900-1 9.140000+3 1.669400-1 9.150000+3 1.241200-12828 3107 241 9.160000+3 9.419500-2 9.168000+3 7.681300-2 9.175000+3 6.502100-22828 3107 242 9.185000+3 5.215900-2 9.200000+3 3.878100-2 9.230000+3 2.361400-22828 3107 243 9.270000+3 1.401800-2 9.310000+3 9.241300-3 9.350000+3 6.538900-32828 3107 244 9.400000+3 4.549600-3 9.500000+3 2.566500-3 9.600000+3 1.648800-32828 3107 245 9.700000+3 1.150800-3 9.800000+3 8.509500-4 1.000000+4 5.231200-42828 3107 246 1.000000+4 1.790600-2 3.000000+4 8.042500-3 6.000000+4 4.755100-32828 3107 247 1.000000+5 3.604600-3 1.500000+5 2.911100-3 2.000000+5 2.660800-32828 3107 248 3.000000+5 2.596600-3 4.000000+5 2.235200-3 6.000000+5 2.069900-32828 3107 249 8.000000+5 2.817500-3 1.000000+6 3.875400-3 1.200000+6 4.459100-32828 3107 250 1.400000+6 5.256800-3 1.600000+6 7.043400-3 1.800000+6 9.411200-32828 3107 251 2.000000+6 1.169500-2 2.250000+6 1.428300-2 2.500000+6 1.884900-22828 3107 252 2.750000+6 2.468800-2 3.000000+6 2.924900-2 3.500000+6 3.623200-22828 3107 253 4.000000+6 4.383500-2 4.500000+6 4.754200-2 5.000000+6 5.324300-22828 3107 254 6.000000+6 6.331800-2 7.000000+6 7.050700-2 8.000000+6 7.610500-22828 3107 255 9.000000+6 7.432800-2 1.000000+7 7.464400-2 2.000000+7 7.000000-22828 3107 256 2828 3 0 257 2828 0 0 258 0 0 0 259 2.806000+4 5.941600+1 -1 0 0 12831 1451 1 0.000000+0 0.000000+0 0 0 0 62831 1451 2 1.000000+0 0.000000+0 0 0 10 62831 1451 3 0.000000+0 0.000000+0 0 0 196 52831 1451 4 28-NI- 60 ORNL EVAL-OCT89 LARSON, CM PEREY, HETRICK, FU 2831 1451 5 ORNL/TM10219,ENDF-344 DIST-APR90 900220 2831 1451 6 ----ENDF/B-VI MATERIAL 2831 2831 1451 7 -----INCIDENT NEUTRON DATA 2831 1451 8 ------ENDF-6 FORMAT 2831 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2831 1451 10 ACTIVATION I 2831 1451 11 ******************************************************************2831 1451 12 THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE 2831 1451 13 DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1) 2831 1451 14 AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES 2831 1451 15 ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE 2831 1451 16 COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL2831 1451 17 REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE 2831 1451 18 CONTENTS OF THIS EVALUATION AND EXTENSIVE COMPARISONS OF 2831 1451 19 CALCULATIONS WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5).2831 1451 20 2831 1451 21 ----- DESCRIPTION OF FILES 2831 1451 22 (MF-MT) 2831 1451 23 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2831 1451 24 2-151 RESONANCE PARAMETERS -- TAKEN FROM REF (6). THE NEGATIVE 2831 1451 25 ENERGY RESONANCES WERE ADJUSTED BY THE AUTHOR, C. M. PEREY2831 1451 26 TO GIVE THE PROPER THERMAL SCATTERING AND CAPTURE. USING 2831 1451 27 THESE MODIFIED RESULTS, NO BACKGROUND IS REQUIRED IN 3/1 2831 1451 28 IE, THE TOTAL, SCATTERING AND CAPTURE IS GIVEN COMPLETELY 2831 1451 29 BY THE RESONANCE PARAMETERS FROM 1.E-5 EV TO 450 KEV. 2831 1451 30 RESONANCE PARAMETERS ARE FROM A REICH-MOORE ANALYSIS WITH 2831 1451 31 THE CODE SAMMY (REF 7). 2831 1451 32 THUS, THE THERMAL CROSS SECTIONS ARE GIVEN BY THE 2831 1451 33 RESONANCE PARAMETERS AND HAVE VALUES: TOTAL 3.9 B, 2831 1451 34 ELASTIC SCATTERING 0.98 B, AND CAPTURE 2.92 B. 2831 1451 35 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2831 1451 36 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2831 1451 37 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2831 1451 38 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2831 1451 39 3-1 TOTAL CROSS SECTION -- FROM 450 KEV TO 1611 KEV THE DATA 2831 1451 40 OF REF (8) WERE USED. FROM 1611 KEV TO 20 MEV THE DATA 2831 1451 41 OF REF (9) WERE USED. SEVERAL LOWER RESOLUTION DATA SETS 2831 1451 42 WERE ENERGY-BINNED AND CHECKED WITH BINNED DATA FROM 8,9. 2831 1451 43 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2831 1451 44 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2831 1451 45 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2831 1451 46 3-28, 3-102, 3-103, 3-104, AND 3-107. 2831 1451 47 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2831 1451 48 .., 3-61, AND 3-91 2831 1451 49 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2831 1451 50 CODE (2,3,4,5), NO 60NI DATA AVAILABLE. 2831 1451 51 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2831 1451 52 CODE (2,3,4,5). NO 60NI DATA AVAILABLE OTHER THAN A EMISS 2831 1451 53 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2831 1451 54 CODE (2,3,4,5). NO 60NI DATA AVAILABLE OTHER THAN P EMISS 2831 1451 55 3-51 TO 3-61 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2831 1451 56 FROM TNG (2,3,4,5) WHICH INCLUDES DIRECT INTERACTION 2831 1451 57 CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. CALCULATIONS 2831 1451 58 COMPARED WITH EXTENSIVE EXPERIMENTAL DATA (5). 3-51 CROSS2831 1451 59 SECTIONS ABOVE 4.0 MEV ADJUSTED TO BETTER FIT RECENT 2831 1451 60 MEASURED DATA. 2831 1451 61 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2831 1451 62 CALCULATED). 2831 1451 63 3-102 (N,G) CAPTURE CROSS SECTION TAKEN FROM RESONANCE PARAMETER2831 1451 64 FROM 1.E-5 EV TO 450 KEV. TNG CALCULATIONS WERE 2831 1451 65 NORMALIZED TO THE AVERAGED CROSS SECTION OBTAINED FROM THE2831 1451 66 RESONANCE PARAMETERS FROM 100-450 KEV. THESE NORMALIZED 2831 1451 67 TNG RESULTS WERE USED FROM 450 KEV TO 20 MEV. 2831 1451 68 3-103 (N,P) CROSS SECTIONS FOR EN LESS THAN OR EQUAL TO 12 MEV 2831 1451 69 WERE TAKEN FROM A CURVE DRAWN THROUGH THE DATA OF VONACH 2831 1451 70 ET AL. (10). THIS CURVE WAS CONNECTED TO THE ANL DATA OF 2831 1451 71 GREENWOOD (11) FROM 14.5 TO 15.0 MEV. FROM 15.0 TO 20.0 2831 1451 72 MEV THE DATA OF PAULSEN AND LISKIEN (12) WERE USED 2831 1451 73 AS A GUIDE. THE NEW DATA BY VONACH ET AL. (10) 2831 1451 74 RESULT IN AN INTEGRAL VALUE CLOSE TO THE 2.39 VALUE OF 2831 1451 75 MANNHART (13). 2831 1451 76 3-104 (N,D) CROSS SECTION - ENDF/B-V (14) VALUES WERE NORMALIZED2831 1451 77 TO THE DATA OF GRIMES ET AL. (15). 2831 1451 78 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2831 1451 79 TNG CODE (2,3,4,5). LIMITED DATA OTHER THAN A EMISSION. 2831 1451 80 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2831 1451 81 ELASTIC SCATTERING ARE FROM ENDF/B-V. AGREE WELL WITH DATA2831 1451 82 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2831 1451 83 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2831 1451 84 PARAMETERS IN 2/151. 2831 1451 85 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2831 1451 86 NEUTRON AND 59NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2831 1451 87 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2831 1451 88 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2831 1451 89 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2831 1451 90 THE OUTGOING NEUTRON). COMPARES WELL WITH N EMISSION DATA2831 1451 91 WHEN COMBINED WITH N FROM 6/22, 6/28 AND 6/91. 2831 1451 92 6-22 (N,NA)+(N,AN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2831 1451 93 NEUTRON, ALPHA, AND 56FE RESIDUAL, AND ENERGY DEPENDENT 2831 1451 94 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2831 1451 95 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2831 1451 96 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2831 1451 97 FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2831 1451 98 ALPHA AND RESIDUAL). 2831 1451 99 6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2831 1451 100 NEUTRON, P, AND 59CO RESIDUAL, AND ENERGY DEPENDENT YIELD 2831 1451 101 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2831 1451 102 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2831 1451 103 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2831 1451 104 THE OUTGOING NEUTRON). 2831 1451 105 6-51 THROUGH 6-61 INELASTIC SCATTERING EXCITING LEVELS; EACH 2831 1451 106 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2831 1451 107 AND 60NI RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2831 1451 108 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2831 1451 109 BY DWUCK (1) AND TNG (2,3,4,5)), COMPARED WITH DATA IN (5)2831 1451 110 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2831 1451 111 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 60NI 2831 1451 112 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2831 1451 113 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2831 1451 114 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2831 1451 115 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2831 1451 116 OUTGOING NEUTRON). 2831 1451 117 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2831 1451 118 AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2831 1451 119 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2831 1451 120 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2831 1451 121 PRODUCT. COMPARES WELL WITH P EMISSION DATA WHEN COMBINED2831 1451 122 WITH 6/28. 2831 1451 123 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2831 1451 124 AND 57FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2831 1451 125 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2831 1451 126 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2831 1451 127 PRODUCT. COMPARES WELL WITH A EMISSION DATA WHEN COMBINED2831 1451 128 WITH 6/22. 2831 1451 129 12-51 THROUGH 12-61 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2831 1451 130 BY HETRICK ET AL. (5), ARE GIVEN. 2831 1451 131 12-102 (N,G) CAPTURE; MULTIPLICITIES WERE TNG CALCULATED. 2831 1451 132 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2831 1451 133 ASSUMED TO BE ISOTROPIC. 2831 1451 134 15-102 (N,G) CAPTURE; TNG CALCULATED 2831 1451 135 2831 1451 136 -------------------------------------------------------------- 2831 1451 137 UNCERTAINTY FILES 2831 1451 138 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2831 1451 139 REQUIRED BY ENDF/B-VI. 2831 1451 140 2831 1451 141 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2831 1451 142 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2831 1451 143 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2831 1451 144 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2831 1451 145 20 MEV THE FILES ARE DERIVED. 2831 1451 146 33-3 FROM 1.E-5 TO 450 KEV UNCERTAINTIES ARE DERIVED. FROM 4502831 1451 147 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82831 1451 148 33-4 UNCERTAINTIES ARE ALL DERIVED. 2831 1451 149 33-16 COVARIANCES WERE ESTIMATED AS NO DATA AVAILABLE. 2831 1451 150 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2831 1451 151 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM DATA2831 1451 152 AND CALCULATION. 2831 1451 153 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2831 1451 154 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2831 1451 155 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2831 1451 156 ENERGIES, AND CALCULATED RESULTS ABOVE 450 KEV. 2831 1451 157 33-103 COVARIANCES - DATA OF VONACH ET AL. (10) AND CSISRS DATA 2831 1451 158 USED AS A GUIDE. 2831 1451 159 33-104 UNCERTAINTIES ESTIMATED, BASED ON DATA 2831 1451 160 33-107 UNCERTAINTIES EXPLICIT, BASED ON DATA AND TNG RESULTS. 2831 1451 161 2831 1451 162 REFERENCES: 2831 1451 163 (1) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2831 1451 164 COLORADO, UNPUBLISHED (1972). 2831 1451 165 (2) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2831 1451 166 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2831 1451 167 MOMENTUM," ORNL/TM-7042 (1980). 2831 1451 168 (3) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2831 1451 169 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2831 1451 170 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2831 1451 171 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2831 1451 172 NATIONAL LAB. 2831 1451 173 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2831 1451 174 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2831 1451 175 (5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2831 1451 176 -INDUCED CROSS SECTIONS FOR 58,60NI FROM 1 TO 20 MEV AND 2831 1451 177 COMPARISONS WITH EXPERIMENT," ORNL/TM-10219,ENDF-344 (1987). 2831 1451 178 (6) C.M. PEREY, J.A. HARVEY, R.L. MACKLIN, F.G. PEREY AND R.R. 2831 1451 179 WINTERS, PHYS. REV. C27, 2556 (1983) 2831 1451 180 (7) N.M. LARSON AND F.G. PEREY,"USERS GUIDE FOR SAMMY:A COMPUTER 2831 1451 181 MODEL FOR MULTILEVEL R-MATRIX FITS TO NEUTRON DATA USING 2831 1451 182 BAYES' EQUATIONS, ORNL/TM-7485, OAK RIDGE NATIONAL LAB, 1980;2831 1451 183 "UPDATED USERS' GUIDE FOR SAMMY", ORNL/TM-9179, 1984, 2831 1451 184 ORNL/TM-9179/R1, 1985, AND ORNL/TM-9179/R2, 1988. 2831 1451 185 (8) J.A. HARVEY, ORELA, 80-M NE110 TA TARGET DATA, SENT TO NNDC 2831 1451 186 (9) J.A. HARVEY, ORELA, 80-M NE110 BE BLOCK DATA, SENT TO NNDC 2831 1451 187 (10) H. VONACH, M. WAGNER, AND R.C. HAIGHT, "NEUTRON CROSS 2831 1451 188 SECTIONS OF 58NI AND 60NI FOR 8-12 MEV NEUTRONS," PRIVATE 2831 1451 189 COMMUNICATION , 1989. 2831 1451 190 (11) L.R. GREENWOOD, DOE-ER-0046-21, 15,(MAY 1985) 2831 1451 191 (12) A. PAULSEN AND H. LISKIEN, NUKLEONIK 10, 91 (JULY 1967) 2831 1451 192 (13) W. MANNHART, PROC. FOURTH ASTM-EURATOM SYMP. ON REACTOR 2831 1451 193 DOSIMETRY, VOL. II, 637 (MARCH 22-26, 1982) 2831 1451 194 (14) M. DIVADEENAM, "NI ELEMENTAL NEUTRON INDUCED REACTION CROSS- 2831 1451 195 SECTION EVALUATION", BNL-NCS-51346, ENDF-294 (MARCH 1979). 2831 1451 196 (15) S.M. GRIMES, R.C. HAIGHT, K.R. ALVAR, H.H. BARSCHALL, AND 2831 1451 197 R.R. BORCHERS, PHYS. REV. C, 19(6), 2127 (JUNE 1979) 2831 1451 198 2831 1451 199 2831 1451 200 1 451 205 12831 1451 201 3 16 6 12831 1451 202 3 103 12 12831 1451 203 33 16 10 12831 1451 204 33 103 14 12831 1451 205 2831 1 0 206 2831 0 0 207 2.806000+4 5.941600+1 0 0 0 02831 3 16 208 -1.138900+7-1.138900+7 0 0 1 72831 3 16 209 7 2 0 0 0 02831 3 16 210 1.158100+7 0.000000+0 1.200000+7 1.973900-2 1.300000+7 1.689600-12831 3 16 211 1.450000+7 3.859000-1 1.600000+7 4.963300-1 1.750000+7 5.195500-12831 3 16 212 2.000000+7 4.808900-1 0.000000+0 0.000000+0 0.000000+0 0.000000+02831 3 16 213 2831 3 0 214 2.806000+4 5.941600+1 0 0 0 02831 3103 215 -2.042000+6-2.042000+6 0 0 1 252831 3103 216 25 2 0 0 0 02831 3103 217 2.076400+6 0.000000+0 3.000000+6 7.637400-8 3.500000+6 2.328300-52831 3103 218 4.000000+6 3.720600-4 4.500000+6 2.182500-3 5.000000+6 7.875900-32831 3103 219 5.500000+6 1.500000-2 6.000000+6 2.350000-2 6.500000+6 3.400000-22831 3103 220 7.000000+6 4.400000-2 7.500000+6 5.600000-2 8.000000+6 6.500000-22831 3103 221 8.500000+6 7.500000-2 9.000000+6 8.300000-2 9.500000+6 9.250000-22831 3103 222 1.000000+7 1.010000-1 1.100000+7 1.180000-1 1.200000+7 1.350000-12831 3103 223 1.300000+7 1.460000-1 1.350000+7 1.480000-1 1.400000+7 1.465000-12831 3103 224 1.450000+7 1.420200-1 1.600000+7 9.819000-2 1.750000+7 7.700000-22831 3103 225 2.000000+7 5.800000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02831 3103 226 2831 3 0 227 2831 0 0 228 2.806000+4 5.941600+1 0 0 0 1283133 16 229 0.000000+0 0.000000+0 0 16 0 3283133 16 230 0.000000+0 0.000000+0 0 1 6 3283133 16 231 1.000000-5 0.000000+0 1.158100+7 5.000000-3 2.000000+7 0.000000+0283133 16 232 0.000000+0 0.000000+0 0 1 10 5283133 16 233 1.000000-5 0.000000+0 1.158100+7 4.050000-2 1.300000+7 1.012500-2283133 16 234 1.750000+7 4.500000-3 2.000000+7 0.000000+0 0.000000+0 0.000000+0283133 16 235 0.000000+0 0.000000+0 0 8 10 5283133 16 236 1.000000-5 0.000000+0 1.158100+7 1.753300-6 1.300000+7 3.211600-5283133 16 237 1.750000+7 1.349700-4 2.000000+7 0.000000+0 0.000000+0 0.000000+0283133 16 238 283133 0 239 2.806000+4 5.941600+1 0 0 0 1283133103 240 0.000000+0 0.000000+0 0 103 0 4283133103 241 0.000000+0 0.000000+0 0 0 6 3283133103 242 1.000000-5 0.000000+0 2.076400+6 1.00000-11 2.000000+7 0.000000+0283133103 243 0.000000+0 0.000000+0 0 1 6 3283133103 244 1.000000-5 0.000000+0 2.076400+6 5.000000-3 2.000000+7 0.000000+0283133103 245 0.000000+0 0.000000+0 0 1 16 8283133103 246 1.000000-5 0.000000+0 2.076400+6 7.200000-2 5.000000+6 1.800000-2283133103 247 7.000000+6 1.012500-2 1.000000+7 1.012500-2 1.200000+7 4.500000-3283133103 248 1.600000+7 1.800000-2 2.000000+7 0.000000+0 0.000000+0 0.000000+0283133103 249 0.000000+0 0.000000+0 0 8 16 8283133103 250 1.000000-5 0.000000+0 2.076400+6 4.66640-17 5.000000+6 1.240600-7283133103 251 7.000000+6 2.178000-6 1.000000+7 1.147600-5 1.200000+7 9.112500-6283133103 252 1.600000+7 1.928300-5 2.000000+7 0.000000+0 0.000000+0 0.000000+0283133103 253 283133 0 254 2831 0 0 255 0 0 0 256 2.806100+4 6.040800+1 -1 0 0 12834 1451 1 0.000000+0 0.000000+0 0 0 0 62834 1451 2 1.000000+0 0.000000+0 0 0 10 62834 1451 3 0.000000+0 0.000000+0 0 0 153 22834 1451 4 28-NI- 61 ORNL EVAL-FEB89 HETRICK,FU,LARSON 2834 1451 5 ORNL/TM10219,ENDF-344 DIST-APR90 900221 2834 1451 6 ----ENDF/B-VI MATERIAL 2834 2834 1451 7 -----INCIDENT NEUTRON DATA 2834 1451 8 ------ENDF-6 FORMAT 2834 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2834 1451 10 ACTIVATION I 2834 1451 11 ******************************************************************2834 1451 12 THIS WORK EMPLOYED THE HAUSER-FESHBACH CODE TNG (1,2,3). 2834 1451 13 THE TNG CODE PROVIDES ENERGY AND ANGULAR DISTRIBUTIONS OF 2834 1451 14 PARTICLES EMITTED IN THE COMPOUND AND PRE-COMPOUND REACTIONS, 2834 1451 15 ENSURES CONSISTENCY AMONG ALL REACTIONS, AND MAINTAINS ENERGY 2834 1451 16 BALANCE. DETAILS PERTINENT TO THE CONTENTS OF THIS EVALUATION 2834 1451 17 CAN BE FOUND IN REFERENCE (4). 2834 1451 18 2834 1451 19 ----- DESCRIPTION OF FILES 2834 1451 20 (MF-MT) 2834 1451 21 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2834 1451 22 2-151 RESONANCE PARAMETERS; TAKEN FROM THE COMPILATION OF 2834 1451 23 MUGHABGHAB (5). FROM 1.E-5 TO 70 KEV THE TOTAL, 2834 1451 24 SCATTERING AND CAPTURE CROSS SECTIONS ARE GIVEN COMPLETELY2834 1451 25 BY THE RESONANCE PARAMETERS; NO BACKGROUND FILES ARE GIVEN2834 1451 26 THE THERMAL CROSS SECTIONS ARE GIVEN BY THE RESONANCE 2834 1451 27 PARAMETERS AND HAVE VALUES: TOTAL 10.4 B, ELASTIC 2834 1451 28 SCATTERING 7.9 B, CAPTURE 2.5 B 2834 1451 29 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2834 1451 30 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2834 1451 31 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2834 1451 32 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2834 1451 33 3-1 TOTAL CROSS SECTION - 1.E-5 EV TO 70 KEV, GIVEN BY THE 2834 1451 34 RESONANCE PARAMETERS. FROM 70 KEV TO 20 MEV, NAT NI DATA 2834 1451 35 OF REF. (6) WERE USED AS NO 61NI DATA AVAILABLE. 2834 1451 36 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2834 1451 37 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2834 1451 38 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 2834 1451 39 3-28, 3-102, 3-103, AND 3-107. 2834 1451 40 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2834 1451 41 .., 3-58, AND 3-91 2834 1451 42 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2834 1451 43 CODE (1,2,3,4). NO DATA AVAILABLE. 2834 1451 44 3-28 (N,NP)+(N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2834 1451 45 CODE (1,2,3,4). NO DATA AVAILABLE. 2834 1451 46 3-51 TO 3-58 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2834 1451 47 FROM TNG (1,2,3,4). 2834 1451 48 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM IS TNG 2834 1451 49 CALCULATED BUT ADJUSTED TO INCLUDE THE CROSS SECTION 2834 1451 50 SUBTRACTED AWAY FROM THE (N,P) (SEE BELOW) SO THAT THE 2834 1451 51 (N,P) AGREED WITH MEASURED DATA. THIS IS REASONABLE 2834 1451 52 BECAUSE THE TNG CALCULATIONS DID NOT INCLUDE A DIRECT 2834 1451 53 INTERACTION COMPONENT AND THE NONELASTIC STAYS THE SAME. 2834 1451 54 3-102 (N,G) CAPTURE CROSS SECTION GIVEN BY RESONANCE PARAMETERS 2834 1451 55 FROM 1.E-5 EV TO 70 KEV. POINTWISE CROSS SECTIONS WERE 2834 1451 56 GENERATED FROM THE RESONANCE PARAMETERS AND BINNED. THE 2834 1451 57 CAPTURE CROSS SECTION FROM TNG WAS NORMALIZED TO BINNED 2834 1451 58 DAT FROM 10-70 KEV AND USED FROM 70 KEV TO 20 MEV. 2834 1451 59 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2834 1451 60 CODE (1,2,3,4) BUT THEN WERE ADJUSTED TO FIT THE DATA OF 2834 1451 61 QAIM ET AL. (7). THE DIFFERENCE BETWEEN THE TNG RESULTS 2834 1451 62 FOR (N,P) AND THE DATA WERE ADDED TO THE TNG RESULTS FOR 2834 1451 63 3-91 (SEE ABOVE). 2834 1451 64 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2834 1451 65 TNG CODE (1,2,3,4). NO DATA AVAILABLE. 2834 1451 66 3-111 (N,2P) CROSS SECTIONS WERE CALCULATED BY THE 2834 1451 67 TNG CODE (1,2,3,4). NO DATA AVAILABLE. 2834 1451 68 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2834 1451 69 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2834 1451 70 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2834 1451 71 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2834 1451 72 PARAMETERS IN 2/151. 2834 1451 73 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2834 1451 74 NEUTRON AND 60NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2834 1451 75 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2834 1451 76 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2834 1451 77 EACH PRODUCT. ISOTROPY IS ASSUMED. 2834 1451 78 6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2834 1451 79 NEUTRON, P, AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD 2834 1451 80 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2834 1451 81 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2834 1451 82 EACH PRODUCT. ISOTROPY IS ASSUMED. 2834 1451 83 6-51 THROUGH 6-58 INELASTIC SCATTERING EXCITING LEVELS; 2834 1451 84 ASSUMED ISOTROPIC. 2834 1451 85 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2834 1451 86 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 61NI 2834 1451 87 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2834 1451 88 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2834 1451 89 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2834 1451 90 FOR EACH. ISOTROPY IS ASSUMED. 2834 1451 91 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2834 1451 92 AND 61CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2834 1451 93 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2834 1451 94 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2834 1451 95 PRODUCT. ISOTROPY IS ASSUMED. 2834 1451 96 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2834 1451 97 AND 58FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2834 1451 98 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2834 1451 99 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2834 1451 100 PRODUCT. ISOTROPY IS ASSUMED. 2834 1451 101 12-51 THROUGH 12-58 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2834 1451 102 12-102 (N,G) CAPTURE; MULTIPLICITIES FOR ENERGIES LESS THAN 2834 1451 103 1.0 MEV WERE TAKEN FROM ENDF/B-V FOR NAT NI BUT ADJUSTED 2834 1451 104 FOR ENERGY BALANCE; TNG CALCULATIONS WERE USED 2834 1451 105 FOR ENERGIES 2.0 AND 5.0 MEV. 2834 1451 106 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2834 1451 107 ASSUMED TO BE ISOTROPIC. 2834 1451 108 15-102 (N,G) CAPTURE; AS IN 12-102. 2834 1451 109 2834 1451 110 UNCERTAINTY FILES 2834 1451 111 ALL NON-DERIVED UNCERTAINTY FILES CONTAIN AN LB=8 COMPONENT 2834 1451 112 AS REQUIRED BY ENDF/B-VI. 2834 1451 113 2834 1451 114 33-1 UNCERTANTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 EV 2834 1451 115 TO 20 MEV THE UNCERTAINTIES ARE EXPLICIT, USING LB=0,1 AND 82834 1451 116 33-2 EXPLICIT FROM 1.E-5 TO 100 EV, USING LB=1 AND 8. FROM 100EV2834 1451 117 TO 20 MEV THE UNCERTAINTIES ARE DERIVED. 2834 1451 118 33-3 DERIVED FROM 1.E-5 TO 70 KEV, EXPLICIT FROM 70 KEV TO 20 MEV2834 1451 119 USING LB=1 AND 8. 2834 1451 120 33-4 UNCERTAINTIES ALL DERIVED. 2834 1451 121 33-16 UNCERTAINTIES EXPLICIT, ESTIMATED FROM TNG. 2834 1451 122 33-28 UNCERTAINTIES EXPLICIT, ESTIMATED FROM TNG. 2834 1451 123 33-51-91 UNCERTAINTIES EXPLICIT, ESTIMATED FROM DATA AND TNG. 2834 1451 124 33-102 UNCERTAINTIES BASED ON THERMAL CAPTURE AT LOW ENERGIES, 2834 1451 125 DATA TO 70 KEV, AND TNG CALCULATIONS TO 20 MEV. 2834 1451 126 33-103 BASED ON DATA AND TNG CALCULATIONS. 2834 1451 127 33-107 BASED ON TNG CALCULATIONS. 2834 1451 128 33-111 BASED ON TNG CALCULATIONS. 2834 1451 129 2834 1451 130 REFERENCES: 2834 1451 131 (1) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2834 1451 132 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2834 1451 133 MOMENTUM," ORNL/TM-7042 (1980). 2834 1451 134 (2) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2834 1451 135 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2834 1451 136 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2834 1451 137 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2834 1451 138 NATIONAL LAB. 2834 1451 139 (3) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2834 1451 140 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2834 1451 141 (4) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2834 1451 142 -INDUCED CROSS SECTIONS FOR 58,60NI FROM 1 TO 20 MEV AND 2834 1451 143 COMPARISONS WITH EXPERIMENT," ORNL/TM-10219,ENDF-344 (1987). 2834 1451 144 (5) S.F. MUGHABGHAB, M. DIVADEENAM, AND N.E. HOLDEN, "NEUTRON 2834 1451 145 CROSS SECTIONS, VOL. 1, NEUTRON RESONANCE PARAMETERS AND 2834 1451 146 THERMAL CROSS SECTIONS, PART A, Z=1-60," ACADEMIC 2834 1451 147 PRESS (1981). 2834 1451 148 (6) D.C. LARSON, N.M. LARSON, J.A.HARVEY, N.W. HILL AND C.H. 2834 1451 149 JOHNSON, "APPLICATION OF NEW TECHNIQUES TO ORELA NEUTRON 2834 1451 150 TRANSMISSION MEASUREMENTS AND THEIR UNCERTAINTY ANALYSIS: 2834 1451 151 THE CASE OF NATURAL NICKEL FROM 2 KEV TO 20 MEV", ORNL/TM82032834 1451 152 ENDF-333, OCTOBER 1983. 2834 1451 153 (7) S.M. QAIM, R. WOLFLE, M.M. RAHMAN, AND H. OLLIG, NUCL. SCI. 2834 1451 154 ENG., 88, 143-153 (1984) AND N.I. MOLLA AND S.M. QAIM, NUCL. 2834 1451 155 PHYS., A283, 269-288 (1977). 2834 1451 156 2834 1451 157 1 451 159 12834 1451 158 3 111 6 12834 1451 159 2834 1 0 160 2834 0 0 161 2.806100+4 6.040800+1 0 0 0 02834 3111 162 -9.288700+6-9.288700+6 0 0 1 72834 3111 163 7 2 0 0 0 02834 3111 164 9.442500+6 0.000000+0 1.200000+7 2.80400-10 1.300000+7 9.923000-82834 3111 165 1.450000+7 8.834200-6 1.600000+7 1.143200-4 1.750000+7 5.735800-42834 3111 166 2.000000+7 2.715700-3 0.000000+0 0.000000+0 0.000000+0 0.000000+02834 3111 167 2834 3 0 168 2834 0 0 169 0 0 0 170 2.806200+4 6.139600+1 1 0 0 12837 1451 1 0.000000+0 0.000000+0 0 0 0 62837 1451 2 1.000000+0 0.000000+0 0 0 10 62837 1451 3 0.000000+0 0.000000+0 0 0 174 62837 1451 4 28-NI- 62 ORNL EVAL-OCT89 HETRICK,FU,LARSON 2837 1451 5 ORNL/TM10219,ENDF-344 DIST-APR90 900221 2837 1451 6 ----ENDF/B-VI MATERIAL 2837 2837 1451 7 -----INCIDENT NEUTRON DATA 2837 1451 8 ------ENDF-6 FORMAT 2837 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2837 1451 10 ACTIVATION I 2837 1451 11 ******************************************************************2837 1451 12 THIS WORK EMPLOYED THE HAUSER-FESHBACH CODE TNG (1,2,3). 2837 1451 13 THE TNG CODE PROVIDES ENERGY AND ANGULAR DISTRIBUTIONS OF 2837 1451 14 PARTICLES EMITTED IN THE COMPOUND AND PRE-COMPOUND REACTIONS, 2837 1451 15 ENSURES CONSISTENCY AMONG ALL REACTIONS, AND MAINTAINS ENERGY 2837 1451 16 BALANCE. DETAILS PERTINENT TO THE CONTENTS OF THIS EVALUATION 2837 1451 17 CAN BE FOUND IN REFERENCE (4). 2837 1451 18 2837 1451 19 ----- DESCRIPTION OF FILES 2837 1451 20 (MF-MT) 2837 1451 21 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2837 1451 22 2-151 RESONANCE PARAMETERS; TAKEN FROM THE COMPILATION OF 2837 1451 23 MUGHABGHAB (5). FROM 1.E-5 EV TO 600 KEV THE SCATTERING 2837 1451 24 CROSS SECTION IS GIVEN COMPLETELY BY THE RESONANCE 2837 1451 25 PARAMETERS. FOR TOTAL AND CAPTURE, A CONTRIBUTION IS ADDED2837 1451 26 FROM 10-600 KEV DUE TO THE CAPTURE CROSS SECTION (SEE 2837 1451 27 3-102 BELOW). NO BACKGROUND FILES ARE GIVEN. 2837 1451 28 THERMAL CROSS SECTIONS HAVE VALUES: TOTAL 24.3 B, 2837 1451 29 ELASTIC SCATTERING 9.89 B, AND CAPTURE 14.4 B. 2837 1451 30 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2837 1451 31 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2837 1451 32 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2837 1451 33 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2837 1451 34 3-1 TOTAL CROSS SECTION - 1.E-5 EV TO 600 KEV, GIVEN BY 2837 1451 35 RESONANCE PARAMETERS AND A CONTRIBUTION FROM 10 TO 600 KEV2837 1451 36 THAT SUPPLEMENTS THE RESONANCE CAPTURE. FROM 600 KEV TO 2837 1451 37 20 MEV, NAT NI DATA OF REF. (6) WERE USED AS NO 62NI DATA 2837 1451 38 AVAILABLE. 2837 1451 39 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2837 1451 40 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2837 1451 41 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2837 1451 42 3-28, 3-102, 3-103, 3-104, AND 3-107. 2837 1451 43 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2837 1451 44 .., 3-54, AND 3-91 2837 1451 45 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2837 1451 46 CODE (1,2,3,4). NO DATA AVAILABLE. 2837 1451 47 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2837 1451 48 CODE (1,2,3,4). NO DATA AVAILABLE OTHER THAN A EMISSION. 2837 1451 49 3-28 (N,NP)+(N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2837 1451 50 CODE (1,2,3,4). AVAILABLE DATA DISAGREE, BUT DATA OF 2837 1451 51 QAIM (7) FOR (N,NP)+(N,PN) INCLUDES (N,D). THUS, ENDF/B-V 2837 1451 52 NAT NI (N,D) DATA (8) WAS NORMALIZED SO THAT THE TNG CALC.2837 1451 53 VALUE FOR (N,NP)+(N,PN), + THE (N,D) VALUE, FIT THE QAIM'S2837 1451 54 DATA FOR (N,NP)+(N,PN)+(N,D). 2837 1451 55 3-51 TO 3-54 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2837 1451 56 FROM TNG (1,2,3,4). 2837 1451 57 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2837 1451 58 CALCULATED). 2837 1451 59 3-102 (N,G) CAPTURE CROSS SECTION GIVEN BY RESONANCE PARAMETERS 2837 1451 60 FROM 1.E-5 EV TO 10 KEV. WHILE THE RESONANCE PARAMETERS 2837 1451 61 CONTRIBUTE UP TO 600 KEV, AN ADDITIONAL CONTRIBUTION FROM 2837 1451 62 TNG IS INCLUDED FROM 10 TO 600 KEV IN 3/102, DUE TO INCOM-2837 1451 63 PLETE EXPERIMENTAL CAPTURE RESONANCE INFORMATION. THE SAME2837 1451 64 NORMALIZATION (0.4) USED FOR 58,60NI WAS ASSUMED FOR 62NI;2837 1451 65 THE NORMALIZED TNG CALCULATIONS WERE USED FROM 600 KEV 2837 1451 66 TO 20 MEV. 2837 1451 67 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2837 1451 68 CODE (1,2,3,4). 2837 1451 69 3-104 (N,D) CROSS SECTIONS WERE TAKEN FROM THE ENDF/B-V FILE (8)2837 1451 70 FOR NAT NI BUT NORMALIZED TO BE SMALLER BY A FACTOR OF 5.52837 1451 71 SO THAT THE (N,NP)+(N,PN)+(N,D) CROSS SECTION MATCHED THE 2837 1451 72 DATA OF QAIM (7). 2837 1451 73 3-107 (N,A) CROSS SECTIONS WERE TAKEN FROM THE ENDF/B-V 2837 1451 74 ACTIVATION FILE BUT NORMALIZED TO BE SMALLER BY A FACTOR 2837 1451 75 OF 1.9 SO THAT THE CROSS SECTIONS FIT THE AVAILABLE DATA 2837 1451 76 OF QAIM ET AL. (9) AND KNEFF ET AL (10). 2837 1451 77 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2837 1451 78 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2837 1451 79 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2837 1451 80 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2837 1451 81 PARAMETERS IN 2/151. 2837 1451 82 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2837 1451 83 NEUTRON AND 61NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2837 1451 84 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2837 1451 85 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2837 1451 86 EACH PRODUCT. ISOTROPY IS ASSUMED. 2837 1451 87 6-22 (N,NA)+(N,AN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2837 1451 88 NEUTRON, ALPHA, AND 58FE RESIDUAL, AND ENERGY DEPENDENT 2837 1451 89 YIELD BASED ON THE TNG CALCULATED GAMMA-RAY SPECTRA FOR 2837 1451 90 THE GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE 2837 1451 91 GIVEN FOR EACH PRODUCT. ISOTROPY IS ASSUMED. 2837 1451 92 6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2837 1451 93 NEUTRON, P, AND 61CO RESIDUAL, AND ENERGY DEPENDENT YIELD2837 1451 94 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2837 1451 95 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2837 1451 96 EACH PRODUCT. ISOTROPY IS ASSUMED. 2837 1451 97 6-51 THROUGH 6-54 INELASTIC SCATTERING EXCITING LEVELS; 2837 1451 98 ASSUMED ISOTROPIC. 2837 1451 99 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2837 1451 100 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 62NI 2837 1451 101 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2837 1451 102 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2837 1451 103 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2837 1451 104 FOR EACH. ISOTROPY IS ASSUMED. 2837 1451 105 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2837 1451 106 AND 62CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2837 1451 107 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2837 1451 108 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2837 1451 109 PRODUCT. ISOTROPY IS ASSUMED. 2837 1451 110 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2837 1451 111 AND 59FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2837 1451 112 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2837 1451 113 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2837 1451 114 PRODUCT. ISOTROPY IS ASSUMED. 2837 1451 115 12-51 THROUGH 12-54 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2837 1451 116 12-102 (N,G) CAPTURE; MULTIPLICITIES FOR ENERGIES LESS THAN 2837 1451 117 1.0 MEV WERE TAKEN FROM ENDF/B-V, BUT ADJUSTED FOR ENERGY 2837 1451 118 BALANCE; TNG CALCULATIONS WERE USED FOR EN = 2 AND 5 MEV. 2837 1451 119 14-51 THROUGH 14-54 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2837 1451 120 ASSUMED TO BE ISOTROPIC. 2837 1451 121 15-102 (N,G) CAPTURE; AS IN 12-102. 2837 1451 122 2837 1451 123 -------------------------------------------------------------- 2837 1451 124 UNCERTAINTY FILES 2837 1451 125 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2837 1451 126 REQUIRED BY ENDF/B-VI. 2837 1451 127 2837 1451 128 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 10 EV. FROM 10 2837 1451 129 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2837 1451 130 33-2 FROM 1.E-5 TO 10 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2837 1451 131 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 10 EV TO 2837 1451 132 20 MEV THE FILES ARE DERIVED. 2837 1451 133 33-3 FROM 1.E-5 TO 600 KEV UNCERTAINTIES ARE DERIVED. FROM 6002837 1451 134 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82837 1451 135 33-4 UNCERTAINTIES ARE ALL DERIVED. 2837 1451 136 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG 2837 1451 137 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2837 1451 138 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2837 1451 139 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2837 1451 140 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2837 1451 141 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2837 1451 142 ENERGIES, AND CALCULATED RESULTS ABOVE 600 KEV. 2837 1451 143 33-103 UNCERTAINTIES ESTIMATED FROM TNG. 2837 1451 144 33-104 UNCERTAINTIES ESTIMATED, BASED ON DATA. 2837 1451 145 33-107 UNCERTAINTIES ESTIMATED FROM TNG. 2837 1451 146 2837 1451 147 REFERENCES: 2837 1451 148 (1) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2837 1451 149 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2837 1451 150 MOMENTUM," ORNL/TM-7042 (1980). 2837 1451 151 (2) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2837 1451 152 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2837 1451 153 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2837 1451 154 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2837 1451 155 NATIONAL LAB. 2837 1451 156 (3) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2837 1451 157 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2837 1451 158 (4) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2837 1451 159 -INDUCED CROSS SECTIONS FOR 58,60NI FROM 1 TO 20 MEV AND 2837 1451 160 COMPARISONS WITH EXPERIMENT," ORNL/TM-10219,ENDF-344 (1987). 2837 1451 161 (5) S.F. MUGHABGHAB, M. DIVADEENAM, AND N.E. HOLDEN, "NEUTRON 2837 1451 162 CROSS SECTIONS, VOL. 1, NEUTRON RESONANCE PARAMETERS AND 2837 1451 163 THERMAL CROSS SECTIONS, PART A, Z=1-60," ACADEMIC 2837 1451 164 PRESS (1981). 2837 1451 165 (6) D.C. LARSON, N.M. LARSON, J.A.HARVEY, N.W. HILL AND C.H. 2837 1451 166 JOHNSON, "APPLICATION OF NEW TECHNIQUES TO ORELA NEUTRON 2837 1451 167 TRANSMISSION MEASUREMENTS AND THEIR UNCERTAINTY ANALYSIS: 2837 1451 168 THE CASE OF NATURAL NICKEL FROM 2 KEV TO 20 MEV", ORNL/TM82032837 1451 169 ENDF-333, OCTOBER 1983. 2837 1451 170 (7) S.M. QAIM, NUCL. PHYS., A382, 255-268 (1982). 2837 1451 171 (8) M. DIVADEENAM, "NI ELEMENTAL NEUTRON INDUCED REACTION CROSS 2837 1451 172 SECTION EVALUATION", BNL-NCS-51346, ENDF-294 (MARCH 1979) 2837 1451 173 (9) S.M. QAIM, R. WOLFLE, M.M. RAHMAN, AND H. OLLIG, NUCL. SCI. 2837 1451 174 ENG., 88, 143-153 (1984). 2837 1451 175 (10) D.W. KNEFF, B.M. OLIVER, H. FARRAR,IV, AND L.R. GREENWOOD, 2837 1451 176 NUCL. SCI. ENG., 92, 491-524 (1986) 2837 1451 177 2837 1451 178 1 451 184 12837 1451 179 2 151 63 12837 1451 180 3 102 13 12837 1451 181 3 103 9 12837 1451 182 3 104 11 12837 1451 183 3 107 14 12837 1451 184 2837 1 0 185 2837 0 0 186 2.806200+4 6.139600+1 0 0 1 02837 2151 187 2.806200+4 1.000000+0 0 0 1 02837 2151 188 1.000000-5 6.000000+5 1 3 0 12837 2151 189 0.000000+0 6.200000-1 0 0 2 22837 2151 190 6.139600+1 0.000000+0 0 0 180 302837 2151 191 -7.700000+1 5.000000-1 1.360000-1 9.100000-1 0.000000+0 0.000000+02837 2151 192 4.540000+3 5.000000-1 1.880000+3 7.600000-1 0.000000+0 0.000000+02837 2151 193 4.287000+4 5.000000-1 3.400000+2 9.075000-1 0.000000+0 0.000000+02837 2151 194 9.470000+4 5.000000-1 2.500000+3 5.600000-1 0.000000+0 0.000000+02837 2151 195 1.056500+5 5.000000-1 4.600000+3 1.400000+0 0.000000+0 0.000000+02837 2151 196 1.493000+5 5.000000-1 1.400000+2 9.075000-1 0.000000+0 0.000000+02837 2151 197 2.295000+5 5.000000-1 6.250000+3 9.075000-1 0.000000+0 0.000000+02837 2151 198 2.422000+5 5.000000-1 7.800000+2 9.075000-1 0.000000+0 0.000000+02837 2151 199 2.805000+5 5.000000-1 4.800000+3 9.075000-1 0.000000+0 0.000000+02837 2151 200 2.860000+5 5.000000-1 1.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 201 3.040000+5 5.000000-1 8.000000+2 9.075000-1 0.000000+0 0.000000+02837 2151 202 3.270000+5 5.000000-1 5.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 203 3.442000+5 5.000000-1 7.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 204 3.562000+5 5.000000-1 2.000000+3 9.075000-1 0.000000+0 0.000000+02837 2151 205 3.745000+5 5.000000-1 2.500000+2 9.075000-1 0.000000+0 0.000000+02837 2151 206 3.825000+5 5.000000-1 1.250000+3 9.075000-1 0.000000+0 0.000000+02837 2151 207 3.885000+5 5.000000-1 4.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 208 4.015000+5 5.000000-1 1.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 209 4.230000+5 5.000000-1 1.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 210 4.330000+5 5.000000-1 6.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 211 4.440000+5 5.000000-1 3.500000+2 9.075000-1 0.000000+0 0.000000+02837 2151 212 4.580000+5 5.000000-1 5.000000+2 9.075000-1 0.000000+0 0.000000+02837 2151 213 4.750000+5 5.000000-1 1.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 214 4.885000+5 5.000000-1 4.000000+3 9.075000-1 0.000000+0 0.000000+02837 2151 215 4.980000+5 5.000000-1 1.500000+3 9.075000-1 0.000000+0 0.000000+02837 2151 216 5.390000+5 5.000000-1 2.000000+3 9.075000-1 0.000000+0 0.000000+02837 2151 217 5.718000+5 5.000000-1 4.000000+3 9.075000-1 0.000000+0 0.000000+02837 2151 218 5.810000+5 5.000000-1 5.000000+2 9.075000-1 0.000000+0 0.000000+02837 2151 219 5.835000+5 5.000000-1 1.000000+4 9.075000-1 0.000000+0 0.000000+02837 2151 220 5.905000+5 5.000000-1 2.000000+3 9.075000-1 0.000000+0 0.000000+02837 2151 221 6.139600+1 0.000000+0 1 0 162 272837 2151 222 5.691000+4 1.500000+0 2.800000+1 2.933300-1 0.000000+0 0.000000+02837 2151 223 1.375000+5 5.000000-1 1.270000+2 2.933300-1 0.000000+0 0.000000+02837 2151 224 1.882000+5 1.500000+0 4.500000+1 2.933300-1 0.000000+0 0.000000+02837 2151 225 2.147000+5 5.000000-1 1.900000+2 2.933300-1 0.000000+0 0.000000+02837 2151 226 2.595000+5 1.500000+0 5.650000+1 2.933300-1 0.000000+0 0.000000+02837 2151 227 2.725000+5 1.500000+0 1.665000+2 2.933300-1 0.000000+0 0.000000+02837 2151 228 2.970000+5 1.500000+0 1.000000+2 2.933300-1 0.000000+0 0.000000+02837 2151 229 2.995000+5 5.000000-1 5.000000+2 2.933300-1 0.000000+0 0.000000+02837 2151 230 3.155000+5 1.500000+0 1.190000+2 2.933300-1 0.000000+0 0.000000+02837 2151 231 3.190000+5 1.500000+0 1.875000+2 2.933300-1 0.000000+0 0.000000+02837 2151 232 3.230000+5 5.000000-1 5.800000+2 2.933300-1 0.000000+0 0.000000+02837 2151 233 3.520000+5 1.500000+0 1.395000+2 2.933300-1 0.000000+0 0.000000+02837 2151 234 3.640000+5 1.500000+0 9.700000+1 2.933300-1 0.000000+0 0.000000+02837 2151 235 4.033000+5 5.000000-1 3.920000+2 2.933300-1 0.000000+0 0.000000+02837 2151 236 4.203000+5 1.500000+0 4.065000+2 2.933300-1 0.000000+0 0.000000+02837 2151 237 4.498000+5 1.500000+0 1.250000+2 2.933300-1 0.000000+0 0.000000+02837 2151 238 4.500000+5 5.000000-1 2.360000+2 2.933300-1 0.000000+0 0.000000+02837 2151 239 4.618000+5 1.500000+0 2.750000+2 2.933300-1 0.000000+0 0.000000+02837 2151 240 4.800000+5 1.500000+0 1.620000+2 2.933300-1 0.000000+0 0.000000+02837 2151 241 4.935000+5 5.000000-1 9.340000+2 2.933300-1 0.000000+0 0.000000+02837 2151 242 5.155000+5 1.500000+0 7.250000+1 2.933300-1 0.000000+0 0.000000+02837 2151 243 5.220000+5 1.500000+0 1.950000+2 2.933300-1 0.000000+0 0.000000+02837 2151 244 5.290000+5 1.500000+0 8.450000+2 2.933300-1 0.000000+0 0.000000+02837 2151 245 5.355000+5 5.000000-1 1.390000+3 2.933300-1 0.000000+0 0.000000+02837 2151 246 5.540000+5 1.500000+0 3.375000+2 2.933300-1 0.000000+0 0.000000+02837 2151 247 5.685000+5 5.000000-1 8.430000+2 2.933300-1 0.000000+0 0.000000+02837 2151 248 5.995000+5 5.000000-1 9.050000+2 2.933300-1 0.000000+0 0.000000+02837 2151 249 2837 2 0 250 2837 0 0 251 2.806200+4 6.139600+1 0 99 0 02837 3102 252 6.839000+6 6.839000+6 0 0 1 292837 3102 253 29 2 0 0 0 02837 3102 254 1.000000-5 0.000000+0 1.000000+4 0.000000+0 1.000000+4 7.000000-22837 3102 255 4.000000+4 5.400000-2 5.000000+4 4.000000-2 6.000000+4 4.200000-22837 3102 256 1.000000+5 2.000000-2 4.000000+5 9.000000-3 6.000000+5 8.400000-32837 3102 257 6.000000+5 9.200000-3 7.000000+5 8.640000-3 8.000000+5 8.480000-32837 3102 258 9.000000+5 8.320000-3 1.000000+6 7.840000-3 1.142100+6 8.300000-32837 3102 259 1.187100+6 8.192000-3 1.192100+6 8.184000-3 1.197100+6 6.904000-32837 3102 260 1.242100+6 5.772000-3 2.000000+6 4.160000-3 3.000000+6 3.550000-32837 3102 261 4.000000+6 2.680000-3 5.000000+6 1.720000-3 7.500000+6 7.600000-42837 3102 262 1.000000+7 2.210000-4 1.200000+7 2.250000-4 1.450000+7 2.430000-42837 3102 263 1.750000+7 1.940000-4 2.000000+7 1.150000-4 0.000000+0 0.000000+02837 3102 264 2837 3 0 265 2.806200+4 6.139600+1 0 0 0 02837 3103 266 -4.459000+6-4.459000+6 0 0 1 182837 3103 267 18 2 0 0 0 02837 3103 268 4.531600+6 0.000000+0 5.500000+6 3.433900-8 6.000000+6 4.647200-62837 3103 269 6.500000+6 6.488600-5 7.000000+6 2.914100-4 7.500000+6 7.246500-42837 3103 270 8.000000+6 1.332100-3 8.500000+6 2.118000-3 9.000000+6 3.108900-32837 3103 271 9.500000+6 4.160700-3 1.000000+7 5.551600-3 1.100000+7 9.102700-32837 3103 272 1.200000+7 1.461800-2 1.300000+7 2.198300-2 1.450000+7 3.451600-22837 3103 273 1.600000+7 4.111400-2 1.750000+7 4.166400-2 2.000000+7 3.815100-22837 3103 274 2837 3 0 275 2.806200+4 6.139600+1 0 0 0 02837 3104 276 -8.912870+6-8.912870+6 0 0 1 242837 3104 277 24 2 0 0 0 02837 3104 278 9.058000+6 0.000000+0 9.500000+6 1.367700-4 1.000000+7 6.215500-42837 3104 279 1.047400+7 8.586200-4 1.050000+7 8.715600-4 1.100000+7 1.050600-32837 3104 280 1.150000+7 1.221200-3 1.200000+7 1.432700-3 1.250000+7 1.731300-32837 3104 281 1.300000+7 2.095500-3 1.350000+7 2.464000-3 1.400000+7 2.883800-32837 3104 282 1.450000+7 3.294900-3 1.500000+7 3.792000-3 1.550000+7 4.079600-32837 3104 283 1.600000+7 4.733100-3 1.650000+7 5.187300-3 1.700000+7 5.633600-32837 3104 284 1.750000+7 6.138000-3 1.800000+7 6.570000-3 1.850000+7 6.931100-32837 3104 285 1.900000+7 7.162700-3 1.950000+7 7.332000-3 2.000000+7 7.405800-32837 3104 286 2837 3 0 287 2.806200+4 6.139600+1 0 0 0 02837 3107 288 -4.374000+5-4.374000+5 0 0 1 332837 3107 289 33 2 0 0 0 02837 3107 290 4.445200+5 0.000000+0 4.500000+6 2.631600-6 5.000000+6 1.121000-52837 3107 291 5.500000+6 7.894700-5 6.000000+6 1.157900-4 6.500000+6 3.263200-42837 3107 292 7.000000+6 7.894700-4 7.500000+6 1.631600-3 8.000000+6 2.684200-32837 3107 293 8.500000+6 4.052600-3 9.000000+6 5.263200-3 9.500000+6 6.052600-32837 3107 294 1.000000+7 6.631600-3 1.050000+7 7.052600-3 1.100000+7 7.500000-32837 3107 295 1.150000+7 8.315800-3 1.200000+7 9.421100-3 1.250000+7 1.078900-22837 3107 296 1.300000+7 1.247400-2 1.350000+7 1.421100-2 1.400000+7 1.594700-22837 3107 297 1.450000+7 1.763200-2 1.500000+7 1.842100-2 1.550000+7 1.842100-22837 3107 298 1.600000+7 1.721100-2 1.650000+7 1.605300-2 1.700000+7 1.526300-22837 3107 299 1.750000+7 1.447400-2 1.800000+7 1.368400-2 1.850000+7 1.289500-22837 3107 300 1.900000+7 1.221100-2 1.950000+7 1.131600-2 2.000000+7 1.031600-22837 3107 301 2837 3 0 302 2837 0 0 303 0 0 0 304 2.806400+4 6.337900+1 -1 0 0 12843 1451 1 0.000000+0 0.000000+0 0 0 0 62843 1451 2 1.000000+0 0.000000+0 0 0 10 62843 1451 3 0.000000+0 0.000000+0 0 0 175 22843 1451 4 28-NI- 64 ORNL EVAL-OCT89 HETRICK,FU,LARSON 2843 1451 5 ORNL/TM10219,ENDF-344 DIST-APR90 900221 2843 1451 6 ----ENDF/B-VI MATERIAL 2843 2843 1451 7 -----INCIDENT NEUTRON DATA 2843 1451 8 ------ENDF-6 FORMAT 2843 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2843 1451 10 ACTIVATION I 2843 1451 11 ******************************************************************2843 1451 12 THIS WORK EMPLOYED THE HAUSER-FESHBACH CODE TNG (1,2,3). 2843 1451 13 THE TNG CODE PROVIDES ENERGY AND ANGULAR DISTRIBUTIONS OF 2843 1451 14 PARTICLES EMITTED IN THE COMPOUND AND PRE-COMPOUND REACTIONS, 2843 1451 15 ENSURES CONSISTENCY AMONG ALL REACTIONS, AND MAINTAINS ENERGY 2843 1451 16 BALANCE. DETAILS PERTINENT TO THE CONTENTS OF THIS EVALUATION 2843 1451 17 CAN BE FOUND IN REFERENCE (4). 2843 1451 18 2843 1451 19 ----- DESCRIPTION OF FILES 2843 1451 20 (MF-MT) 2843 1451 21 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2843 1451 22 2-151 RESONANCE PARAMETERS; TAKEN FROM THE COMPILATION OF 2843 1451 23 MUGHABGHAB (5). FROM 1.E-5 EV TO 600 KEV THE SCATTERING 2843 1451 24 CROSS SECTION IS GIVEN COMPLETELY BY THE RESONANCE 2843 1451 25 PARAMETERS. FOR TOTAL AND CAPTURE, A CONTRIBUTION IS 2843 1451 26 ADDED FROM 40-600 KEV DUE TO THE CAPTURE CROSS SECTION 2843 1451 27 (SEE 3-102 BELOW). NO BACKGROUND FILES ARE GIVEN. 2843 1451 28 THERMAL CROSS SECTIONS ARE: TOTAL 1.53 B, ELASTIC SCATTER-2843 1451 29 ING .0163, AND CAPTURE 1.52 B. 2843 1451 30 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2843 1451 31 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2843 1451 32 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2843 1451 33 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2843 1451 34 3-1 TOTAL CROSS SECTION: 1.E-5 EV TO 600 KEV GIVEN BY 2843 1451 35 RESONANCE PARAMETERS, AND A CONTRIBUTION FROM 40 TO 600 2843 1451 36 KEV SUPPLEMENTS THE RESONANCE CAPTURE. FROM 600 KEV TO 2843 1451 37 20 MEV, NAT NI DATA OF REF. (6) WERE USED AS NO 64NI 2843 1451 38 DATA AVAILABLE. 2843 1451 39 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2843 1451 40 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2843 1451 41 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2843 1451 42 3-28, 3-102, 3-103, 3-104, AND 3-107. 2843 1451 43 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, AND 2843 1451 44 3-91. 2843 1451 45 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2843 1451 46 CODE (1,2,3,4). NO DATA AVAILABLE. 2843 1451 47 3-22 (N,NA)+(N,AN) CROSS SECTIONS WERE CALCULATED BY TNG. NO 2843 1451 48 DATA AVAILABLE OTHER THAN TOTAL ALPHA EMISSION CROSS 2843 1451 49 SECTION. 2843 1451 50 3-28 (N,NP)+(N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2843 1451 51 CODE (1,2,3,4). SPARSE DATA AVAILABLE DISAGREE. NOTE 2843 1451 52 THAT THE (N,D) CROSS SECTION WAS TAKEN FROM ENDF/B-V FOR 2843 1451 53 NAT NI (7) BUT NORMALIZED TO BE SMALLER BY A FACTOR OF 6.42843 1451 54 SO THAT THE (N,NP)+(N,PN)+(N,D) AGREES WITH THE DATA OF 2843 1451 55 QAIM (8). (SEE 3-104 BELOW). 2843 1451 56 3-51 TO 3-52 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2843 1451 57 FROM TNG (1,2,3,4). 2843 1451 58 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2843 1451 59 CALCULATED). 2843 1451 60 3-102 (N,G) CAPTURE CROSS SECTION IS GIVEN COMPLETELY BY THE 2843 1451 61 RESONANCE PARAMETERS FROM 1.E-5 EV TO 40 KEV. WHILE THE 2843 1451 62 RESONANCE PARAMETERS CONTRIBUTE UP TO 600 KEV, AN 2843 1451 63 ADDITIONAL CONTRIBUTION FROM THE TNG CALCULATION IS 2843 1451 64 INCLUDED FROM 40 TO 600 KEV IN 3/102, DUE TO INCOMPLETE 2843 1451 65 EXPERIMENTAL CAPTURE RESONANCE INFORMATION. THE SAME 2843 1451 66 NORMALIZATION (0.4) USED FOR 58,60NI WAS ASSUMED FOR 64NI;2843 1451 67 THE NORMALIZED TNG CALCULATIONS WERE USED FROM 600 KEV TO 2843 1451 68 20 MEV. 2843 1451 69 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2843 1451 70 CODE (1,2,3,4). 2843 1451 71 3-104 (N,D) CROSS SECTIONS WERE TAKEN FROM ENDF/B-V FOR NAT. NI 2843 1451 72 BUT NORMALIZED TO BE SMALLER BY A FACTOR OF 6.4 SO THAT 2843 1451 73 THE (N,NP)+(N,PN)+(N,D) MATCHED THE DATA OF QAIM (8) AT 2843 1451 74 14.5 MEV. 2843 1451 75 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2843 1451 76 TNG CODE (1,2,3,4) BUT NORMALIZED TO BE LARGER BY A FACTOR2843 1451 77 OF 12.5 SO THAT THE CROSS SECTIONS WOULD FIT THE DATA OF 2843 1451 78 QAIM ET AL. (9) AND KNEFF ET AL. (10). 2843 1451 79 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2843 1451 80 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2843 1451 81 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2843 1451 82 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2843 1451 83 PARAMETERS IN 2/151. 2843 1451 84 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2843 1451 85 NEUTRON AND 63NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2843 1451 86 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2843 1451 87 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2843 1451 88 EACH PRODUCT. ISOTROPY IS ASSUMED. 2843 1451 89 6-22 (N,NA)+(N,AN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2843 1451 90 NEUTRON, ALPHA, AND 60FE RESIDUAL, AND ENERGY DEPENDENT 2843 1451 91 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2843 1451 92 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2843 1451 93 FOR EACH PRODUCT. ISOTROPY IS ASSUMED. 2843 1451 94 6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2843 1451 95 NEUTRON, P, AND 63CO RESIDUAL, AND ENERGY DEPENDENT YIELD 2843 1451 96 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2843 1451 97 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2843 1451 98 EACH PRODUCT. ISOTROPY IS ASSUMED. 2843 1451 99 6-51 THROUGH 6-52 INELASTIC SCATTERING EXCITING LEVELS; 2843 1451 100 ASSUMED ISOTROPIC. 2843 1451 101 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2843 1451 102 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 64NI 2843 1451 103 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2843 1451 104 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2843 1451 105 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2843 1451 106 FOR EACH. ISOTROPY IS ASSUMED. 2843 1451 107 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2843 1451 108 AND 64CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2843 1451 109 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2843 1451 110 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2843 1451 111 PRODUCT. ISOTROPY IS ASSUMED. 2843 1451 112 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2843 1451 113 AND 61FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2843 1451 114 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2843 1451 115 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2843 1451 116 PRODUCT. ISOTROPY IS ASSUMED. 2843 1451 117 12-51 THROUGH 12-52 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN. 2843 1451 118 12-102 (N,G) CAPTURE; MULTIPLICITIES FOR ENERGIES LESS THAN 2843 1451 119 1.0 MEV WERE TAKEN FROM ENDF/B-V, BUT ADJUSTED FOR ENERGY 2843 1451 120 BALANCE; TNG CALCULATIONS WERE USED FOR EN = 2 AND 5 MEV. 2843 1451 121 14-51 THROUGH 14-52 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2843 1451 122 ASSUMED TO BE ISOTROPIC. 2843 1451 123 15-102 (N,G) CAPTURE; AS IN 12-102. 2843 1451 124 2843 1451 125 -------------------------------------------------------------- 2843 1451 126 UNCERTAINTY FILES 2843 1451 127 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2843 1451 128 REQUIRED BY ENDF/B-VI. 2843 1451 129 2843 1451 130 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 10 EV. FROM 10 2843 1451 131 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2843 1451 132 33-2 FROM 1.E-5 TO 10 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2843 1451 133 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 10 EV TO 2843 1451 134 20 MEV THE FILES ARE DERIVED. 2843 1451 135 33-3 FROM 1.E-5 TO 600 KEV UNCERTAINTIES ARE DERIVED. FROM 6002843 1451 136 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82843 1451 137 33-4 UNCERTAINTIES ARE ALL DERIVED. 2843 1451 138 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG 2843 1451 139 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2843 1451 140 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2843 1451 141 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2843 1451 142 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2843 1451 143 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2843 1451 144 ENERGIES, AND CALCULATED RESULTS ABOVE 600 KEV. 2843 1451 145 33-103 UNCERTAINTIES ESTIMATED FROM TNG. 2843 1451 146 33-104 UNCERTAINTIES ESTIMATED, BASED ON DATA. 2843 1451 147 33-107 UNCERTAINTIES ESTIMATED FROM TNG. 2843 1451 148 2843 1451 149 REFERENCES: 2843 1451 150 (1) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2843 1451 151 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2843 1451 152 MOMENTUM," ORNL/TM-7042 (1980). 2843 1451 153 (2) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2843 1451 154 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2843 1451 155 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2843 1451 156 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2843 1451 157 NATIONAL LAB. 2843 1451 158 (3) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2843 1451 159 STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986). 2843 1451 160 (4) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2843 1451 161 -INDUCED CROSS SECTIONS FOR 58,60NI FROM 1 TO 20 MEV AND 2843 1451 162 COMPARISONS WITH EXPERIMENT," ORNL/TM-10219,ENDF-344 (1987). 2843 1451 163 (5) S.F. MUGHABGHAB, M. DIVADEENAM, AND N.E. HOLDEN, "NEUTRON 2843 1451 164 CROSS SECTIONS, VOL. 1, NEUTRON RESONANCE PARAMETERS AND 2843 1451 165 THERMAL CROSS SECTIONS, PART A, Z=1-60," ACADEMIC 2843 1451 166 PRESS (1981). 2843 1451 167 (6) D.C. LARSON, N.M. LARSON, J.A.HARVEY, N.W. HILL AND C.H. 2843 1451 168 JOHNSON, "APPLICATION OF NEW TECHNIQUES TO ORELA NEUTRON 2843 1451 169 TRANSMISSION MEASUREMENTS AND THEIR UNCERTAINTY ANALYSIS: 2843 1451 170 THE CASE OF NATURAL NICKEL FROM 2 KEV TO 20 MEV", ORNL/TM82032843 1451 171 ENDF-333, OCTOBER 1983. 2843 1451 172 (7) M. DIVADEENAM, "NI ELEMENTAL NEUTRON INDUCED REACTION CROSS 2843 1451 173 SECTION EVALUATION", BNL-NCS-51346, ENDF-294 (MARCH 1979) 2843 1451 174 (8) S.M. QAIM, NUCL. PHYS., A382, 255-268 (1982). 2843 1451 175 (9) S.M. QAIM, R. WOLFLE, M.M. RAHMAN, AND H. OLLIG, NUCL. SCI. 2843 1451 176 ENG., 88, 143-153 (1984). 2843 1451 177 (10) D.W. KNEFF, B.M. OLIVER, H. FARRAR,IV, AND L.R. GREENWOOD, 2843 1451 178 NUCL. SCI. ENG., 92, 491-524 (1986) 2843 1451 179 1 451 181 12843 1451 180 3 22 6 12843 1451 181 2843 1 0 182 2843 0 0 183 2.806400+4 6.337900+1 0 0 0 02843 3 22 184 -8.082000+6-8.082000+6 0 0 1 72843 3 22 185 7 2 0 0 0 02843 3 22 186 8.209500+6 0.000000+0 1.200000+7 7.65690-10 1.300000+7 8.665900-82843 3 22 187 1.450000+7 5.059800-6 1.600000+7 9.409700-5 1.750000+7 7.064600-42843 3 22 188 2.000000+7 3.043700-3 0.000000+0 0.000000+0 0.000000+0 0.000000+02843 3 22 189 2843 3 0 190 2843 0 0 191 0 0 0 192 2.906300+4 6.238900+1 1 0 0 12925 1451 1 0.000000+0 0.000000+0 0 0 0 62925 1451 2 1.000000+0 0.000000+0 0 0 10 62925 1451 3 0.000000+0 0.000000+0 0 0 228 92925 1451 4 29-CU- 63 ORNL EVAL-NOV89 HETRICK,FU,LARSON 2925 1451 5 ORNL/TM-9083,ENDF-337 DIST-APR90 900409 2925 1451 6 ----ENDF/B-VI MATERIAL 2925 2925 1451 7 -----INCIDENT NEUTRON DATA 2925 1451 8 ------ENDF-6 FORMAT 2925 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2925 1451 10 ACTIVATION I 2925 1451 11 ******************************************************************2925 1451 12 THIS WORK EMPLOYED SEVERAL NUCLEAR MODEL CODES INCLUDING THE 2925 1451 13 OPTICAL-MODEL CODE GENOA (1), THE DISTORTED WAVE BORN 2925 1451 14 APPROXIMATION (DWBA) PROGRAM DWUCK (2), AND THE HAUSER-FESHBACH 2925 1451 15 CODE TNG (3,4). THE TNG CODE PROVIDES ENERGY AND ANGULAR 2925 1451 16 DISTRIBUTIONS OF PARTICLES EMITTED IN THE COMPOUND AND PRE- 2925 1451 17 COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL REACTIONS, AND 2925 1451 18 MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE CONTENTS OF 2925 1451 19 THIS EVALUATION AND EXTENSIVE COMPARISONS OF CALCULATIONS WITH 2925 1451 20 EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5). 2925 1451 21 2925 1451 22 ----- DESCRIPTION OF FILES 2925 1451 23 (MF-MT) 2925 1451 24 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2925 1451 25 2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB(6). POINT2925 1451 26 WISE RECONSTRUCTION COMPARED WITH DATA (7) SHOWED POORER 2925 1451 27 FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2925 1451 28 99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT 2925 1451 29 WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2925 1451 30 FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN 2925 1451 31 AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND 2925 1451 32 COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO 2925 1451 33 TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES 2925 1451 34 SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION. 2925 1451 35 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2925 1451 36 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2925 1451 37 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2925 1451 38 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2925 1451 39 3-1 THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS 2925 1451 40 FROM 1.E-5 EV TO 99.5 KEV. FROM 1.E-5 TO 1 EV, -0.9B IS 2925 1451 41 GIVEN TO REDUCE THE ELASTIC AND GIVE THE CORRECT TOTAL 2925 1451 42 THERMAL CROSS SECTION (9.6 B). FROM 1 EV TO 170 EV THIS 2925 1451 43 GOES LINEARLY TO ZERO. A SMALL CONTRIBUTION FROM 3/102 IS2925 1451 44 REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151 2925 1451 45 REPRODUCES THE CAPTURE DATA. FROM 99.5 KEV TO 1.12 MEV 2925 1451 46 CU63 DATA FROM (7) IS USED, AFTER APPROPRIATE AVERAGING. 2925 1451 47 ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE. FROM 1.12 TO 2925 1451 48 4.0 MEV,NAT CU DATA OF PEREY (8) USED IN V5 IS RETAINED. 2925 1451 49 FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL (9) IS 2925 1451 50 AVERAGED AND USED. COMPARISONS FROM 1.2 TO 4.5 2925 1451 51 MEV WITH AVERAGED ARGONNE DATA FOR NAT CU (10) SHOW 2925 1451 52 1% AGREEMENT. 2925 1451 53 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2925 1451 54 SUBTRACTING THE NONELASTIC (3-3) FROM THE TOTAL. THE 2925 1451 55 THERMAL VALUE OF 5.1 B IS REPRODUCED. 2925 1451 56 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2925 1451 57 3-28, 3-102, 3-103, 3-104, 3-106, AND 3-107. 2925 1451 58 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2925 1451 59 .., 3-72, AND 3-91 2925 1451 60 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS (11) 2925 1451 61 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 62 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 63 SECTIONS (12). 2925 1451 64 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2925 1451 65 CODE (3,4,5). NO DATA AVAILABLE OTHER THAN A-EMISSION. 2925 1451 66 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2925 1451 67 CODE (3,4,5). DATA SCARCE FOR THIS REACTION (SEE (5)). 2925 1451 68 3-51 TO 3-72 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2925 1451 69 FROM TNG (3,4,5) WHICH INCLUDES DIRECT INTERACTION 2925 1451 70 CROSS SECTIONS FROM DWUCK (2) CALCULATIONS. EXTENSIVE 2925 1451 71 COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION 2925 1451 72 PROCESS ARE SHOWN IN (5). 2925 1451 73 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2925 1451 74 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA (5). 2925 1451 75 3-102 (N,G) DATA TAKEN FROM RESONANCE PARAMETERS FROM 1.E-5 EVTO2925 1451 76 99.5 KEV. A SMALL BACKGROUND IS GIVEN HERE WHICH WHEN 2925 1451 77 ADDED TO THE RESONACE CONTRIBUTION REPRODUCES EXPERIMENTAL2925 1451 78 DATA,INCLUDING THE THERMAL VALUE OF 4.50B. V5 DATA FROM 2925 1451 79 99.5 KEV TO 20.0 MEV WERE REPLACED BY POINTS ON A CURVE 2925 1451 80 DRAWN THROUGH DATA FROM THE CSISRS LIBRARY (5,13); RESULTS2925 1451 81 COMPARABLE TO EYE GUIDE IN REF (14). 2925 1451 82 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2925 1451 83 CODE (3,4,5). 2925 1451 84 3-104 (N,D) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED 2925 1451 85 NORMALIZED TO AVAILABLE DATA (5). 2925 1451 86 3-106 (N,3HE) CROSS SECTION - SHAPE OF (N,A) CROSS SECTION 2925 1451 87 USED NORMALIZED TO AVAILABLE DATA (15). 2925 1451 88 3-107 (N,A) CROSS SECTIONS WERE TAKEN FROM THE GLUCS (11) 2925 1451 89 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 90 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 91 SECTIONS (12). 2925 1451 92 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2925 1451 93 ELASTIC SCATTERING ARE RESULTS OF FITTING DATA WITH GENOA.2925 1451 94 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2925 1451 95 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2925 1451 96 PARAMETERS IN 2/151. 2925 1451 97 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2925 1451 98 NEUTRON AND 62CU RESIDUAL, AND ENERGY DEPENDENT YIELD 2925 1451 99 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2925 1451 100 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2925 1451 101 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2925 1451 102 THE OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION 2925 1451 103 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS (5). 2925 1451 104 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2925 1451 105 NEUTRON, ALPHA, AND 59CO RESIDUAL, AND ENERGY DEPENDENT 2925 1451 106 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2925 1451 107 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2925 1451 108 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2925 1451 109 FOR THE OUTGOING NEUTRON). (N,XA) AND (N,XG) D-D EMISSION2925 1451 110 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS (5). 2925 1451 111 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2925 1451 112 NEUTRON AND 62NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2925 1451 113 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2925 1451 114 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2925 1451 115 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2925 1451 116 THE OUTGOING NEUTRON). (N,XP) AND (N,XG) D-D EMISSION 2925 1451 117 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS (5). 2925 1451 118 6-51 THROUGH 6-72 INELASTIC SCATTERING EXCITING LEVELS; EACH 2925 1451 119 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2925 1451 120 AND 63CU RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2925 1451 121 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2925 1451 122 BY DWUCK (2) AND TNG (3,4,5)). EXTENSIVE COMPARISONS 2925 1451 123 WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN REF. (5). 2925 1451 124 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2925 1451 125 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 63CU 2925 1451 126 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2925 1451 127 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED2925 1451 128 NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH (ANGULAR 2925 1451 129 DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON). 2925 1451 130 (N,XN) AND (N,XG) D-D EMISSION DATA HEAVILY USED TO BENCH-2925 1451 131 MARK THE TNG CALCULATIONS (5). 2925 1451 132 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2925 1451 133 AND 63NI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2925 1451 134 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2925 1451 135 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2925 1451 136 PRODUCT. (N,XP) AND (N,XG) D-D EMISSION DATA USED TO 2925 1451 137 BENCHMARK THE TNG CALCULATIONS (5). 2925 1451 138 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2925 1451 139 AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2925 1451 140 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2925 1451 141 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2925 1451 142 PRODUCT. (N,XA) AND (N,XG) D-D EMISSION DATA USED TO 2925 1451 143 BENCHMARK THE TNG CALCULATIONS (5). 2925 1451 144 12-51 THROUGH 12-72 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2925 1451 145 BY HETRICK ET AL. (5) ARE GIVEN. 2925 1451 146 12-102 (N,G) CAPTURE; THERMAL VALUES TAKEN FROM DELFINI ET AL. 2925 1451 147 (16). HIGHER-ENERGY VALUES BASED ON TNG CALCULATIONS 2925 1451 148 USING PRIMARY BRANCHING RATIOS OF DELFINI ET AL. FOR 2925 1451 149 S-WAVES 2925 1451 150 14-51 THROUGH 14-72 GAMMA-RAY ANGULAR DISTRIBUTIONS ASSUMED TO 2925 1451 151 BE ISOTROPIC. 2925 1451 152 14-102 (N,G) CAPTURE; ISOTROPIC DISTRIBUTIONS ASSUMED 2925 1451 153 15-102 (N,G) CAPTURE; AS IN 12-102 2925 1451 154 -------------------------------------------------------------- 2925 1451 155 UNCERTAINTY FILES 2925 1451 156 ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS 2925 1451 157 REQUIRED BY ENDF/B-VI FORMATS 2925 1451 158 2925 1451 159 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV 2925 1451 160 EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8. 2925 1451 161 33-2 EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV2925 1451 162 33-3 DERIVED FROM 1.E-5 TO 99.5 KEV, EXPLICIT USING LB=1,8 FROM2925 1451 163 99.5 KEV TO 20 MEV. 2925 1451 164 33-4 DERIVED FROM THRESHOLD TO 20 MEV. 2925 1451 165 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS (11) 2925 1451 166 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 167 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 168 SECTIONS (12). 2925 1451 169 33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM TNG CALCULATION. 2925 1451 170 33-28 (N,NP) COVARIANCES ESTIMATED FROM TNG CALCULATION. 2925 1451 171 33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA 2925 1451 172 AND CALCULATIONS. 2925 1451 173 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2925 1451 174 ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS 2925 1451 175 DATA (5,13,14) FROM 99.5 KEV TO 20 MEV. 2925 1451 176 33-103 (N,P) COVARIANCES - ESTIMATED AS NO DATA AVAILABLE. 2925 1451 177 33-104 (N,D) COVARIANCES - ESTIMATED, BASED ON DATA. 2925 1451 178 33-106 (N,3HE) COVARIANCES - ESTIMATED, BASED ON DATA. 2925 1451 179 33-107 (N,A) COVARIANCES WERE TAKEN FROM THE GLUCS (11) 2925 1451 180 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 181 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 182 SECTIONS (12). 2925 1451 183 REFERENCES: 2925 1451 184 (1) F.G. PEREY, COMPUTER CODE GENOA, ORNL, UNPUBLISHED (1967). 2925 1451 185 (2) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2925 1451 186 COLORADO, UNPUBLISHED (1972). 2925 1451 187 (3) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2925 1451 188 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2925 1451 189 MOMENTUM," ORNL/TM-7042 (1980). ALSO, 2925 1451 190 C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2925 1451 191 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2925 1451 192 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2925 1451 193 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2925 1451 194 NATIONAL LAB. 2925 1451 195 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2925 1451 196 STATISTICAL MODEL CODE," ORNL/TM-10093 (AUGUST, 1986). 2925 1451 197 (5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2925 1451 198 -INDUCED CROSS SECTIONS FOR 63,65CU FROM 1 TO 20 MEV AND 2925 1451 199 COMPARISONS WITH EXPERIMENT," ORNL/TM-9083,ENDF-337 (1984). 2925 1451 200 (6) S. F. MUGHABGHAB, M. DIVADEENAM, AND N.E. HOLDEN, "NEUTRON 2925 1451 201 CROSS SECTIONS, VOL. 1, NEUTRON RESONANCE PARAMETERS AND 2925 1451 202 THERMAL CROSS SECTIONS, PART A, Z=1-60," ACADEMIC 2925 1451 203 PRESS (1981). 2925 1451 204 (7) M.S. PANDEY, J.B. GARG AND J.A. HARVEY, "NEUTRON TOTAL CROSS 2925 1451 205 SECTIONS AND RESONANCE PARAMETERS OF 63,65CU, I AND II", PHYS2925 1451 206 REV. C15 (1977) 600, AND PRIVATE COMMUNICATION. 2925 1451 207 (8) F.G. PEREY, PRIVATE COMMUNICATION, 1977. 2925 1451 208 (9) D.C. LARSON, "ORELA MEASUREMENTS TO MEET FUSION ENERGY 2925 1451 209 NEUTRON CROSS SECTION NEEDS," PROC. SYMP. ON CROSS-SECTIONS 2925 1451 210 FROM 10-50 MEV, BNL-NCS-51245, BROOKHAVEN NATIONAL 2925 1451 211 LAB. (JULY,1980). 2925 1451 212 (10) P. GUENTHER ET.AL, ARGONNE NATIONAL LAB DATA IN CSISRS WITH 2925 1451 213 AN/SAN 12869/002, AND W.P. POENITZ AND J.F. WHALEN, ANL/NDM802925 1451 214 IN CSISRS WITH AN/SAN 12853/ , BOTH DATED 1983 2925 1451 215 (11) D.M. HETRICK AND C.Y. FU, "GLUCS: A GENERALIZED LEAST SQUARES2925 1451 216 PROGRAM FOR UPDATING CROSS SECTION EVALUATIONS WITH 2925 1451 217 CORRELATED DATA SETS," ORNL/TM-7341, ENDF-303 (OCT,1980). 2925 1451 218 (12) C.Y. FU AND D.M. HETRICK, "EXPERIENCE IN USING THE 2925 1451 219 COVARIANCES OF SOME ENDF/B-V DOSIMETRY CROSS SECTIONS: 2925 1451 220 PROPOSED IMPROVEMENTS AND ADDITIONS OF CROSS-REACTION 2925 1451 221 COVARIANCES," PROC. FOURTH ASTM-EURATOM SYMP. ON REACTOR 2925 1451 222 DOSIMETRY, GAITHERSBURG, MARYLAND, MARCH 22-26,1982, P877, 2925 1451 223 US NATIONAL BUREAU OF STANDARDS. 2925 1451 224 (13) CSISRS LIBRARY, NATIONAL NUCLEAR DATA CENTER, BROOKHAVEN 2925 1451 225 NATIONAL LABORATORY, UPTON, N.Y. 11973. 2925 1451 226 (14) V. MCLANE, C.L. DUNFORD AND P.F. ROSE, "NEUTRON CROSS 2925 1451 227 SECTIONS, VOL. 2, NEUTRON CROSS SECTION CURVES", ACADEMIC 2925 1451 228 PRESS, 1988. 2925 1451 229 (15) S.M. QAIM, RADIOCHIMICA ACTA, 25, 13-16 (1978). 2925 1451 230 (16) M. G. DELFINI ET AL., NUCL. PHYS. A404, 250 (1983). 2925 1451 231 2925 1451 232 1 451 241 12925 1451 233 2 151 260 12925 1451 234 3 16 10 12925 1451 235 3 102 11 12925 1451 236 3 103 12 12925 1451 237 3 107 20 12925 1451 238 33 16 58 12925 1451 239 33 103 12 12925 1451 240 33 107 81 12925 1451 241 2925 1 0 242 2925 0 0 243 2.906300+4 6.238900+1 0 0 1 02925 2151 244 2.906300+4 1.000000+0 0 0 1 02925 2151 245 1.000000-5 9.950000+4 1 3 0 12925 2151 246 1.500000+0 6.700000-1 1 0 2 32925 2151 247 6.238900+1 6.700000-1 0 0 1296 2162925 2151 248 -1.870000+3 2.000000+0 9.280000+1 5.000000-1 0.000000+0 0.000000+02925 2151 249 -2.710000+2 1.000000+0 4.920000+0 5.000000-1 0.000000+0 0.000000+02925 2151 250 5.790000+2 2.000000+0 5.900000-1 4.850000-1 0.000000+0 0.000000+02925 2151 251 6.500000+2 1.000000+0 1.693000-2 3.500000-1 0.000000+0 0.000000+02925 2151 252 8.070000+2 2.000000+0 4.000000-3 5.000700-1 0.000000+0 0.000000+02925 2151 253 9.940000+2 2.000000+0 1.328000-2 5.000700-1 0.000000+0 0.000000+02925 2151 254 2.038000+3 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6.263600-4 5.622300-4 5.958200-3 2.212000-3 1.985600-3292533107 666 3.508400-3 2.432400-3 3.581700-3 0.000000+0 0.000000+0 0.000000+0292533107 667 0.000000+0 0.000000+0 18 4 72 36292533107 668 1.000000-5-1.000000+0 2.500000+6-1.000000+0 3.000000+6-1.000000+0292533107 669 3.500000+6-1.000000+0 4.000000+6-1.000000+0 4.500000+6-1.000000+0292533107 670 5.000000+6-1.000000+0 5.500000+6-1.000000+0 6.000000+6-6.300000-1292533107 671 7.500000+6-1.000000+0 7.750000+6-1.000000+0 8.000000+6-1.000000+0292533107 672 9.000000+6-1.000000+0 1.000000+7-1.000000+0 1.100000+7-1.000000+0292533107 673 1.200000+7-1.000000+0 1.300000+7-2.000000-1 2.000000+7 0.000000+0292533107 674 1.000000-5 0.000000+0 2.500000+6 1.798100-1 3.000000+6 1.241800-1292533107 675 3.500000+6 1.210500-1 4.000000+6 5.468900-2 4.500000+6 5.798400-2292533107 676 5.000000+6 4.704100-2 5.500000+6 4.866100-2 6.000000+6 4.414500-2292533107 677 7.500000+6 4.614400-2 7.750000+6 4.861700-2 8.000000+6 3.794500-2292533107 678 9.000000+6 3.809600-2 1.000000+7 4.892400-2 1.100000+7 7.718900-2292533107 679 1.200000+7 5.923200-2 1.300000+7 5.984700-2 2.000000+7 0.000000+0292533107 680 0.000000+0 0.000000+0 0 1 100 50292533107 681 1.000000-5 0.000000+0 2.530000-2 0.000000+0 1.742200+6 0.000000+0292533107 682 2.000000+6 0.000000+0 2.500000+6 2.909800-2 3.000000+6 1.387800-2292533107 683 3.500000+6 1.318700-2 4.000000+6 2.691800-3 4.500000+6 3.025900-3292533107 684 5.000000+6 1.991600-3 5.500000+6 2.131100-3 6.000000+6 1.105000-3292533107 685 6.500000+6 1.105000-3 7.000000+6 1.105000-3 7.500000+6 1.916300-3292533107 686 7.750000+6 2.127300-3 8.000000+6 1.295800-3 9.000000+6 1.306200-3292533107 687 1.000000+7 2.154200-3 1.100000+7 5.362400-3 1.200000+7 3.157600-3292533107 688 1.300000+7 6.447100-4 1.325000+7 6.447100-4 1.350000+7 6.447100-4292533107 689 1.375000+7 6.447100-4 1.400000+7 6.447100-4 1.425000+7 6.447100-4292533107 690 1.450000+7 6.447100-4 1.475000+7 6.447100-4 1.500000+7 6.447100-4292533107 691 1.525000+7 6.447100-4 1.550000+7 6.447100-4 1.575000+7 6.447100-4292533107 692 1.600000+7 6.447100-4 1.625000+7 6.447100-4 1.650000+7 6.447100-4292533107 693 1.675000+7 6.447100-4 1.700000+7 6.447100-4 1.725000+7 6.447100-4292533107 694 1.750000+7 6.447100-4 1.775000+7 6.447100-4 1.800000+7 6.447100-4292533107 695 1.825000+7 6.447100-4 1.850000+7 6.447100-4 1.875000+7 6.447100-4292533107 696 1.900000+7 6.447100-4 1.925000+7 6.447100-4 1.950000+7 6.447100-4292533107 697 1.975000+7 6.447100-4 2.000000+7 0.000000+0 0.000000+0 0.000000+0292533107 698 0.000000+0 0.000000+0 0 8 100 50292533107 699 1.000000-5 0.000000+0 2.530000-2 0.000000+0 1.742200+6 0.000000+0292533107 700 2.000000+6 0.000000+0 2.500000+6 4.06650-15 3.000000+6 1.78590-13292533107 701 3.500000+6 4.77250-12 4.000000+6 1.75710-11 4.500000+6 1.46500-10292533107 702 5.000000+6 4.82550-10 5.500000+6 2.339400-9 6.000000+6 3.761800-9292533107 703 6.500000+6 1.061500-8 7.000000+6 1.838800-8 7.500000+6 4.660700-8292533107 704 7.750000+6 6.646500-8 8.000000+6 4.891100-8 9.000000+6 9.647100-8292533107 705 1.000000+7 2.324600-7 1.100000+7 8.609500-7 1.200000+7 6.189100-7292533107 706 1.300000+7 1.372500-7 1.325000+7 1.406600-7 1.350000+7 1.380000-7292533107 707 1.375000+7 1.339200-7 1.400000+7 1.329900-7 1.425000+7 1.228400-7292533107 708 1.450000+7 1.156500-7 1.475000+7 1.078700-7 1.500000+7 1.001200-7292533107 709 1.525000+7 9.172200-8 1.550000+7 8.332100-8 1.575000+7 7.511000-8292533107 710 1.600000+7 6.749700-8 1.625000+7 6.006600-8 1.650000+7 5.321600-8292533107 711 1.675000+7 4.701600-8 1.700000+7 4.144400-8 1.725000+7 3.666600-8292533107 712 1.750000+7 3.250000-8 1.775000+7 2.886300-8 1.800000+7 2.563200-8292533107 713 1.825000+7 2.279900-8 1.850000+7 2.026600-8 1.875000+7 1.797600-8292533107 714 1.900000+7 1.582200-8 1.925000+7 1.391200-8 1.950000+7 1.213800-8292533107 715 1.975000+7 1.046900-8 2.000000+7 0.000000+0 0.000000+0 0.000000+0292533107 716 292533 0 717 2925 0 0 718 0 0 0 719 2.906500+4 6.437000+1 1 0 0 12931 1451 1 0.000000+0 0.000000+0 0 0 0 62931 1451 2 1.000000+0 0.000000+0 0 0 10 62931 1451 3 0.000000+0 0.000000+0 0 0 231 62931 1451 4 29-CU- 65 ORNL EVAL-NOV89 HETRICK,FU,LARSON 2931 1451 5 ORNL/TM-9083,ENDF-337 DIST-APR90 900409 2931 1451 6 ----ENDF/B-VI MATERIAL 2931 2931 1451 7 -----INCIDENT NEUTRON DATA 2931 1451 8 ------ENDF-6 FORMAT 2931 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2931 1451 10 ACTIVATION I 2931 1451 11 ******************************************************************2931 1451 12 THIS WORK EMPLOYED SEVERAL NUCLEAR MODEL CODES INCLUDING THE 2931 1451 13 OPTICAL-MODEL CODE GENOA (1), THE DISTORTED WAVE BORN 2931 1451 14 APPROXIMATION (DWBA) PROGRAM DWUCK (2), AND THE HAUSER-FESHBACH 2931 1451 15 CODE TNG (3,4). THE TNG CODE PROVIDES ENERGY AND ANGULAR 2931 1451 16 DISTRIBUTIONS OF PARTICLES EMITTED IN THE COMPOUND AND PRE- 2931 1451 17 COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL REACTIONS, AND 2931 1451 18 MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE CONTENTS OF 2931 1451 19 THIS EVALUATION AND EXTENSIVE COMPARISONS OF CALCULATIONS WITH 2931 1451 20 EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5). 2931 1451 21 2931 1451 22 ----- DESCRIPTION OF FILES 2931 1451 23 (MF-MT) 2931 1451 24 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2931 1451 25 2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB (6). POINT2931 1451 26 WISE RECONSTRUCTION COMPARED WITH DATA (7) SHOWED POORER 2931 1451 27 FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2931 1451 28 99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT 2931 1451 29 WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2931 1451 30 FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN 2931 1451 31 AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND 2931 1451 32 COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO 2931 1451 33 TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES 2931 1451 34 SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION. 2931 1451 35 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2931 1451 36 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2931 1451 37 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2931 1451 38 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2931 1451 39 3-1 THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS 2931 1451 40 FROM 1.E-5 EV TO 99.5 KEV. THE THERMAL CROSS SECTION 2931 1451 41 (16.3B) IS REPRODUCED. A SMALL CONTRIBUTION FROM 3/102 IS2931 1451 42 REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151 2931 1451 43 REPRODUCES THE CAPTURE DATA. FROM 99.5 KEV TO 1.12 MEV 2931 1451 44 CU65 DATA FROM (7) IS USED, AFTER APPROPRIATE AVERAGING. 2931 1451 45 ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE. FROM 1.12 TO 2931 1451 46 4.0 MEV, NAT CU DATA OF PEREY (8) USED IN V5 IS RETAINED. 2931 1451 47 FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL (9) IS 2931 1451 48 AVERAGED AND USED. COMPARISONS FROM 1.2 TO 4.5 MEV 2931 1451 49 WITH AVERAGED ARGONNE DATA FOR NAT CU (10) SHOW 1% 2931 1451 50 AGREEMENT. LARSON'S DATA ABOVE 10 MEV WERE ADJUSTED 2931 1451 51 SLIGHTLY (<2 %) TO FIT 65CU DATA OF DYUMIN ET AL. (11). 2931 1451 52 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2931 1451 53 SUBTRACTING THE NONELASTIC FROM THE TOTAL. THE THERMAL 2931 1451 54 VALUE OF 14.1B IS REPRODUCED. 2931 1451 55 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2931 1451 56 3-28, 3-102, 3-103, 3-104, 3-105, 3-106, AND 3-107. 2931 1451 57 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2931 1451 58 .., 3-63, AND 3-91 2931 1451 59 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS (12) 2931 1451 60 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2931 1451 61 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2931 1451 62 SECTIONS (13). 2931 1451 63 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2931 1451 64 CODE (3,4,5) WHICH AGREES WELL WITH AVAILABLE DATA (5). 2931 1451 65 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2931 1451 66 CODE (3,4,5). DATA ARE SCARCE FOR THIS REACTION (5). 2931 1451 67 3-51 TO 3-63 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2931 1451 68 FROM TNG (3,4,5) WHICH INCLUDES DIRECT INTERACTION 2931 1451 69 CROSS SECTIONS FROM DWUCK (2) CALCULATIONS. EXTENSIVE 2931 1451 70 COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION 2931 1451 71 PROCESS ARE SHOWN IN (5). 2931 1451 72 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2931 1451 73 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA (5). 2931 1451 74 3-102 (N,G) CAPTURE CROSS SECTION IS OBTAINED FROM RESONANCE 2931 1451 75 PARAMETERS FROM 1.E-5 EV TO 99.5 KEV. A SMALL BACKGROUND 2931 1451 76 IS GIVEN HERE, WHICH WHEN ADDED TO THE RESONANCE 2931 1451 77 CONTRIBUTION REPRODUCES EXPERIMENTAL DATA, INCLUDING THE 2931 1451 78 THERMAL VALUE OF 2.17B. FROM 99.5 KEV TO 20 MEV, DATA 2931 1451 79 FROM THE CSISRS LIBRARY (14) WERE USED TO CONSTRUCT AN 2931 1451 80 AVERAGE CURVE THROUGH THE DATA; RESULTS ARE SIMILAR TO EYE2931 1451 81 GUIDE IN REF (15). 2931 1451 82 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2931 1451 83 CODE (3,4,5) WHICH AGREES WELL WITH MEASURED DATA (5). 2931 1451 84 3-104 (N,D) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED 2931 1451 85 NORMALIZED TO AVAILABLE DATA (5). 2931 1451 86 3-105 (N,T) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION 2931 1451 87 USED NORMALIZED TO SYSTEMATICS OF QAIM AND STOCKLIN (16) 2931 1451 88 AT 14.6 MEV. 2931 1451 89 3-106 (N,3HE) CROSS SECTION - SHAPE OF (N,A) CROSS SECTION 2931 1451 90 USED NORMALIZED TO AVAILABLE DATA (17). 2931 1451 91 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2931 1451 92 TNG CODE (3,4,5). DATA ARE SCARCE AND DISCREPANT FOR 2931 1451 93 THIS REACTION (5). 2931 1451 94 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2931 1451 95 ELASTIC SCATTERING ARE RESULTS OF FITTING DATA WITH GENOA.2931 1451 96 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2931 1451 97 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2931 1451 98 PARAMETERS IN 2/151. 2931 1451 99 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2931 1451 100 NEUTRON AND 64CU RESIDUAL, AND ENERGY DEPENDENT YIELD 2931 1451 101 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2931 1451 102 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2931 1451 103 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2931 1451 104 THE OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION DATA2931 1451 105 HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS (5). 2931 1451 106 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2931 1451 107 NEUTRON, ALPHA, AND 61CO RESIDUAL, AND ENERGY DEPENDENT 2931 1451 108 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2931 1451 109 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2931 1451 110 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2931 1451 111 FOR THE OUTGOING NEUTRON). (N,XA) AND (N,XG) D-D EMISSION2931 1451 112 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS (5). 2931 1451 113 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2931 1451 114 NEUTRON AND 64NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2931 1451 115 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2931 1451 116 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2931 1451 117 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2931 1451 118 THE OUTGOING NEUTRON). (N,XP) AND (N,XG) D-D EMISSION 2931 1451 119 DATA USED TO BENCHMARK THE TNG CALCULATIONS (5). 2931 1451 120 6-51 THROUGH 6-63 INELASTIC SCATTERING EXCITING LEVELS; EACH 2931 1451 121 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2931 1451 122 AND 65CU RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2931 1451 123 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2931 1451 124 BY DWUCK (2) AND TNG (3,4,5)). COMPARISONS WITH ANGULAR 2931 1451 125 DISTRIBUTION DATA ARE GIVEN IN (5). 2931 1451 126 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2931 1451 127 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 65CU 2931 1451 128 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2931 1451 129 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; 2931 1451 130 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2931 1451 131 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2931 1451 132 OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION DATA 2931 1451 133 RELIED UPON TO BENCHMARK THE TNG CALCULATIONS (5). 2931 1451 134 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2931 1451 135 AND 65NI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2931 1451 136 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2931 1451 137 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2931 1451 138 PRODUCT. (N,XP) AND (N,XG) D-D EMISSION DATA USED TO 2931 1451 139 BENCHMARK THE TNG CALCULATIONS (5). 2931 1451 140 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2931 1451 141 AND 62CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2931 1451 142 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2931 1451 143 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2931 1451 144 PRODUCT. (N,XA) AND (N,XG) D-D EMISSION DATA USED TO 2931 1451 145 BENCHMARK THE TNG CALCULATIONS (5). 2931 1451 146 12-51 THROUGH 12-63 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2931 1451 147 BY HETRICK ET AL. (5) ARE GIVEN. 2931 1451 148 12-102 (N,G) CAPTURE; THERMAL VALUES TAKEN FROM DELFINI ET AL. 2931 1451 149 (18). HIGHER-ENERGY VALUES BASED ON TNG CALCULATIONS 2931 1451 150 USING PRIMARY BRANCHING RATIOS OF DELFINI ET AL. FOR 2931 1451 151 S-WAVES 2931 1451 152 14-51 THROUGH 14-63 GAMMA RAY ANGULAR DISTRIBUTIONS ASSUMED TO 2931 1451 153 BE ISOTROPIC. 2931 1451 154 14-102 (N,G) CAPTURE; ISOTROPIC DISTRIBUTIONS ASSUMED 2931 1451 155 15-102 (N,G) CAPTURE; AS IN 12-102 2931 1451 156 -------------------------------------------------------------- 2931 1451 157 UNCERTAINTY FILES 2931 1451 158 ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS 2931 1451 159 REQUIRED BY ENDF/B-VI FORMATS 2931 1451 160 2931 1451 161 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV 2931 1451 162 EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8. 2931 1451 163 33-2 EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV2931 1451 164 33-3 DERIVED FROM 1.E-5 TO 99.5 KEV, EXPLICIT USING LB=1,8 FROM2931 1451 165 99.5 KEV TO 20 MEV. 2931 1451 166 33-4 DERIVED FROM THRESHOLD TO 20 MEV. 2931 1451 167 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS (12) 2931 1451 168 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2931 1451 169 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2931 1451 170 SECTIONS (13). 2931 1451 171 33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM TNG AND DATA. 2931 1451 172 33-28 (N,NP) COVARIANCES ESTIMATED FROM TNG AND DATA. 2931 1451 173 33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA 2931 1451 174 AND CALCULATIONS. 2931 1451 175 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2931 1451 176 ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS 2931 1451 177 DATA (5,14,15) FROM 99.5 KEV TO 20 MEV. 2931 1451 178 33-103 (N,P) COVARIANCES - ESTIMATED USING CSISRS DATA AS GUIDE. 2931 1451 179 33-104 (N,D) COVARIANCES - ESTIMATED, BASED ON DATA. 2931 1451 180 33-105 (N,T) COVARIANCES - ESTIMATED. 2931 1451 181 33-106 (N,3HE) COVARIANCES - ESTIMATED, BASED ON DATA. 2931 1451 182 33-107 (N,A) COVARIANCES WERE ESTIMATED BASED ON TNG AND DATA. 2931 1451 183 REFERENCES: 2931 1451 184 (1) F.G. PEREY, COMPUTER CODE GENOA, ORNL, UNPUBLISHED (1967). 2931 1451 185 (2) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2931 1451 186 COLORADO, UNPUBLISHED (1972). 2931 1451 187 (3) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2931 1451 188 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2931 1451 189 MOMENTUM," ORNL/TM-7042 (1980). ALSO, 2931 1451 190 C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2931 1451 191 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2931 1451 192 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2931 1451 193 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2931 1451 194 NATIONAL LAB. 2931 1451 195 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2931 1451 196 STATISTICAL MODEL CODE," ORNL/TM-10093 (AUGUST, 1986). 2931 1451 197 (5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2931 1451 198 -INDUCED CROSS SECTIONS FOR 63,65CU FROM 1 TO 20 MEV AND 2931 1451 199 COMPARISONS WITH EXPERIMENT," ORNL/TM-9083,ENDF-337 (1984). 2931 1451 200 (6) S. F. MUGHABGHAB, M. DIVADEENAM, AND N.E. HOLDEN, "NEUTRON 2931 1451 201 CROSS SECTIONS, VOL. 1, NEUTRON RESONANCE PARAMETERS AND 2931 1451 202 THERMAL CROSS SECTIONS, PART A, Z=1-60," ACADEMIC 2931 1451 203 PRESS (1981). 2931 1451 204 (7) M.S. PANDEY, J.B. GARG AND J.A. HARVEY, "NEUTRON TOTAL CROSS 2931 1451 205 SECTIONS AND RESONANCE PARAMETERS OF 63,65CU, I AND II", PHYS2931 1451 206 REV. C15 (1977) 600, AND PRIVATE COMMUNICATION. 2931 1451 207 (8) F.G. PEREY, PRIVATE COMMUNICATION, 1977. 2931 1451 208 (9) D.C. LARSON, "ORELA MEASUREMENTS TO MEET FUSION ENERGY 2931 1451 209 NEUTRON CROSS SECTION NEEDS," PROC. SYMP. ON CROSS-SECTIONS 2931 1451 210 FROM 10-50 MEV, BNL-NCS-51245, BROOKHAVEN NATIONAL 2931 1451 211 LAB. (JULY,1980). 2931 1451 212 (10) P. GUENTHER ET.AL, ARGONNE NATIONAL LAB DATA IN CSISRS WITH 2931 1451 213 AN/SAN 12869/002, AND W.P. POENITZ AND J.F. WHALEN, ANL/NDM802931 1451 214 IN CSISRS WITH AN/SAN 12853/ , BOTH DATED 1983. 2931 1451 215 (11) A.I. DYUMIN, D.M. KAMINKER, G.N. POPOVA, & V.A. SMOLIN, 2931 1451 216 IZV.AKAD.NAUK SSSR, SER.FIZ. 36 (4), 852 (1972) 2931 1451 217 (12) D.M. HETRICK AND C.Y. FU, "GLUCS: A GENERALIZED LEAST SQUARES2931 1451 218 PROGRAM FOR UPDATING CROSS SECTION EVALUATIONS WITH 2931 1451 219 CORRELATED DATA SETS," ORNL/TM-7341, ENDF-303 (OCT,1980). 2931 1451 220 (13) C.Y. FU AND D.M. HETRICK, "EXPERIENCE IN USING THE 2931 1451 221 COVARIANCES OF SOME ENDF/B-V DOSIMETRY CROSS SECTIONS: 2931 1451 222 PROPOSED IMPROVEMENTS AND ADDITIONS OF CROSS-REACTION 2931 1451 223 COVARIANCES," PROC. FOURTH ASTM-EURATOM SYMP. ON REACTOR 2931 1451 224 DOSIMETRY, GAITHERSBURG, MARYLAND, MARCH 22-26,1982, P877, 2931 1451 225 US NATIONAL BUREAU OF STANDARDS. 2931 1451 226 (14) CSISRS LIBRARY, NATIONAL NUCLEAR DATA CENTER, BROOKHAVEN 2931 1451 227 NATIONAL LABORATORY, UPTON, N.Y. 11973. 2931 1451 228 (15) V. MCLANE, C.L. DUNFORD AND P.F. ROSE, "NEUTRON CROSS 2931 1451 229 SECTIONS, VOL. 2, NEUTRON CROSS SECTION CURVES", ACADEMIC 2931 1451 230 PRESS, 1988. 2931 1451 231 (16) S.M. QAIM AND G. STOCKLIN, NUCL. PHYS. A257 (1976). 2931 1451 232 (17) S.M. QAIM, RADIOCHIMICA ACTA, 25, 13-16 (1978). 2931 1451 233 (18) M. G. DELFINI ET AL., NUCL. PHYS. A404, 250 (1983). 2931 1451 234 2931 1451 235 1 451 241 12931 1451 236 2 151 184 12931 1451 237 3 16 10 12931 1451 238 3 102 11 12931 1451 239 3 105 6 12931 1451 240 33 16 63 12931 1451 241 2931 1 0 242 2931 0 0 243 2.906500+4 6.437000+1 0 0 1 02931 2151 244 2.906500+4 1.000000+0 0 0 1 02931 2151 245 1.000000-5 9.950000+4 1 3 0 12931 2151 246 1.500000+0 6.700000-1 1 0 2 32931 2151 247 6.437000+1 6.700000-1 0 0 912 1522931 2151 248 -3.030000+3 2.000000+0 4.800000+2 3.950000-1 0.000000+0 0.000000+02931 2151 249 -8.330000+2 1.000000+0 3.226700+1 3.950000-1 0.000000+0 0.000000+02931 2151 250 2.300000+2 2.000000+0 1.776000-2 2.450000-1 0.000000+0 0.000000+02931 2151 251 1.362000+3 1.000000+0 2.933000-2 3.951400-1 0.000000+0 0.000000+02931 2151 252 2.529000+3 2.000000+0 1.760000+1 3.600000-1 0.000000+0 0.000000+02931 2151 253 3.142000+3 2.000000+0 6.080000-3 3.951400-1 0.000000+0 0.000000+02931 2151 254 3.594000+3 1.000000+0 6.267000-2 3.951400-1 0.000000+0 0.000000+02931 2151 255 3.920000+3 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0.000000+02931 2151 394 1.356800+5 2.000000+0 7.500000+2 3.951400-1 0.000000+0 0.000000+02931 2151 395 1.363500+5 1.000000+0 2.400000+1 3.951400-1 0.000000+0 0.000000+02931 2151 396 1.399400+5 1.000000+0 6.400000+2 3.951400-1 0.000000+0 0.000000+02931 2151 397 1.408700+5 1.000000+0 8.000000+1 3.951400-1 0.000000+0 0.000000+02931 2151 398 1.439500+5 1.000000+0 2.500000+2 3.951400-1 0.000000+0 0.000000+02931 2151 399 1.491000+5 2.000000+0 4.500000+2 3.951400-1 0.000000+0 0.000000+02931 2151 400 6.437000+1 6.700000-1 1 0 156 262931 2151 401 2.202800+4 3.000000+0 4.685700+0 3.695000-1 0.000000+0 0.000000+02931 2151 402 2.879700+4 2.000000+0 2.160000+0 3.000000-1 0.000000+0 0.000000+02931 2151 403 3.082700+4 1.000000+0 3.466700+0 3.000000-1 0.000000+0 0.000000+02931 2151 404 3.228900+4 0.000000+0 1.520000+0 3.695000-1 0.000000+0 0.000000+02931 2151 405 3.351600+4 3.000000+0 3.142900+0 3.000000-1 0.000000+0 0.000000+02931 2151 406 4.687300+4 2.000000+0 8.960000+0 3.695000-1 0.000000+0 0.000000+02931 2151 407 4.975200+4 1.000000+0 5.333300+0 5.780000-1 0.000000+0 0.000000+02931 2151 408 5.076700+4 3.000000+0 3.771400+0 3.695000-1 0.000000+0 0.000000+02931 2151 409 5.288700+4 2.000000+0 4.320000+0 3.695000-1 0.000000+0 0.000000+02931 2151 410 5.835400+4 3.000000+0 6.285700+0 3.695000-1 0.000000+0 0.000000+02931 2151 411 6.110500+4 3.000000+0 5.371400+0 3.695000-1 0.000000+0 0.000000+02931 2151 412 6.866000+4 2.000000+0 9.120000+0 3.695000-1 0.000000+0 0.000000+02931 2151 413 7.018700+4 1.000000+0 9.600000+0 3.695000-1 0.000000+0 0.000000+02931 2151 414 7.197000+4 3.000000+0 1.451400+1 3.695000-1 0.000000+0 0.000000+02931 2151 415 7.390700+4 2.000000+0 5.920000+0 3.695000-1 0.000000+0 0.000000+02931 2151 416 7.693200+4 3.000000+0 6.628600+0 3.695000-1 0.000000+0 0.000000+02931 2151 417 7.723500+4 3.000000+0 6.628600+0 3.695000-1 0.000000+0 0.000000+02931 2151 418 7.943000+4 2.000000+0 5.760000+0 3.695000-1 0.000000+0 0.000000+02931 2151 419 8.303200+4 1.000000+0 3.920000+1 3.695000-1 0.000000+0 0.000000+02931 2151 420 8.334000+4 0.000000+0 1.040000+2 3.695000-1 0.000000+0 0.000000+02931 2151 421 8.810300+4 3.000000+0 5.257100+0 3.695000-1 0.000000+0 0.000000+02931 2151 422 8.993500+4 2.000000+0 8.640000+0 3.695000-1 0.000000+0 0.000000+02931 2151 423 9.280600+4 3.000000+0 3.542900+0 3.695000-1 0.000000+0 0.000000+02931 2151 424 9.432500+4 1.000000+0 2.240000+1 3.695000-1 0.000000+0 0.000000+02931 2151 425 9.649300+4 2.000000+0 1.936000+1 3.695000-1 0.000000+0 0.000000+02931 2151 426 9.706800+4 3.000000+0 1.177100+1 3.695000-1 0.000000+0 0.000000+02931 2151 427 2931 2 0 428 2931 0 0 429 2.906500+4 6.437000+1 0 0 0 02931 3 16 430 -9.910000+6-9.910000+6 0 0 1 202931 3 16 431 20 2 0 0 0 02931 3 16 432 1.006300+7 0.000000+0 1.050000+7 2.485100-2 1.100000+7 1.436700-12931 3 16 433 1.150000+7 2.978200-1 1.200000+7 4.646600-1 1.250000+7 6.190700-12931 3 16 434 1.300000+7 7.329500-1 1.350000+7 8.233200-1 1.400000+7 8.953100-12931 3 16 435 1.450000+7 9.488400-1 1.500000+7 9.825500-1 1.550000+7 1.013100+02931 3 16 436 1.600000+7 1.030500+0 1.650000+7 1.062800+0 1.700000+7 1.071100+02931 3 16 437 1.750000+7 1.075800+0 1.800000+7 1.091200+0 1.850000+7 1.076700+02931 3 16 438 1.900000+7 1.036800+0 2.000000+7 9.588500-1 0.000000+0 0.000000+02931 3 16 439 2931 3 0 440 2.906500+4 6.437000+1 0 0 0 02931 3102 441 7.067000+6 7.067000+6 0 0 1 232931 3102 442 23 2 0 0 0 02931 3102 443 1.000000-5 0.000000+0 6.000000+4 0.000000+0 6.000000+4 1.100000-22931 3102 444 7.000000+4 1.800000-2 8.000000+4 1.200000-2 9.000000+4 1.700000-22931 3102 445 9.950000+4 1.500000-2 9.950000+4 2.200000-2 2.000000+5 1.400000-22931 3102 446 3.000000+5 1.000000-2 4.000000+5 8.500000-3 5.000000+5 7.750000-32931 3102 447 6.000000+5 7.950000-3 7.000000+5 8.250000-3 8.000000+5 8.600000-32931 3102 448 9.000000+5 8.550000-3 1.000000+6 8.500000-3 2.000000+6 6.000000-32931 3102 449 5.000000+6 2.200000-3 8.000000+6 1.100000-3 1.000000+7 8.000000-42931 3102 450 1.500000+7 4.500000-4 2.000000+7 3.000000-4 0.000000+0 0.000000+02931 3102 451 2931 3 0 452 2.906500+4 6.437000+1 0 0 0 02931 3105 453 -8.622000+6-8.622000+6 0 0 1 92931 3105 454 9 2 0 0 0 02931 3105 455 8.755900+6 0.000000+0 1.025000+7 6.700000-8 1.050000+7 3.200000-72931 3105 456 1.100000+7 2.800000-6 1.150000+7 1.000000-5 1.300000+7 2.200000-52931 3105 457 1.460000+7 3.900000-5 1.700000+7 6.500000-5 2.000000+7 1.500000-42931 3105 458 2931 3 0 459 2931 0 0 460 2.906500+4 6.437000+1 0 0 0 1293133 16 461 0.000000+0 0.000000+0 0 16 0 4293133 16 462 0.000000+0 0.000000+0 1 5 171 18293133 16 463 1.000000-5 1.006300+7 1.050000+7 1.100000+7 1.250000+7 1.400000+7293133 16 464 1.450000+7 1.600000+7 1.650000+7 1.700000+7 1.750000+7 1.800000+7293133 16 465 1.850000+7 1.900000+7 1.920000+7 1.940000+7 1.960000+7 2.000000+7293133 16 466 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0293133 16 467 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0293133 16 468 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0293133 16 469 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0293133 16 470 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0293133 16 471 0.000000+0 0.000000+0 0.000000+0 1.170600-2 4.741300-4 4.284700-4293133 16 472 1.313100-4 1.106300-4 6.477000-5 6.417200-5 6.216900-5 6.343100-5293133 16 473 6.407700-5 8.524100-5 6.438800-5 7.086900-5 7.087400-5 8.306100-5293133 16 474 2.488000-3 4.064100-4 1.163400-4 9.510000-5 5.626300-5 5.558000-5293133 16 475 5.394900-5 5.491100-5 5.558000-5 7.326900-5 5.489000-5 6.083400-5293133 16 476 6.083000-5 7.134100-5 1.991200-3 1.930700-4 1.177700-4 7.578500-5293133 16 477 7.436800-5 7.324800-5 7.381700-5 7.499200-5 9.343300-5 7.354200-5293133 16 478 7.865700-5 7.865600-5 9.062800-5 8.238100-4 2.212500-4 1.427800-4293133 16 479 1.364600-4 1.342400-4 1.349100-4 1.367800-4 1.729100-4 1.303500-4293133 16 480 1.439400-4 1.439400-4 1.676400-4 2.733300-4 1.472200-4 1.462200-4293133 16 481 1.390100-4 1.414800-4 1.438200-4 2.011500-4 1.343200-4 1.624900-4293133 16 482 1.624900-4 1.965900-4 5.706800-4 1.858900-4 2.043800-4 1.847400-4293133 16 483 1.859800-4 1.535200-4 1.536800-4 1.405300-4 1.405500-4 1.422600-4293133 16 484 3.160300-4 1.768100-4 1.986800-4 1.742500-4 1.582500-4 1.711300-4293133 16 485 1.475800-4 1.475800-4 1.467700-4 3.522000-4 2.135300-4 1.888900-4293133 16 486 1.603100-4 1.798700-4 1.516900-4 1.516800-4 1.473200-4 1.180400-3293133 16 487 -7.011400-5 2.934400-4 2.097300-4 2.460200-4 2.460200-4 2.128100-4293133 16 488 5.144100-4 1.515000-4 1.968900-4 1.572400-4 1.572300-4 1.526400-4293133 16 489 1.451800-3 9.265200-5 5.591700-4 5.591700-4 4.462100-4 5.217100-4293133 16 490 2.367800-4 2.367800-4 2.042500-4 3.296600-3 1.219200-3 8.869900-4293133 16 491 3.296100-3 8.870500-4 2.088900-3 0.000000+0 0.000000+0 0.000000+0293133 16 492 0.000000+0 0.000000+0 18 4 72 36293133 16 493 1.000000-5 0.000000+0 1.006300+7-1.000000+0 1.050000+7-1.000000+0293133 16 494 1.100000+7-7.500000-1 1.250000+7-7.500000-1 1.400000+7-1.000000+0293133 16 495 1.450000+7-8.400000-1 1.600000+7-1.000000+0 1.650000+7-1.000000+0293133 16 496 1.700000+7-1.000000+0 1.750000+7-1.000000+0 1.800000+7-1.000000+0293133 16 497 1.850000+7-1.000000+0 1.900000+7-1.000000+0 1.920000+7-1.000000+0293133 16 498 1.940000+7-1.000000+0 1.960000+7-1.000000+0 2.000000+7 0.000000+0293133 16 499 1.000000-5 0.000000+0 1.006300+7 0.000000+0 1.050000+7 1.082000-1293133 16 500 1.100000+7 4.988000-2 1.250000+7 4.462300-2 1.400000+7 2.870200-2293133 16 501 1.450000+7 1.653300-2 1.600000+7 2.388900-2 1.650000+7 1.777700-2293133 16 502 1.700000+7 1.876700-2 1.750000+7 3.435700-2 1.800000+7 2.268100-2293133 16 503 1.850000+7 3.810300-2 1.900000+7 2.284100-2 1.920000+7 5.741600-2293133 16 504 1.940000+7 5.741200-2 1.960000+7 4.570400-2 2.000000+7 0.000000+0293133 16 505 0.000000+0 0.000000+0 0 1 48 24293133 16 506 1.000000-5 0.000000+0 1.006300+7 0.000000+0 1.050000+7 1.053600-2293133 16 507 1.100000+7 1.679400-3 1.150000+7 1.679400-3 1.200000+7 1.679400-3293133 16 508 1.250000+7 1.344100-3 1.300000+7 1.344100-3 1.350000+7 1.344100-3293133 16 509 1.400000+7 7.414300-4 1.450000+7 2.066400-4 1.500000+7 2.066400-4293133 16 510 1.550000+7 2.066400-4 1.600000+7 5.136100-4 1.650000+7 2.844300-4293133 16 511 1.700000+7 3.169800-4 1.750000+7 1.062300-3 1.800000+7 4.629700-4293133 16 512 1.850000+7 1.306700-3 1.900000+7 4.695400-4 1.920000+7 2.966900-3293133 16 513 1.940000+7 2.966500-3 1.960000+7 1.880000-3 2.000000+7 0.000000+0293133 16 514 0.000000+0 0.000000+0 0 8 48 24293133 16 515 1.000000-5 0.000000+0 1.006300+7 0.000000+0 1.050000+7 7.229600-7293133 16 516 1.100000+7 3.851700-6 1.150000+7 1.655100-5 1.200000+7 4.028900-5293133 16 517 1.250000+7 5.723600-5 1.300000+7 8.023000-5 1.350000+7 1.012300-4293133 16 518 1.400000+7 6.603500-5 1.450000+7 2.067100-5 1.500000+7 2.216600-5293133 16 519 1.550000+7 2.356500-5 1.600000+7 6.060200-5 1.650000+7 3.569700-5293133 16 520 1.700000+7 4.040600-5 1.750000+7 1.366100-4 1.800000+7 6.125200-5293133 16 521 1.850000+7 1.683100-4 1.900000+7 5.608100-5 1.920000+7 3.751700-4293133 16 522 1.940000+7 3.629800-4 1.960000+7 2.231600-4 2.000000+7 0.000000+0293133 16 523 293133 0 524 2931 0 0 525 0 0 0 526 4.009000+4 8.913200+1 -1 0 0 04025 1451 1 0.000000+0 0.000000+0 0 0 0 64025 1451 2 1.000000+0 0.000000+0 0 0 10 64025 1451 3 0.000000+0 0.000000+0 0 0 134 34025 1451 4 40-ZR- 90 SAI,BNL EVAL-APR76 M.DRAKE,D.SARGIS,T.MAUNG,P.ROSE 4025 1451 5 EPRI NP-250 DIST-JAN90 900126 4025 1451 6 ----ENDF/B-VI MATERIAL 4025 4025 1451 7 -----INCIDENT NEUTRON DATA 4025 1451 8 ------ENDF-6 FORMAT 4025 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4025 1451 10 ACTIVATION II 4025 1451 11 ******************************************************************4025 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4025 1451 13 * * * * * * *4025 1451 14 * * * * * * 4025 1451 15 ZIRCONIUM-90 4025 1451 16 EVALUATED NEUTRON CROSS SECTIONS 4025 1451 17 FOR ZIRCONIUM AND HAFNIUM 4025 1451 18 SAI-76-677-LJ 4025 1451 19 JUNE 1976 4025 1451 20 MARVIN K. DRAKE, DAVE A. SARGIS AND T.MAUNG 4025 1451 21 ISOTOPE EVALUATION CONSTRUCTED FROM SAI DOCUMENTATION BY 4025 1451 22 S. PEARLSTEIN, BNL. 4025 1451 23 * * * * * * 4025 1451 24 RESONANCE REGION REEVALUATED BY P.F. ROSE, BNL 1981 4025 1451 25 RESOLVED RESONANCE PARAMETERS PRIMARILY TAKEN FROM THE 4025 1451 26 RECOMMENDED VALUES GIVEN IN NEUTRON CROSS SECTIONS,FOURTH 4025 1451 27 EDITION, SEE REFERENCE (1) 4025 1451 28 * * * * * * 4025 1451 29 ISOTOPE MAT THERMAL X/S RI 4025 1451 30 ZR-90 1385 0.011 0.179 4025 1451 31 ZR-91 1386 1.188 4.913 4025 1451 32 ZR-92 1387 0.221 0.655 4025 1451 33 ZR-94 1388 0.049 0.311 4025 1451 34 ZR-96 1389 0.023 5.629 4025 1451 35 ZR 1340 0.186 0.965 4025 1451 36 * * * * * * 4025 1451 37 UNRESOLVED PARAMETERS GIVEN FOR ZR-91 ONLY 4025 1451 38 UPPER BOUNDARY OF RESONANCE REGION = 90 KEV 4025 1451 39 * * * * * * 4025 1451 40 TOTAL CROSS SECTION 4025 1451 41 BETWEEN 90 KEV AND 500 KEV THE DATA OF SETH (3) WERE USED 4025 1451 42 BETWEEN 500 KEV AND 2 MEV, THE EVALUATED DATA WERE BASED ON 4025 1451 43 MEASUREMENTS OF GREEN AND MITCHELL (4) AND STOOKSBERRY AND 4025 1451 44 ANDERSON (5) 4025 1451 45 ABOVE 2 MEV, THE MEASUREMENTS OF GREEN AND MITCHELL (4), 4025 1451 46 FOSTER AND GLASGOW (6), CARLSON AND BARSCHALL (7) AND 4025 1451 47 PETERSON, ET AL (8) 4025 1451 48 * * * * * * 4025 1451 49 N,2N CROSS SECTION 4025 1451 50 THE CROSS SECTION FOR THE ELEMENT WAS BASED ON ESTIMATES 4025 1451 51 FOR THE ISOTOPES. 4025 1451 52 EXCEPT FOR ZR-90, THE RESULTS FROM A STATISTICAL MODEL WERE USED.4025 1451 53 THE (N,2N) CROSS SECTION FOR ZR-90 WAS BASE ON MEASUREMENTS 4025 1451 54 BY PRESTWOOD AND BAYHURST (9), NETHAWAY (10) AND SEVERAL 4025 1451 55 MEASUREMENTS NEAR 14 MEV 4025 1451 56 BRANCHING FOR (N,2N) IS BASED ON ABBOUND ET AL (NUCL. PHYS. AI39 4025 1451 57 1969, P42) & KANDU (NUCL. PHYS. A185, 1972, P177). 4025 1451 58 * * * * * * 4025 1451 59 N,ALPHA CROSS SECTION 4025 1451 60 THE (N,ALPHA) CROSS SECTION WAS BASED ON ESTIMATES FOR THE 4025 1451 61 ISOTOPES. 4025 1451 62 THE ENERGY DEPENDENT MEASUREMENTS BY BAYHURST AND PRESTWOOD (11),4025 1451 63 STATISTICAL MODEL CALCULATIONS AND SEVERAL MEASUREMENTS AT 4025 1451 64 14 MEV WERE USED 4025 1451 65 * * * * * * 4025 1451 66 (N,P) CROSS SECTION 4025 1451 67 THE (N,P) X/S FOR ZR-90 WAS BASED ON MEASUREMENTS BY 4025 1451 68 CARROL AND STOOKSBERRY (12) AND BAYHURST AND PRESTWOOD (11) 4025 1451 69 THE (N,P) X/S FOR ZR-91 WAS BASED ON MEASUREMENTS BY 4025 1451 70 CARROL AND STOOKSBERRY (12), REED (13) AND LEVKOVSKII (14) 4025 1451 71 THE (N,P) X/S FOR ZR-92 AND ZR-94 WERE BASED ON MEASUREMENTS 4025 1451 72 BY CARROLL AND STOOKSBERRY (12), REED (13), BRAMLITT AND 4025 1451 73 FINK (15), LU, ET AL (16), LEVKOVSKII (14) AND PRASAD AND 4025 1451 74 SARKAR (16) AND PAUL AND CLARKE (17) 4025 1451 75 * * * * * * 4025 1451 76 THE (N,GAMMA) CROSS SECTION 4025 1451 77 THE DATA RECOMMENDED BY BENZI (18) WERE USED 4025 1451 78 * * * * * * 4025 1451 79 INELASTIC SCATTERING CROSS SECTION 4025 1451 80 19 LEVEL EXCITATION CROSS SECTIONS AND A CONTINUUM CROSS 4025 1451 81 SECTION HAS BEEN GIVEN. 4025 1451 82 THE CROSS SECTIONS WERE BASED ON A PREVIOUS EVALUATION BY 4025 1451 83 KAPL AND THE EXPERIMENTAL DATA OF TESSLER, ET AL (19), 4025 1451 84 DAY (20), MC DANIEL, ET AL (21), BRANDENBERGER AND GLASGOW, 4025 1451 85 SMITH AND WHALEN (22), LIND AND DAY (23), TESSLER AND 4025 1451 86 GLICKSTEIN (24), GUENTHER, ET AL (22), GLAZKOV (25) 4025 1451 87 * * * * * * 4025 1451 88 ELASTIC SCATTERING CROSS SECTION 4025 1451 89 BASICALLY, THE ELASTI SCATTERING CROSS SECTION WAS TAKEN 4025 1451 90 AS THE DIFFERENCE BETWEEN THE TOTAL CROSS SECTION AND 4025 1451 91 THE NON-ELASTIC CROSS SECTION. 4025 1451 92 THE EXPERIMENTAL DATA USED, INCLUDING ENGELBRECHT AND SMITH (26) 4025 1451 93 HANS AND SNOWDON (27), KENT, ET AL (28), WALT AND BEYSTER (29), 4025 1451 94 WALT AND BARSCHALL (30), GILBOY AND TOWLE (31) AND 4025 1451 95 CLARK AND CROSS (32) 4025 1451 96 * * * * * * 4025 1451 97 REFERENCES 4025 1451 98 * * * * * * 4025 1451 99 (1) MUGHABGHAB, S.F., DIVADEENAM, M., AND HOLDEN, N.E. NEUTRON 4025 1451 100 CROSS SECTIONS FOURTH EDITION VOLUME I NEUTRON RESONANCE 4025 1451 101 PARAMETERS AND THERMAL CROSS SECTIONS PART A Z=1-60, NEW YORK, 4025 1451 102 ACADEMIC PRESS (1981) 4025 1451 103 (2) NEWSON, H.W., ET AL, ANNALS OF PHYS. 8, 211 (1959) 4025 1451 104 (3) SETH, K.K., PHYS. LETTERS 16, 306 (1965) 4025 1451 105 (4) GREEN, L. AND MITCHELL, J.A, WAPD-TM-1073 (APRIL 1973) 4025 1451 106 (5) STOOKSBERRY, R.W. AND ANDERSON, J.H., NUC-SCI.AND E.51,235,734025 1451 107 (6) FOSTER, D.C., JR. AND GLASGOW, D.W., PHYS.REV. C3,576 (1971) 4025 1451 108 (7) CARLSON, A.D. AND BARSCHALL, H.H., PHYS.REV. 158,1142 (1967) 4025 1451 109 (8) PETERSON, J.M., ET AL, PHYS.REV. 120, 521 (1960) 4025 1451 110 (9) PRESTWOOD, R.J. AND BAYHURST, B.P., PHYS.REV.121, 1438 (1961)4025 1451 111 (10) NETHAWAY, D.R. NUCL. PHYS. A190, 635 (1972) 4025 1451 112 (11) BAYHURST, B.P. AND PRESTWOOD, R.J., J.INORG. NUCL. CHEM. 4025 1451 113 23, 173 (1961) 4025 1451 114 (12) CARROLL, E.E. AND STOOKSBERRY, R.W., NUCL.SCI. ENG. 4025 1451 115 25, 285 (1966) 4025 1451 116 (13) REED, C.H., UC-34 (1960) 4025 1451 117 (14) LEVKOVSKII, V.N., SOV. PHYS. JETP 18, 213 (1964) 4025 1451 118 (15) BRAMLITT, E.T. AND FINK, R.W., PHYS. REV. 131, 2649 (1963) 4025 1451 119 (16) PRASAD, R. AND SARKAR, D.C., NUOVO CIMENTO 3A, 467 (1971) 4025 1451 120 (17) PAUL, E.B. AND CLARKE, R.L., CAN. J. PHYS. 31, 268 (1953) 4025 1451 121 (18) BENZI, V., ET AL, CEC(71) 9 , NOV. 1971 4025 1451 122 (19) TESSLER, G., ET AL. PHYS. REV. C2, 2390 (1970) 4025 1451 123 (20) DAY, R.B. PRI. COMM. (1965) 4025 1451 124 (21) MC DANIEL, F.D, ET.AL. PHYS. REV C10, 1087 (1974) 4025 1451 125 (22) GUENTHER, P., ET AL, ANL/NDM-4 (1974) 4025 1451 126 (23) LIND, D.A. AND DAY, R.B. ANNALS PHYS. 12, 485 (1961) 4025 1451 127 (24) TESSLER, G. AND GLICKSTEIN, S., BULL. AM. PHYS. SOC. 4025 1451 128 20, 174 (1975) 4025 1451 129 (25) GLAZKOV, N.P. A.E. 15, 416 (1963) 4025 1451 130 (26) REITMAN, ET AL, NUCL. PHYS 48, 593 (1963) 4025 1451 131 (27) HANS, H.S. AND SNOWDON, S.C., PHYS. REV. 108, 1028 (1957) 4025 1451 132 (28) KENT, D.W., PHYS. REV. 125, 331 (1962) 4025 1451 133 (29) WALT, M. AND BEYSTER, J.R., PHYS. REV. 98, 677 (1955) 4025 1451 134 (30) WALT, M. AND BARSCHALL, H.H., PHYS. REV. 93, 1062 (1954) 4025 1451 135 (31) GILBOY, W.H. AND TOWLE, J.H., NUCL. PHYS.42, 86 (1963) 4025 1451 136 (32) CLARKE, R.L. AND CROSS, W.G., NUCL. PHYS. A95, 320 (1967) 4025 1451 137 4025 1451 138 1 451 141 04025 1451 139 3 16 9 04025 1451 140 3 103 14 04025 1451 141 4025 1 0 142 4025 0 0 143 4.009000+4 8.913200+1 0 0 0 04025 3 16 144 -1.199000+7-1.199000+7 0 0 1 174025 3 16 145 17 2 0 0 0 04025 3 16 146 1.212000+7 0.000000+0 1.250000+7 1.270000-1 1.300000+7 2.800000-14025 3 16 147 1.350000+7 4.470000-1 1.400000+7 6.070000-1 1.450000+7 7.540000-14025 3 16 148 1.500000+7 8.800000-1 1.550000+7 9.800000-1 1.600000+7 1.050000+04025 3 16 149 1.650000+7 1.091000+0 1.700000+7 1.118000+0 1.750000+7 1.136000+04025 3 16 150 1.800000+7 1.145000+0 1.850000+7 1.151000+0 1.900000+7 1.154000+04025 3 16 151 1.950000+7 1.155000+0 2.000000+7 1.156000+0 0.000000+0 0.000000+04025 3 16 152 4025 3 0 153 4.009000+4 8.913200+1 0 0 0 04025 3103 154 -1.513000+6-1.513000+6 0 0 1 314025 3103 155 31 2 0 0 0 04025 3103 156 1.530000+6 0.000000+0 3.000000+6 0.000000+0 3.500000+6 5.000000-54025 3103 157 4.000000+6 3.000000-4 4.500000+6 8.000000-4 5.000000+6 1.600000-34025 3103 158 5.500000+6 2.700000-3 6.000000+6 4.100000-3 6.500000+6 5.700000-34025 3103 159 7.000000+6 7.600000-3 7.500000+6 9.600000-3 8.000000+6 1.190000-24025 3103 160 8.500000+6 1.430000-2 9.000000+6 1.690000-2 9.500000+6 1.960000-24025 3103 161 1.000000+7 2.240000-2 1.050000+7 2.540000-2 1.100000+7 2.840000-24025 3103 162 1.150000+7 3.150000-2 1.200000+7 3.470000-2 1.250000+7 3.790000-24025 3103 163 1.300000+7 4.070000-2 1.350000+7 4.260000-2 1.400000+7 4.400000-24025 3103 164 1.450000+7 4.480000-2 1.500000+7 4.520000-2 1.600000+7 4.570000-24025 3103 165 1.700000+7 4.610000-2 1.800000+7 4.640000-2 1.900000+7 4.650000-24025 3103 166 2.000000+7 4.660000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+04025 3103 167 4025 3 0 168 4025 0 0 169 0 0 0 170 4.009100+4 9.012200+1 -1 0 0 04028 1451 1 0.000000+0 0.000000+0 0 0 0 64028 1451 2 1.000000+0 0.000000+0 0 0 10 64028 1451 3 0.000000+0 0.000000+0 0 0 132 24028 1451 4 40-ZR- 91 SAI,BNL EVAL-APR76 M.DRAKE,D.SARGIS,T.MAUNG,P.ROSE 4028 1451 5 EPRI NP-250 DIST-JAN90 900126 4028 1451 6 ----ENDF/B-VI MATERIAL 4028 4028 1451 7 -----INCIDENT NEUTRON DATA 4028 1451 8 ------ENDF-6 FORMAT 4028 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4028 1451 10 ACTIVATION II 4028 1451 11 ******************************************************************4028 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4028 1451 13 * * * * * * *4028 1451 14 * * * * * * 4028 1451 15 ZIRCONIUM-91 4028 1451 16 EVALUATED NEUTRON CROSS SECTIONS 4028 1451 17 FOR ZIRCONIUM AND HAFNIUM 4028 1451 18 SAI-76-677-LJ 4028 1451 19 JUNE 1976 4028 1451 20 MARVIN K. DRAKE, DAVE A. SARGIS AND T.MAUNG 4028 1451 21 ISOTOPE EVALUATION CONSTRUCTED FROM SAI DOCUMENTATION 4028 1451 22 BY S. PEARLSTEIN, BNL. 4028 1451 23 * * * * * * 4028 1451 24 RESONANCE REGION REEVALUATED BY P.F. ROSE, BNL 1981 4028 1451 25 RESOLVED RESONANCE PARAMETERS PRIMARILY TAKEN FROM THE 4028 1451 26 RECOMMENDED VALUES GIVEN IN NEUTRON CROSS SECTIONS,FOURTH 4028 1451 27 EDITION, SEE REFERENCE (1) 4028 1451 28 * * * * * * 4028 1451 29 ISOTOPE MAT THERMAL X/S RI 4028 1451 30 ZR-90 1385 0.011 0.179 4028 1451 31 ZR-91 1386 1.188 4.913 4028 1451 32 ZR-92 1387 0.221 0.655 4028 1451 33 ZR-94 1388 0.049 0.311 4028 1451 34 ZR-96 1389 0.023 5.629 4028 1451 35 ZR 1340 0.186 0.965 4028 1451 36 * * * * * * 4028 1451 37 UNRESOLVED PARAMETERS GIVEN FOR ZR-91 ONLY 4028 1451 38 UPPER BOUNDARY OF RESONANCE REGION = 90 KEV 4028 1451 39 * * * * * * 4028 1451 40 TOTAL CROSS SECTION 4028 1451 41 BETWEEN 90 KEV AND 500 KEV THE DATA OF SETH (3) WERE USED 4028 1451 42 BETWEEN 500 KEV AND 2 MEV, THE EVALUATED DATA WERE BASED ON 4028 1451 43 MEASUREMENTS OF GREEN AND MITCHELL (4) AND STOOKSBERRY AND 4028 1451 44 ANDERSON (5) 4028 1451 45 ABOVE 2 MEV, THE MEASUREMENTS OF GREEN AND MITCHELL (4), 4028 1451 46 FOSTER AND GLASGOW (6), CARLSON AND BARSCHALL (7) AND 4028 1451 47 PETERSON, ET AL (8) 4028 1451 48 * * * * * * 4028 1451 49 N,2N CROSS SECTION 4028 1451 50 THE CROSS SECTION FOR THE ELEMENT WAS BASED ON ESTIMATES 4028 1451 51 FOR THE ISOTOPES. 4028 1451 52 EXCEPT FOR ZR-90, THE RESULTS FROM A STATISTICAL MODEL WERE USED.4028 1451 53 THE (N,2N) CROSS SECTION FOR ZR-90 WAS BASE ON MEASUREMENTS 4028 1451 54 BY PRESTWOOD AND BAYHURST (9), NETHAWAY (10) AND SEVERAL 4028 1451 55 MEASUREMENTS NEAR 14 MEV 4028 1451 56 * * * * * * 4028 1451 57 N,ALPHA CROSS SECTION 4028 1451 58 THE (N,ALPHA) CROSS SECTION WAS BASED ON ESTIMATES FOR THE 4028 1451 59 ISOTOPES. 4028 1451 60 THE ENERGY DEPENDENT MEASUREMENTS BY BAYHURST AND PRESTWOOD (11),4028 1451 61 STATISTICAL MODEL CALCULATIONS AND SEVERAL MEASUREMENTS AT 4028 1451 62 14 MEV WERE USED 4028 1451 63 * * * * * * 4028 1451 64 (N,P) CROSS SECTION 4028 1451 65 THE (N,P) X/S FOR ZR-90 WAS BASED ON MEASUREMENTS BY 4028 1451 66 CARROL AND STOOKSBERRY (12) AND BAYHURST AND PRESTWOOD (11) 4028 1451 67 THE (N,P) X/S FOR ZR-91 WAS BASED ON MEASUREMENTS BY 4028 1451 68 CARROL AND STOOKSBERRY (12), REED (13) AND LEVKOVSKII (14) 4028 1451 69 THE (N,P) X/S FOR ZR-92 AND ZR-94 WERE BASED ON MEASUREMENTS 4028 1451 70 BY CARROLL AND STOOKSBERRY (12), REED (13), BRAMLITT AND 4028 1451 71 FINK (15), LU, ET AL (16), LEVKOVSKII (14) AND PRASAD AND 4028 1451 72 SARKAR (16) AND PAUL AND CLARKE (17) 4028 1451 73 * * * * * * 4028 1451 74 THE (N,GAMMA) CROSS SECTION 4028 1451 75 THE DATA RECOMMENDED BY BENZI (18) WERE USED 4028 1451 76 * * * * * * 4028 1451 77 INELASTIC SCATTERING CROSS SECTION 4028 1451 78 19 LEVEL EXCITATION CROSS SECTIONS AND A CONTINUUM CROSS 4028 1451 79 SECTION HAS BEEN GIVEN. 4028 1451 80 THE CROSS SECTIONS WERE BASED ON A PREVIOUS EVALUATION BY 4028 1451 81 KAPL AND THE EXPERIMENTAL DATA OF TESSLER, ET AL (19), 4028 1451 82 DAY (20), MC DANIEL, ET AL (21), BRANDENBERGER AND GLASGOW, 4028 1451 83 SMITH AND WHALEN (22), LIND AND DAY (23), TESSLER AND 4028 1451 84 GLICKSTEIN (24), GUENTHER, ET AL (22), GLAZKOV (25) 4028 1451 85 * * * * * * 4028 1451 86 ELASTIC SCATTERING CROSS SECTION 4028 1451 87 BASICALLY, THE ELASTI SCATTERING CROSS SECTION WAS TAKEN 4028 1451 88 AS THE DIFFERENCE BETWEEN THE TOTAL CROSS SECTION AND 4028 1451 89 THE NON-ELASTIC CROSS SECTION. 4028 1451 90 THE EXPERIMENTAL DATA USED, INCLUDING ENGELBRECHT AND SMITH (26) 4028 1451 91 HANS AND SNOWDON (27), KENT, ET AL (28), WALT AND BEYSTER (29), 4028 1451 92 WALT AND BARSCHALL (30), GILBOY AND TOWLE (31) AND 4028 1451 93 CLARK AND CROSS (32) 4028 1451 94 * * * * * * 4028 1451 95 REFERENCES 4028 1451 96 * * * * * * 4028 1451 97 (1) MUGHABGHAB, S.F., DIVADEENAM, M., AND HOLDEN, N.E. NEUTRON 4028 1451 98 CROSS SECTIONS FOURTH EDITION VOLUME I NEUTRON RESONANCE 4028 1451 99 PARAMETERS AND THERMAL CROSS SECTIONS PART A Z=1-60, NEW YORK, 4028 1451 100 ACADEMIC PRESS (1981) 4028 1451 101 (2) NEWSON, H.W., ET AL, ANNALS OF PHYS. 8, 211 (1959) 4028 1451 102 (3) SETH, K.K., PHYS. LETTERS 16, 306 (1965) 4028 1451 103 (4) GREEN, L. AND MITCHELL, J.A, WAPD-TM-1073 (APRIL 1973) 4028 1451 104 (5) STOOKSBERRY, R.W. AND ANDERSON, J.H., NUC-SCI.AND E.51,235,734028 1451 105 (6) FOSTER, D.C., JR. AND GLASGOW, D.W., PHYS.REV. C3,576 (1971) 4028 1451 106 (7) CARLSON, A.D. AND BARSCHALL, H.H., PHYS.REV. 158,1142 (1967) 4028 1451 107 (8) PETERSON, J.M., ET AL, PHYS.REV. 120, 521 (1960) 4028 1451 108 (9) PRESTWOOD, R.J. AND BAYHURST, B.P., PHYS.REV.121, 1438 (1961)4028 1451 109 (10) NETHAWAY, D.R. NUCL. PHYS. A190, 635 (1972) 4028 1451 110 (11) BAYHURST, B.P. AND PRESTWOOD, R.J., J.INORG. NUCL. CHEM. 4028 1451 111 23, 173 (1961) 4028 1451 112 (12) CARROLL, E.E. AND STOOKSBERRY, R.W., NUCL.SCI. ENG. 4028 1451 113 25, 285 (1966) 4028 1451 114 (13) REED, C.H., UC-34 (1960) 4028 1451 115 (14) LEVKOVSKII, V.N., SOV. PHYS. JETP 18, 213 (1964) 4028 1451 116 (15) BRAMLITT, E.T. AND FINK, R.W., PHYS. REV. 131, 2649 (1963) 4028 1451 117 (16) PRASAD, R. AND SARKAR, D.C., NUOVO CIMENTO 3A, 467 (1971) 4028 1451 118 (17) PAUL, E.B. AND CLARKE, R.L., CAN. J. PHYS. 31, 268 (1953) 4028 1451 119 (18) BENZI, V., ET AL, CEC(71) 9 , NOV. 1971 4028 1451 120 (19) TESSLER, G., ET AL. PHYS. REV. C2, 2390 (1970) 4028 1451 121 (20) DAY, R.B. PRI. COMM. (1965) 4028 1451 122 (21) MC DANIEL, F.D, ET.AL. PHYS. REV C10, 1087 (1974) 4028 1451 123 (22) GUENTHER, P., ET AL, ANL/NDM-4 (1974) 4028 1451 124 (23) LIND, D.A. AND DAY, R.B. ANNALS PHYS. 12, 485 (1961) 4028 1451 125 (24) TESSLER, G. AND GLICKSTEIN, S., BULL. AM. PHYS. SOC. 4028 1451 126 20, 174 (1975) 4028 1451 127 (25) GLAZKOV, N.P. A.E. 15, 416 (1963) 4028 1451 128 (26) REITMAN, ET AL, NUCL. PHYS 48, 593 (1963) 4028 1451 129 (27) HANS, H.S. AND SNOWDON, S.C., PHYS. REV. 108, 1028 (1957) 4028 1451 130 (28) KENT, D.W., PHYS. REV. 125, 331 (1962) 4028 1451 131 (29) WALT, M. AND BEYSTER, J.R., PHYS. REV. 98, 677 (1955) 4028 1451 132 (30) WALT, M. AND BARSCHALL, H.H., PHYS. REV. 93, 1062 (1954) 4028 1451 133 (31) GILBOY, W.H. AND TOWLE, J.H., NUCL. PHYS.42, 86 (1963) 4028 1451 134 (32) CLARKE, R.L. AND CROSS, W.G., NUCL. PHYS. A95, 320 (1967) 4028 1451 135 4028 1451 136 1 451 138 04028 1451 137 3 103 13 04028 1451 138 4028 1 0 139 4028 0 0 140 4.009100+4 9.012200+1 0 0 0 04028 3103 141 -7.615000+5-7.615000+5 0 0 1 294028 3103 142 29 2 0 0 0 04028 3103 143 7.700000+5 0.000000+0 4.000000+6 0.000000+0 4.500000+6 2.000000-44028 3103 144 5.000000+6 6.000000-4 5.500000+6 1.300000-3 6.000000+6 2.100000-34028 3103 145 6.500000+6 3.100000-3 7.000000+6 4.200000-3 7.500000+6 5.600000-34028 3103 146 8.000000+6 7.100000-3 8.500000+6 8.900000-3 9.000000+6 1.080000-24028 3103 147 9.500000+6 1.300000-2 1.000000+7 1.520000-2 1.050000+7 1.760000-24028 3103 148 1.100000+7 2.020000-2 1.150000+7 2.270000-2 1.200000+7 2.510000-24028 3103 149 1.250000+7 2.720000-2 1.300000+7 2.910000-2 1.350000+7 3.070000-24028 3103 150 1.400000+7 3.200000-2 1.450000+7 3.300000-2 1.500000+7 3.380000-24028 3103 151 1.600000+7 3.510000-2 1.700000+7 3.570000-2 1.800000+7 3.590000-24028 3103 152 1.900000+7 3.580000-2 2.000000+7 3.540000-2 0.000000+0 0.000000+04028 3103 153 4028 3 0 154 4028 0 0 155 0 0 0 156 4.009200+4 9.111200+1 1 0 0 04031 1451 1 0.000000+0 0.000000+0 0 0 0 64031 1451 2 1.000000+0 0.000000+0 0 0 10 64031 1451 3 0.000000+0 0.000000+0 0 0 132 34031 1451 4 40-ZR- 92 SAI,BNL EVAL-APR76 M.DRAKE,D.SARGIS,T.MAUNG,P.ROSE 4031 1451 5 EPRI NP-250 DIST-JAN90 900126 4031 1451 6 ----ENDF/B-VI MATERIAL 4031 4031 1451 7 -----INCIDENT NEUTRON DATA 4031 1451 8 ------ENDF-6 FORMAT 4031 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4031 1451 10 ACTIVATION II 4031 1451 11 ******************************************************************4031 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4031 1451 13 * * * * * * *4031 1451 14 * * * * * * 4031 1451 15 ZIRCONIUM-92 4031 1451 16 EVALUATED NEUTRON CROSS SECTIONS 4031 1451 17 FOR ZIRCONIUM AND HAFNIUM 4031 1451 18 SAI-76-677-LJ 4031 1451 19 JUNE 1976 4031 1451 20 MARVIN K. DRAKE, DAVE A. SARGIS AND T.MAUNG 4031 1451 21 ISOTOPE EVALUATION CONSTRUCTED FROM SAI DOCUMENTATION 4031 1451 22 BY S. PEARLSTEIN, BNL. 4031 1451 23 * * * * * * 4031 1451 24 RESONANCE REGION REEVALUATED BY P.F. ROSE, BNL 1981 4031 1451 25 RESOLVED RESONANCE PARAMETERS PRIMARILY TAKEN FROM THE 4031 1451 26 RECOMMENDED VALUES GIVEN IN NEUTRON CROSS SECTIONS,FOURTH 4031 1451 27 EDITION, SEE REFERENCE (1) 4031 1451 28 * * * * * * 4031 1451 29 ISOTOPE MAT THERMAL X/S RI 4031 1451 30 ZR-90 1385 0.011 0.179 4031 1451 31 ZR-91 1386 1.188 4.913 4031 1451 32 ZR-92 1387 0.221 0.655 4031 1451 33 ZR-94 1388 0.049 0.311 4031 1451 34 ZR-96 1389 0.023 5.629 4031 1451 35 ZR 1340 0.186 0.965 4031 1451 36 * * * * * * 4031 1451 37 UNRESOLVED PARAMETERS GIVEN FOR ZR-91 ONLY 4031 1451 38 UPPER BOUNDARY OF RESONANCE REGION = 90 KEV 4031 1451 39 * * * * * * 4031 1451 40 TOTAL CROSS SECTION 4031 1451 41 BETWEEN 90 KEV AND 500 KEV THE DATA OF SETH (3) WERE USED 4031 1451 42 BETWEEN 500 KEV AND 2 MEV, THE EVALUATED DATA WERE BASED ON 4031 1451 43 MEASUREMENTS OF GREEN AND MITCHELL (4) AND STOOKSBERRY AND 4031 1451 44 ANDERSON (5) 4031 1451 45 ABOVE 2 MEV, THE MEASUREMENTS OF GREEN AND MITCHELL (4), 4031 1451 46 FOSTER AND GLASGOW (6), CARLSON AND BARSCHALL (7) AND 4031 1451 47 PETERSON, ET AL (8) 4031 1451 48 * * * * * * 4031 1451 49 N,2N CROSS SECTION 4031 1451 50 THE CROSS SECTION FOR THE ELEMENT WAS BASED ON ESTIMATES 4031 1451 51 FOR THE ISOTOPES. 4031 1451 52 EXCEPT FOR ZR-90, THE RESULTS FROM A STATISTICAL MODEL WERE USED.4031 1451 53 THE (N,2N) CROSS SECTION FOR ZR-90 WAS BASE ON MEASUREMENTS 4031 1451 54 BY PRESTWOOD AND BAYHURST (9), NETHAWAY (10) AND SEVERAL 4031 1451 55 MEASUREMENTS NEAR 14 MEV 4031 1451 56 * * * * * * 4031 1451 57 N,ALPHA CROSS SECTION 4031 1451 58 THE (N,ALPHA) CROSS SECTION WAS BASED ON ESTIMATES FOR THE 4031 1451 59 ISOTOPES. 4031 1451 60 THE ENERGY DEPENDENT MEASUREMENTS BY BAYHURST AND PRESTWOOD (11),4031 1451 61 STATISTICAL MODEL CALCULATIONS AND SEVERAL MEASUREMENTS AT 4031 1451 62 14 MEV WERE USED 4031 1451 63 * * * * * * 4031 1451 64 (N,P) CROSS SECTION 4031 1451 65 THE (N,P) X/S FOR ZR-90 WAS BASED ON MEASUREMENTS BY 4031 1451 66 CARROL AND STOOKSBERRY (12) AND BAYHURST AND PRESTWOOD (11) 4031 1451 67 THE (N,P) X/S FOR ZR-91 WAS BASED ON MEASUREMENTS BY 4031 1451 68 CARROL AND STOOKSBERRY (12), REED (13) AND LEVKOVSKII (14) 4031 1451 69 THE (N,P) X/S FOR ZR-92 AND ZR-94 WERE BASED ON MEASUREMENTS 4031 1451 70 BY CARROLL AND STOOKSBERRY (12), REED (13), BRAMLITT AND 4031 1451 71 FINK (15), LU, ET AL (16), LEVKOVSKII (14) AND PRASAD AND 4031 1451 72 SARKAR (16) AND PAUL AND CLARKE (17) 4031 1451 73 * * * * * * 4031 1451 74 THE (N,GAMMA) CROSS SECTION 4031 1451 75 THE DATA RECOMMENDED BY BENZI (18) WERE USED 4031 1451 76 * * * * * * 4031 1451 77 INELASTIC SCATTERING CROSS SECTION 4031 1451 78 19 LEVEL EXCITATION CROSS SECTIONS AND A CONTINUUM CROSS 4031 1451 79 SECTION HAS BEEN GIVEN. 4031 1451 80 THE CROSS SECTIONS WERE BASED ON A PREVIOUS EVALUATION BY 4031 1451 81 KAPL AND THE EXPERIMENTAL DATA OF TESSLER, ET AL (19), 4031 1451 82 DAY (20), MC DANIEL, ET AL (21), BRANDENBERGER AND GLASGOW, 4031 1451 83 SMITH AND WHALEN (22), LIND AND DAY (23), TESSLER AND 4031 1451 84 GLICKSTEIN (24), GUENTHER, ET AL (22), GLAZKOV (25) 4031 1451 85 * * * * * * 4031 1451 86 ELASTIC SCATTERING CROSS SECTION 4031 1451 87 BASICALLY, THE ELASTI SCATTERING CROSS SECTION WAS TAKEN 4031 1451 88 AS THE DIFFERENCE BETWEEN THE TOTAL CROSS SECTION AND 4031 1451 89 THE NON-ELASTIC CROSS SECTION. 4031 1451 90 THE EXPERIMENTAL DATA USED, INCLUDING ENGELBRECHT AND SMITH (26) 4031 1451 91 HANS AND SNOWDON (27), KENT, ET AL (28), WALT AND BEYSTER (29), 4031 1451 92 WALT AND BARSCHALL (30), GILBOY AND TOWLE (31) AND 4031 1451 93 CLARK AND CROSS (32) 4031 1451 94 * * * * * * 4031 1451 95 REFERENCES 4031 1451 96 * * * * * * 4031 1451 97 (1) MUGHABGHAB, S.F., DIVADEENAM, M., AND HOLDEN, N.E. NEUTRON 4031 1451 98 CROSS SECTIONS FOURTH EDITION VOLUME I NEUTRON RESONANCE 4031 1451 99 PARAMETERS AND THERMAL CROSS SECTIONS PART A Z=1-60, NEW YORK, 4031 1451 100 ACADEMIC PRESS (1981) 4031 1451 101 (2) NEWSON, H.W., ET AL, ANNALS OF PHYS. 8, 211 (1959) 4031 1451 102 (3) SETH, K.K., PHYS. LETTERS 16, 306 (1965) 4031 1451 103 (4) GREEN, L. AND MITCHELL, J.A, WAPD-TM-1073 (APRIL 1973) 4031 1451 104 (5) STOOKSBERRY, R.W. AND ANDERSON, J.H., NUC-SCI.AND E.51,235,734031 1451 105 (6) FOSTER, D.C., JR. AND GLASGOW, D.W., PHYS.REV. C3,576 (1971) 4031 1451 106 (7) CARLSON, A.D. AND BARSCHALL, H.H., PHYS.REV. 158,1142 (1967) 4031 1451 107 (8) PETERSON, J.M., ET AL, PHYS.REV. 120, 521 (1960) 4031 1451 108 (9) PRESTWOOD, R.J. AND BAYHURST, B.P., PHYS.REV.121, 1438 (1961)4031 1451 109 (10) NETHAWAY, D.R. NUCL. PHYS. A190, 635 (1972) 4031 1451 110 (11) BAYHURST, B.P. AND PRESTWOOD, R.J., J.INORG. NUCL. CHEM. 4031 1451 111 23, 173 (1961) 4031 1451 112 (12) CARROLL, E.E. AND STOOKSBERRY, R.W., NUCL.SCI. ENG. 4031 1451 113 25, 285 (1966) 4031 1451 114 (13) REED, C.H., UC-34 (1960) 4031 1451 115 (14) LEVKOVSKII, V.N., SOV. PHYS. JETP 18, 213 (1964) 4031 1451 116 (15) BRAMLITT, E.T. AND FINK, R.W., PHYS. REV. 131, 2649 (1963) 4031 1451 117 (16) PRASAD, R. AND SARKAR, D.C., NUOVO CIMENTO 3A, 467 (1971) 4031 1451 118 (17) PAUL, E.B. AND CLARKE, R.L., CAN. J. PHYS. 31, 268 (1953) 4031 1451 119 (18) BENZI, V., ET AL, CEC(71) 9 , NOV. 1971 4031 1451 120 (19) TESSLER, G., ET AL. PHYS. REV. C2, 2390 (1970) 4031 1451 121 (20) DAY, R.B. PRI. COMM. (1965) 4031 1451 122 (21) MC DANIEL, F.D, ET.AL. PHYS. REV C10, 1087 (1974) 4031 1451 123 (22) GUENTHER, P., ET AL, ANL/NDM-4 (1974) 4031 1451 124 (23) LIND, D.A. AND DAY, R.B. ANNALS PHYS. 12, 485 (1961) 4031 1451 125 (24) TESSLER, G. AND GLICKSTEIN, S., BULL. AM. PHYS. SOC. 4031 1451 126 20, 174 (1975) 4031 1451 127 (25) GLAZKOV, N.P. A.E. 15, 416 (1963) 4031 1451 128 (26) REITMAN, ET AL, NUCL. PHYS 48, 593 (1963) 4031 1451 129 (27) HANS, H.S. AND SNOWDON, S.C., PHYS. REV. 108, 1028 (1957) 4031 1451 130 (28) KENT, D.W., PHYS. REV. 125, 331 (1962) 4031 1451 131 (29) WALT, M. AND BEYSTER, J.R., PHYS. REV. 98, 677 (1955) 4031 1451 132 (30) WALT, M. AND BARSCHALL, H.H., PHYS. REV. 93, 1062 (1954) 4031 1451 133 (31) GILBOY, W.H. AND TOWLE, J.H., NUCL. PHYS.42, 86 (1963) 4031 1451 134 (32) CLARKE, R.L. AND CROSS, W.G., NUCL. PHYS. A95, 320 (1967) 4031 1451 135 4031 1451 136 1 451 139 04031 1451 137 2 151 85 04031 1451 138 3 102 69 04031 1451 139 4031 1 0 140 4031 0 0 141 4.009200+4 9.111200+1 0 0 1 04031 2151 142 4.009200+4 1.000000+0 0 0 1 04031 2151 143 1.000000-5 9.000000+4 1 2 0 04031 2151 144 0.000000+0 7.420000-1 0 0 2 04031 2151 145 9.120700+1 0.000000+0 0 0 96 164031 2151 146 -8.600000+1 5.000000-1 1.480000-1 1.700000-2 1.310000-1 0.000000+04031 2151 147 2.686000+3 5.000000-1 2.537000+1 2.520000+1 1.700000-1 0.000000+04031 2151 148 4.638000+3 5.000000-1 1.531500+1 1.520000+1 1.150000-1 0.000000+04031 2151 149 6.809000+3 5.000000-1 7.337000+1 7.300000+1 3.700000-1 0.000000+04031 2151 150 9.121000+3 5.000000-1 6.393000+0 6.300000+0 9.300000-2 0.000000+04031 2151 151 2.018000+4 5.000000-1 1.610000+0 1.300000+0 3.100000-1 0.000000+04031 2151 152 2.308000+4 5.000000-1 1.080800+2 1.080000+2 8.000000-2 0.000000+04031 2151 153 2.567000+4 5.000000-1 2.630000+0 2.500000+0 1.300000-1 0.000000+04031 2151 154 3.036000+4 5.000000-1 4.740500+0 4.600000+0 1.404600-1 0.000000+04031 2151 155 3.308000+4 5.000000-1 1.207800+1 1.200000+1 7.800000-2 0.000000+04031 2151 156 3.945000+4 5.000000-1 7.312000+1 7.300000+1 1.200000-1 0.000000+04031 2151 157 4.757000+4 5.000000-1 1.200700+2 1.200000+2 6.900000-2 0.000000+04031 2151 158 5.265000+4 5.000000-1 1.750900+2 1.750000+2 9.000000-2 0.000000+04031 2151 159 5.615000+4 5.000000-1 9.007000+1 9.000000+1 7.000000-2 0.000000+04031 2151 160 9.120000+4 5.000000-1 3.014000+1 3.000000+1 1.404600-1 0.000000+04031 2151 161 1.024000+5 5.000000-1 5.014000+1 5.000000+1 1.404600-1 0.000000+04031 2151 162 9.120700+1 0.000000+0 1 0 378 634031 2151 163 2.010000+3 1.500000+0 3.912500-1 2.650000-2 3.647500-1 0.000000+04031 2151 164 4.118000+3 1.500000+0 3.300000+0 3.000000+0 3.000000-1 0.000000+04031 2151 165 5.039000+3 5.000000-1 1.258000+0 1.070000+0 1.880000-1 0.000000+04031 2151 166 6.635000+3 1.500000+0 1.310000+0 9.800000-1 3.300000-1 0.000000+04031 2151 167 8.831000+3 5.000000-1 4.131000+0 4.000000+0 1.310000-1 0.000000+04031 2151 168 9.804000+3 1.500000+0 1.460000+0 1.350000+0 1.100000-1 0.000000+04031 2151 169 1.193600+4 1.500000+0 1.750000+0 1.600000+0 1.500000-1 0.000000+04031 2151 170 1.200200+4 5.000000-1 9.200000+0 9.000000+0 2.000000-1 0.000000+04031 2151 171 1.305300+4 1.500000+0 1.610000+0 1.500000+0 1.100000-1 0.000000+04031 2151 172 1.441000+4 5.000000-1 1.418000+1 1.400000+1 1.800000-1 0.000000+04031 2151 173 1.501700+4 1.500000+0 6.147500-1 2.500000-1 3.647500-1 0.000000+04031 2151 174 1.711000+4 1.500000+0 1.226000+1 1.210000+1 1.600000-1 0.000000+04031 2151 175 1.905000+4 1.500000+0 2.290000+0 2.150000+0 1.400000-1 0.000000+04031 2151 176 2.083000+4 5.000000-1 2.810000+0 2.400000+0 4.100000-1 0.000000+04031 2151 177 2.196000+4 5.000000-1 3.090000+0 2.800000+0 2.900000-1 0.000000+04031 2151 178 2.619000+4 1.500000+0 1.114800+0 7.500000-1 3.647500-1 0.000000+04031 2151 179 2.675000+4 1.500000+0 1.514800+0 1.150000+0 3.647500-1 0.000000+04031 2151 180 2.730000+4 5.000000-1 2.292000+1 2.250000+1 4.200000-1 0.000000+04031 2151 181 2.808000+4 1.500000+0 1.264000+1 1.250000+1 1.400000-1 0.000000+04031 2151 182 2.815000+4 5.000000-1 6.210000+0 6.000000+0 2.100000-1 0.000000+04031 2151 183 3.090000+4 1.500000+0 1.231000+1 1.200000+1 3.100000-1 0.000000+04031 2151 184 3.244000+4 1.500000+0 1.172000+1 1.150000+1 2.200000-1 0.000000+04031 2151 185 3.499000+4 5.000000-1 6.518000+1 6.500000+1 1.800000-1 0.000000+04031 2151 186 3.564000+4 5.000000-1 5.233000+1 5.200000+1 3.300000-1 0.000000+04031 2151 187 3.591000+4 1.500000+0 2.674000+1 2.650000+1 2.400000-1 0.000000+04031 2151 188 3.750000+4 5.000000-1 1.432000+1 1.400000+1 3.200000-1 0.000000+04031 2151 189 3.874000+4 5.000000-1 4.610000+0 4.500000+0 1.100000-1 0.000000+04031 2151 190 3.892000+4 1.500000+0 5.200000+0 5.000000+0 2.000000-1 0.000000+04031 2151 191 3.930000+4 5.000000-1 7.039000+1 7.000000+1 3.900000-1 0.000000+04031 2151 192 4.120000+4 1.500000+0 1.524000+1 1.500000+1 2.400000-1 0.000000+04031 2151 193 4.375000+4 1.500000+0 2.864700+0 2.500000+0 3.647500-1 0.000000+04031 2151 194 4.503000+4 5.000000-1 1.053800+2 1.050000+2 3.800000-1 0.000000+04031 2151 195 4.571000+4 5.000000-1 3.630000+1 3.600000+1 3.000000-1 0.000000+04031 2151 196 4.687000+4 1.500000+0 2.657500+2 2.650000+2 7.500000-1 0.000000+04031 2151 197 4.928000+4 1.500000+0 6.364800+0 6.000000+0 3.647500-1 0.000000+04031 2151 198 4.980000+4 1.500000+0 5.864800+0 5.500000+0 3.647500-1 0.000000+04031 2151 199 5.350000+4 1.500000+0 7.864800+0 7.500000+0 3.647500-1 0.000000+04031 2151 200 5.450000+4 1.500000+0 1.364800+0 1.000000+0 3.647500-1 0.000000+04031 2151 201 5.560000+4 1.500000+0 1.036500+1 1.000000+1 3.647500-1 0.000000+04031 2151 202 5.815000+4 1.500000+0 2.286500+1 2.250000+1 3.647500-1 0.000000+04031 2151 203 6.094000+4 1.500000+0 7.526000+1 7.500000+1 2.600000-1 0.000000+04031 2151 204 6.265000+4 1.500000+0 2.018000+1 2.000000+1 1.800000-1 0.000000+04031 2151 205 6.342000+4 1.500000+0 8.045000+1 8.000000+1 4.500000-1 0.000000+04031 2151 206 6.745000+4 1.500000+0 1.436500+1 1.400000+1 3.647500-1 0.000000+04031 2151 207 6.914000+4 1.500000+0 1.436500+1 1.400000+1 3.647500-1 0.000000+04031 2151 208 7.275000+4 1.500000+0 2.136500+1 2.100000+1 3.647500-1 0.000000+04031 2151 209 8.075000+4 5.000000-1 6.036500+1 6.000000+1 3.647500-1 0.000000+04031 2151 210 8.300000+4 1.500000+0 1.102200+2 1.100000+2 2.200000-1 0.000000+04031 2151 211 8.340000+4 1.500000+0 6.286500+1 6.250000+1 3.647500-1 0.000000+04031 2151 212 8.470000+4 1.500000+0 2.054900+2 2.050000+2 4.900000-1 0.000000+04031 2151 213 8.949000+4 1.500000+0 5.407500+2 5.400000+2 7.500000-1 0.000000+04031 2151 214 9.315000+4 1.500000+0 2.305000+2 2.300000+2 5.000000-1 0.000000+04031 2151 215 9.435000+4 1.500000+0 1.902900+2 1.900000+2 2.900000-1 0.000000+04031 2151 216 9.885000+4 5.000000-1 1.804800+2 1.800000+2 4.800000-1 0.000000+04031 2151 217 1.003500+5 1.500000+0 2.756900+2 2.750000+2 6.900000-1 0.000000+04031 2151 218 1.039000+5 5.000000-1 8.036500+1 8.000000+1 3.647500-1 0.000000+04031 2151 219 1.045000+5 5.000000-1 8.036500+1 8.000000+1 3.647500-1 0.000000+04031 2151 220 1.060500+5 1.500000+0 9.213400+2 9.200000+2 1.340000+0 0.000000+04031 2151 221 1.114000+5 1.500000+0 1.500700+2 1.500000+2 7.000000-2 0.000000+04031 2151 222 1.132200+5 1.500000+0 1.604500+2 1.600000+2 4.500000-1 0.000000+04031 2151 223 1.156500+5 5.000000-1 2.036500+1 2.000000+1 3.647500-1 0.000000+04031 2151 224 1.190000+5 1.500000+0 5.509600+2 5.500000+2 9.600000-1 0.000000+04031 2151 225 1.200000+5 5.000000-1 5.514800+2 5.500000+2 1.480000+0 0.000000+04031 2151 226 4031 2 0 227 4031 0 0 228 4.009200+4 9.111200+1 0 0 0 04031 3102 229 7.980000+6 7.980000+6 0 0 1 1964031 3102 230 196 2 0 0 0 04031 3102 231 1.000000-5 0.000000+0 2.530000-2 0.000000+0 1.000000+3 0.000000+04031 3102 232 9.000000+4 0.000000+0 9.000000+4 1.828460-2 9.300000+4 1.790000-24031 3102 233 9.700000+4 1.749000-2 1.000000+5 1.710000-2 1.050000+5 1.690000-24031 3102 234 1.100000+5 1.680000-2 1.150000+5 1.650000-2 1.200000+5 1.620000-24031 3102 235 1.250000+5 1.600000-2 1.300000+5 1.580000-2 1.350000+5 1.550000-24031 3102 236 1.400000+5 1.530000-2 1.450000+5 1.510000-2 1.500000+5 1.500000-24031 3102 237 1.550000+5 1.490000-2 1.600000+5 1.480000-2 1.650000+5 1.460000-24031 3102 238 1.700000+5 1.440000-2 1.750000+5 1.420000-2 1.800000+5 1.400000-24031 3102 239 1.850000+5 1.380000-2 1.900000+5 1.360000-2 1.950000+5 1.350000-24031 3102 240 2.000000+5 1.340000-2 2.100000+5 1.330000-2 2.200000+5 1.310000-24031 3102 241 2.300000+5 1.290000-2 2.400000+5 1.270000-2 2.500000+5 1.260000-24031 3102 242 2.600000+5 1.250000-2 2.700000+5 1.240000-2 2.800000+5 1.230000-24031 3102 243 2.900000+5 1.220000-2 3.000000+5 1.210000-2 3.100000+5 1.200000-24031 3102 244 3.200000+5 1.190000-2 3.300000+5 1.180000-2 3.400000+5 1.170000-24031 3102 245 4.000000+5 1.170000-2 4.100000+5 1.180000-2 4.300000+5 1.180000-24031 3102 246 4.400000+5 1.190000-2 5.100000+5 1.190000-2 5.200000+5 1.200000-24031 3102 247 5.400000+5 1.200000-2 5.500000+5 1.210000-2 5.700000+5 1.210000-24031 3102 248 5.800000+5 1.220000-2 6.000000+5 1.220000-2 6.200000+5 1.230000-24031 3102 249 6.400000+5 1.240000-2 6.600000+5 1.260000-2 6.800000+5 1.280000-24031 3102 250 7.000000+5 1.300000-2 7.200000+5 1.310000-2 7.400000+5 1.320000-24031 3102 251 7.600000+5 1.330000-2 7.800000+5 1.340000-2 8.000000+5 1.350000-24031 3102 252 8.200000+5 1.370000-2 8.400000+5 1.380000-2 8.600000+5 1.390000-24031 3102 253 8.800000+5 1.400000-2 9.000000+5 1.410000-2 9.200000+5 1.400000-24031 3102 254 9.281000+5 1.390000-2 9.400000+5 1.380000-2 9.448000+5 1.370000-24031 3102 255 9.600000+5 1.320000-2 9.800000+5 1.270000-2 1.000000+6 1.150000-24031 3102 256 1.050000+6 1.030000-2 1.100000+6 1.010000-2 1.150000+6 1.000000-24031 3102 257 1.218300+6 1.000000-2 1.250000+6 1.010000-2 1.314000+6 1.010000-24031 3102 258 1.350000+6 1.020000-2 1.398000+6 1.030000-2 1.400000+6 1.030000-24031 3102 259 1.450000+6 1.050000-2 1.476100+6 1.060000-2 1.500000+6 1.070000-24031 3102 260 1.600000+6 1.110000-2 1.687000+6 1.140000-2 1.700000+6 1.170000-24031 3102 261 1.780000+6 1.210000-2 1.800000+6 1.220000-2 1.870000+6 1.240000-24031 3102 262 1.900000+6 1.260000-2 2.000000+6 1.280000-2 2.073000+6 1.220000-24031 3102 263 2.100000+6 1.200000-2 2.174000+6 1.120000-2 2.200000+6 1.090000-24031 3102 264 2.286000+6 1.010000-2 2.300000+6 9.900000-3 2.345000+6 9.400000-34031 3102 265 2.346000+6 9.300000-3 2.376000+6 9.200000-3 2.400000+6 8.900000-34031 3102 266 2.500000+6 7.900000-3 2.585000+6 7.000000-3 2.600000+6 6.700000-34031 3102 267 2.639000+6 6.400000-3 2.700000+6 5.900000-3 2.769000+6 5.400000-34031 3102 268 2.779000+6 5.300000-3 2.800000+6 5.200000-3 2.871000+6 4.800000-34031 3102 269 2.900000+6 4.700000-3 3.000000+6 4.400000-3 3.073000+6 4.250000-34031 3102 270 3.100000+6 4.200000-3 3.111000+6 4.200000-3 3.189000+6 4.070000-34031 3102 271 3.200000+6 4.020000-3 3.300000+6 3.930000-3 3.347000+6 3.870000-34031 3102 272 3.400000+6 3.850000-3 3.408000+6 3.800000-3 3.487000+6 3.750000-34031 3102 273 3.500000+6 3.720000-3 3.600000+6 3.700000-3 3.629000+6 3.690000-34031 3102 274 3.700000+6 3.670000-3 3.800000+6 3.640000-3 3.883000+6 3.580000-34031 3102 275 3.900000+6 3.480000-3 4.000000+6 3.370000-3 4.015000+6 3.360000-34031 3102 276 4.200000+6 3.240000-3 4.400000+6 2.920000-3 4.600000+6 2.550000-34031 3102 277 4.800000+6 2.180000-3 5.000000+6 1.830000-3 5.200000+6 1.650000-34031 3102 278 5.400000+6 1.500000-3 5.600000+6 1.370000-3 5.800000+6 1.240000-34031 3102 279 6.000000+6 1.140000-3 6.200000+6 1.050000-3 6.400000+6 9.900000-44031 3102 280 6.600000+6 9.200000-4 6.800000+6 8.600000-4 7.000000+6 8.100000-44031 3102 281 7.200000+6 7.600000-4 7.270000+6 7.500000-4 7.400000+6 7.200000-44031 3102 282 7.600000+6 6.800000-4 7.800000+6 6.500000-4 8.000000+6 6.200000-44031 3102 283 8.200000+6 5.900000-4 8.400000+6 5.600000-4 8.460000+6 5.500000-44031 3102 284 8.600000+6 5.300000-4 8.800000+6 5.100000-4 9.000000+6 4.900000-44031 3102 285 9.200000+6 4.800000-4 9.400000+6 4.700000-4 9.600000+6 4.600000-44031 3102 286 9.800000+6 4.600000-4 1.000000+7 4.700000-4 1.020000+7 4.800000-44031 3102 287 1.040000+7 4.900000-4 1.060000+7 5.000000-4 1.080000+7 5.200000-44031 3102 288 1.100000+7 5.500000-4 1.120000+7 5.700000-4 1.140000+7 6.000000-44031 3102 289 1.160000+7 6.300000-4 1.180000+7 6.500000-4 1.200000+7 6.800000-44031 3102 290 1.220000+7 7.100000-4 1.240000+7 7.300000-4 1.260000+7 7.500000-44031 3102 291 1.280000+7 7.700000-4 1.300000+7 7.900000-4 1.320000+7 8.000000-44031 3102 292 1.340000+7 8.100000-4 1.360000+7 8.200000-4 1.380000+7 8.300000-44031 3102 293 1.550000+7 8.300000-4 1.600000+7 8.200000-4 1.650000+7 8.100000-44031 3102 294 1.700000+7 7.800000-4 1.750000+7 7.600000-4 1.800000+7 7.300000-44031 3102 295 1.850000+7 7.100000-4 1.900000+7 6.800000-4 1.950000+7 6.500000-44031 3102 296 2.000000+7 6.300000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+04031 3102 297 4031 3 0 298 4031 0 0 299 0 0 0 300 4.009400+4 9.309600+1 1 0 0 04037 1451 1 0.000000+0 0.000000+0 0 0 0 64037 1451 2 1.000000+0 0.000000+0 0 0 10 64037 1451 3 0.000000+0 0.000000+0 0 0 132 44037 1451 4 40-ZR- 94 SAI,BNL EVAL-APR76 M.DRAKE,D.SARGIS,T.MAUNG,P.ROSE 4037 1451 5 EPRI NP-250 DIST-JAN90 900126 4037 1451 6 ----ENDF/B-VI MATERIAL 4037 4037 1451 7 -----INCIDENT NEUTRON DATA 4037 1451 8 ------ENDF-6 FORMAT 4037 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4037 1451 10 ACTIVATION II 4037 1451 11 ******************************************************************4037 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4037 1451 13 * * * * * * *4037 1451 14 * * * * * * 4037 1451 15 ZIRCONIUM-94 4037 1451 16 EVALUATED NEUTRON CROSS SECTIONS 4037 1451 17 FOR ZIRCONIUM AND HAFNIUM 4037 1451 18 SAI-76-677-LJ 4037 1451 19 JUNE 1976 4037 1451 20 MARVIN K. DRAKE, DAVE A. SARGIS AND T.MAUNG 4037 1451 21 ISOTOPE EVALUATION CONSTRUCTED FROM SAI DOCUMENTATION 4037 1451 22 BY S. PEARLSTEIN, BNL. 4037 1451 23 * * * * * * 4037 1451 24 RESONANCE REGION REEVALUATED BY P.F. ROSE, BNL 1981 4037 1451 25 RESOLVED RESONANCE PARAMETERS PRIMARILY TAKEN FROM THE 4037 1451 26 RECOMMENDED VALUES GIVEN IN NEUTRON CROSS SECTIONS,FOURTH 4037 1451 27 EDITION, SEE REFERENCE (1) 4037 1451 28 * * * * * * 4037 1451 29 ISOTOPE MAT THERMAL X/S RI 4037 1451 30 ZR-90 1385 0.011 0.179 4037 1451 31 ZR-91 1386 1.188 4.913 4037 1451 32 ZR-92 1387 0.221 0.655 4037 1451 33 ZR-94 1388 0.049 0.311 4037 1451 34 ZR-96 1389 0.023 5.629 4037 1451 35 ZR 1340 0.186 0.965 4037 1451 36 * * * * * * 4037 1451 37 UNRESOLVED PARAMETERS GIVEN FOR ZR-91 ONLY 4037 1451 38 UPPER BOUNDARY OF RESONANCE REGION = 90 KEV 4037 1451 39 * * * * * * 4037 1451 40 TOTAL CROSS SECTION 4037 1451 41 BETWEEN 90 KEV AND 500 KEV THE DATA OF SETH (3) WERE USED 4037 1451 42 BETWEEN 500 KEV AND 2 MEV, THE EVALUATED DATA WERE BASED ON 4037 1451 43 MEASUREMENTS OF GREEN AND MITCHELL (4) AND STOOKSBERRY AND 4037 1451 44 ANDERSON (5) 4037 1451 45 ABOVE 2 MEV, THE MEASUREMENTS OF GREEN AND MITCHELL (4), 4037 1451 46 FOSTER AND GLASGOW (6), CARLSON AND BARSCHALL (7) AND 4037 1451 47 PETERSON, ET AL (8) 4037 1451 48 * * * * * * 4037 1451 49 N,2N CROSS SECTION 4037 1451 50 THE CROSS SECTION FOR THE ELEMENT WAS BASED ON ESTIMATES 4037 1451 51 FOR THE ISOTOPES. 4037 1451 52 EXCEPT FOR ZR-90, THE RESULTS FROM A STATISTICAL MODEL WERE USED.4037 1451 53 THE (N,2N) CROSS SECTION FOR ZR-90 WAS BASE ON MEASUREMENTS 4037 1451 54 BY PRESTWOOD AND BAYHURST (9), NETHAWAY (10) AND SEVERAL 4037 1451 55 MEASUREMENTS NEAR 14 MEV 4037 1451 56 * * * * * * 4037 1451 57 N,ALPHA CROSS SECTION 4037 1451 58 THE (N,ALPHA) CROSS SECTION WAS BASED ON ESTIMATES FOR THE 4037 1451 59 ISOTOPES. 4037 1451 60 THE ENERGY DEPENDENT MEASUREMENTS BY BAYHURST AND PRESTWOOD (11),4037 1451 61 STATISTICAL MODEL CALCULATIONS AND SEVERAL MEASUREMENTS AT 4037 1451 62 14 MEV WERE USED 4037 1451 63 * * * * * * 4037 1451 64 (N,P) CROSS SECTION 4037 1451 65 THE (N,P) X/S FOR ZR-90 WAS BASED ON MEASUREMENTS BY 4037 1451 66 CARROL AND STOOKSBERRY (12) AND BAYHURST AND PRESTWOOD (11) 4037 1451 67 THE (N,P) X/S FOR ZR-91 WAS BASED ON MEASUREMENTS BY 4037 1451 68 CARROL AND STOOKSBERRY (12), REED (13) AND LEVKOVSKII (14) 4037 1451 69 THE (N,P) X/S FOR ZR-92 AND ZR-94 WERE BASED ON MEASUREMENTS 4037 1451 70 BY CARROLL AND STOOKSBERRY (12), REED (13), BRAMLITT AND 4037 1451 71 FINK (15), LU, ET AL (16), LEVKOVSKII (14) AND PRASAD AND 4037 1451 72 SARKAR (16) AND PAUL AND CLARKE (17) 4037 1451 73 * * * * * * 4037 1451 74 THE (N,GAMMA) CROSS SECTION 4037 1451 75 THE DATA RECOMMENDED BY BENZI (18) WERE USED 4037 1451 76 * * * * * * 4037 1451 77 INELASTIC SCATTERING CROSS SECTION 4037 1451 78 19 LEVEL EXCITATION CROSS SECTIONS AND A CONTINUUM CROSS 4037 1451 79 SECTION HAS BEEN GIVEN. 4037 1451 80 THE CROSS SECTIONS WERE BASED ON A PREVIOUS EVALUATION BY 4037 1451 81 KAPL AND THE EXPERIMENTAL DATA OF TESSLER, ET AL (19), 4037 1451 82 DAY (20), MC DANIEL, ET AL (21), BRANDENBERGER AND GLASGOW, 4037 1451 83 SMITH AND WHALEN (22), LIND AND DAY (23), TESSLER AND 4037 1451 84 GLICKSTEIN (24), GUENTHER, ET AL (22), GLAZKOV (25) 4037 1451 85 * * * * * * 4037 1451 86 ELASTIC SCATTERING CROSS SECTION 4037 1451 87 BASICALLY, THE ELASTI SCATTERING CROSS SECTION WAS TAKEN 4037 1451 88 AS THE DIFFERENCE BETWEEN THE TOTAL CROSS SECTION AND 4037 1451 89 THE NON-ELASTIC CROSS SECTION. 4037 1451 90 THE EXPERIMENTAL DATA USED, INCLUDING ENGELBRECHT AND SMITH (26) 4037 1451 91 HANS AND SNOWDON (27), KENT, ET AL (28), WALT AND BEYSTER (29), 4037 1451 92 WALT AND BARSCHALL (30), GILBOY AND TOWLE (31) AND 4037 1451 93 CLARK AND CROSS (32) 4037 1451 94 * * * * * * 4037 1451 95 REFERENCES 4037 1451 96 * * * * * * 4037 1451 97 (1) MUGHABGHAB, S.F., DIVADEENAM, M., AND HOLDEN, N.E. NEUTRON 4037 1451 98 CROSS SECTIONS FOURTH EDITION VOLUME I NEUTRON RESONANCE 4037 1451 99 PARAMETERS AND THERMAL CROSS SECTIONS PART A Z=1-60, NEW YORK, 4037 1451 100 ACADEMIC PRESS (1981) 4037 1451 101 (2) NEWSON, H.W., ET AL, ANNALS OF PHYS. 8, 211 (1959) 4037 1451 102 (3) SETH, K.K., PHYS. LETTERS 16, 306 (1965) 4037 1451 103 (4) GREEN, L. AND MITCHELL, J.A, WAPD-TM-1073 (APRIL 1973) 4037 1451 104 (5) STOOKSBERRY, R.W. AND ANDERSON, J.H., NUC-SCI.AND E.51,235,734037 1451 105 (6) FOSTER, D.C., JR. AND GLASGOW, D.W., PHYS.REV. C3,576 (1971) 4037 1451 106 (7) CARLSON, A.D. AND BARSCHALL, H.H., PHYS.REV. 158,1142 (1967) 4037 1451 107 (8) PETERSON, J.M., ET AL, PHYS.REV. 120, 521 (1960) 4037 1451 108 (9) PRESTWOOD, R.J. AND BAYHURST, B.P., PHYS.REV.121, 1438 (1961)4037 1451 109 (10) NETHAWAY, D.R. NUCL. PHYS. A190, 635 (1972) 4037 1451 110 (11) BAYHURST, B.P. AND PRESTWOOD, R.J., J.INORG. NUCL. CHEM. 4037 1451 111 23, 173 (1961) 4037 1451 112 (12) CARROLL, E.E. AND STOOKSBERRY, R.W., NUCL.SCI. ENG. 4037 1451 113 25, 285 (1966) 4037 1451 114 (13) REED, C.H., UC-34 (1960) 4037 1451 115 (14) LEVKOVSKII, V.N., SOV. PHYS. JETP 18, 213 (1964) 4037 1451 116 (15) BRAMLITT, E.T. AND FINK, R.W., PHYS. REV. 131, 2649 (1963) 4037 1451 117 (16) PRASAD, R. AND SARKAR, D.C., NUOVO CIMENTO 3A, 467 (1971) 4037 1451 118 (17) PAUL, E.B. AND CLARKE, R.L., CAN. J. PHYS. 31, 268 (1953) 4037 1451 119 (18) BENZI, V., ET AL, CEC(71) 9 , NOV. 1971 4037 1451 120 (19) TESSLER, G., ET AL. PHYS. REV. C2, 2390 (1970) 4037 1451 121 (20) DAY, R.B. PRI. COMM. (1965) 4037 1451 122 (21) MC DANIEL, F.D, ET.AL. PHYS. REV C10, 1087 (1974) 4037 1451 123 (22) GUENTHER, P., ET AL, ANL/NDM-4 (1974) 4037 1451 124 (23) LIND, D.A. AND DAY, R.B. ANNALS PHYS. 12, 485 (1961) 4037 1451 125 (24) TESSLER, G. AND GLICKSTEIN, S., BULL. AM. PHYS. SOC. 4037 1451 126 20, 174 (1975) 4037 1451 127 (25) GLAZKOV, N.P. A.E. 15, 416 (1963) 4037 1451 128 (26) REITMAN, ET AL, NUCL. PHYS 48, 593 (1963) 4037 1451 129 (27) HANS, H.S. AND SNOWDON, S.C., PHYS. REV. 108, 1028 (1957) 4037 1451 130 (28) KENT, D.W., PHYS. REV. 125, 331 (1962) 4037 1451 131 (29) WALT, M. AND BEYSTER, J.R., PHYS. REV. 98, 677 (1955) 4037 1451 132 (30) WALT, M. AND BARSCHALL, H.H., PHYS. REV. 93, 1062 (1954) 4037 1451 133 (31) GILBOY, W.H. AND TOWLE, J.H., NUCL. PHYS.42, 86 (1963) 4037 1451 134 (32) CLARKE, R.L. AND CROSS, W.G., NUCL. PHYS. A95, 320 (1967) 4037 1451 135 4037 1451 136 1 451 140 04037 1451 137 2 151 77 04037 1451 138 3 16 12 04037 1451 139 3 102 69 04037 1451 140 4037 1 0 141 4037 0 0 142 4.009400+4 9.309600+1 0 0 1 04037 2151 143 4.009400+4 1.000000+0 0 0 1 04037 2151 144 1.000000-5 9.000000+4 1 2 0 04037 2151 145 0.000000+0 7.420000-1 0 0 2 04037 2151 146 9.318900+1 0.000000+0 0 0 138 234037 2151 147 -1.400000+3 5.000000-1 5.792000+0 5.660000+0 1.320000-1 0.000000+04037 2151 148 2.243000+3 5.000000-1 1.327000+0 1.230000+0 9.700000-2 0.000000+04037 2151 149 5.755000+3 5.000000-1 1.274400+1 1.270000+1 4.400000-2 0.000000+04037 2151 150 7.065000+3 5.000000-1 2.407400+1 2.400000+1 7.400000-2 0.000000+04037 2151 151 1.339000+4 5.000000-1 3.129800+0 3.000000+0 1.297800-1 0.000000+04037 2151 152 1.924000+4 5.000000-1 1.600700+2 1.600000+2 6.500000-2 0.000000+04037 2151 153 1.986000+4 5.000000-1 6.680000+0 6.600000+0 8.000000-2 0.000000+04037 2151 154 2.226000+4 5.000000-1 1.203500+1 1.200000+1 3.500000-2 0.000000+04037 2151 155 2.975000+4 5.000000-1 6.092000+0 6.000000+0 9.200000-2 0.000000+04037 2151 156 3.486000+4 5.000000-1 8.412000+1 8.400000+1 1.200000-1 0.000000+04037 2151 157 3.533000+4 5.000000-1 1.213000+1 1.200000+1 1.297800-1 0.000000+04037 2151 158 3.570000+4 5.000000-1 8.129800+0 8.000000+0 1.297800-1 0.000000+04037 2151 159 3.972000+4 5.000000-1 6.129800+0 6.000000+0 1.297800-1 0.000000+04037 2151 160 4.368000+4 5.000000-1 4.623000+1 4.600000+1 2.300000-1 0.000000+04037 2151 161 4.442000+4 5.000000-1 5.129800+0 5.000000+0 1.297800-1 0.000000+04037 2151 162 4.552000+4 5.000000-1 5.007700+1 5.000000+1 7.700000-2 0.000000+04037 2151 163 4.840000+4 5.000000-1 3.704000+1 3.700000+1 4.000000-2 0.000000+04037 2151 164 6.095000+4 5.000000-1 3.060000+0 3.000000+0 6.000000-2 0.000000+04037 2151 165 6.590000+4 5.000000-1 3.712000+1 3.700000+1 1.200000-1 0.000000+04037 2151 166 7.283000+4 5.000000-1 5.520000+1 5.500000+1 2.000000-1 0.000000+04037 2151 167 8.159000+4 5.000000-1 5.921000+1 5.900000+1 2.100000-1 0.000000+04037 2151 168 8.733000+4 5.000000-1 2.703600+2 2.700000+2 3.600000-1 0.000000+04037 2151 169 8.830000+4 5.000000-1 8.530000+1 8.500000+1 3.000000-1 0.000000+04037 2151 170 9.318900+1 0.000000+0 1 0 288 484037 2151 171 4.920000+3 1.500000+0 3.750000-1 2.250000-1 1.500000-1 0.000000+04037 2151 172 5.814000+3 1.500000+0 2.840000+0 2.660000+0 1.800000-1 0.000000+04037 2151 173 7.705000+3 1.500000+0 8.960000-1 8.000000-1 9.600000-2 0.000000+04037 2151 174 1.013000+4 1.500000+0 2.394000+0 2.300000+0 9.400000-2 0.000000+04037 2151 175 1.056000+4 5.000000-1 1.760000+0 1.700000+0 6.000000-2 0.000000+04037 2151 176 1.203000+4 5.000000-1 3.236000+0 3.100000+0 1.360000-1 0.000000+04037 2151 177 1.251000+4 1.500000+0 1.095400+1 1.080000+1 1.540000-1 0.000000+04037 2151 178 1.422000+4 1.500000+0 2.490000+0 2.400000+0 9.000000-2 0.000000+04037 2151 179 1.538000+4 5.000000-1 8.416000+0 8.300000+0 1.160000-1 0.000000+04037 2151 180 1.735000+4 5.000000-1 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1.600000+7 8.200000-4 1.650000+7 8.100000-44037 3102 300 1.700000+7 7.800000-4 1.750000+7 7.600000-4 1.800000+7 7.300000-44037 3102 301 1.850000+7 7.100000-4 1.900000+7 6.800000-4 1.950000+7 6.500000-44037 3102 302 2.000000+7 6.300000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+04037 3102 303 4037 3 0 304 4037 0 0 305 0 0 0 306 4.109300+4 9.210510+1 1 0 0 14125 1451 1 0.000000+0 0.000000+0 0 0 0 64125 1451 2 1.000000+0 0.000000+0 0 0 10 64125 1451 3 0.000000+0 0.000000+0 0 0 37 74125 1451 4 41-NB- 93 ANL,LLL EVAL-MAR90 A.+D.SMITH, GERADO, HOWERTON 4125 1451 5 ANL/NDM-88 AND -117 DIST-JUN90 900328 4125 1451 6 ----ENDF/B-VI MATERIAL 4125 4125 1451 7 -----INCIDENT NEUTRON DATA 4125 1451 8 ------ENDF-6 FORMAT 4125 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4125 1451 10 ACTIVATION II 4125 1451 11 ******************************************************************4125 1451 12 * * * * * * *4125 1451 13 FULLY DOCUMENTED IN ANL/NDM-88 4125 1451 14 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4125 1451 15 4125 1451 16 NB-93(N,N')NB-93M DOSIMETRY REACTION 4125 1451 17 4125 1451 18 EVALUATED BY D.L. SMITH AND L.P. GERALDO, ANL, MARCH 1990. 4125 1451 19 4125 1451 20 PRODUCTION OF THE ISOMER NB-93M BY THE (N,N') PROCESS IS 4125 1451 21 ROUTINELY EMPLOYED FOR NEUTRON DOSIMETRY APPLICATIONS. ISOMER 4125 1451 22 IS THE FIRST-EXCITED STATE OF THE ISOTOPE NB-93 (30.82 KEV 4125 1451 23 EXCITATION ENERGY). THE REACTION THRESHOLD ENERGY IS 31.15 KEV. 4125 1451 24 THE ISOTOPIC ABUNDANCE OF NB-93 IN NATURAL NIOBIUM IS 100 4125 1451 25 PERCENT. THE HALF LIFE OF NB-93M IS 16.1 YEARS. THE DECAY 4125 1451 26 IS ENTIRELY BY ISOMERIC TRANSITION WITH NEARLY 100 PERCENT 4125 1451 27 INTERNAL CONVERSION. ACTIVITY MEASUREMENT IS BY OBSERVATION OF 4125 1451 28 X-RAYS. X-RAY YIELDS: 16.6 KEV K-ALPHA (0. 09238 PER 4125 1451 29 DISINTEGRATION), 18.6 KEV K-BETA (0.01802 PER DISINTEGRATION). 4125 1451 30 4125 1451 31 EVALUATION IS BASED ON A LEAST-SQUARES ADJUSTMENT PROCEDURE. 4125 1451 32 INPUT INFORMATION INCLUDES RESULTS FROM NUCLEAR MODEL 4125 1451 33 CALCULATIONS AND RECENT DIFFERENTIAL ACTIVATION CROSS SECTION 4125 1451 34 DATA FROM THE LITERATURE. UNCERTAINTIES ARE DERIVED FROM 4125 1451 35 EXPERIMENTAL ERRORS AND THE CONSIDERATION OF SYSTEMATICS. 4125 1451 36 4125 1451 37 EVALUATION DOCUMENTATION: D.L. SMITH AND L.P. GERALDO, 4125 1451 38 REPORT ANL/NDM-117, ARGONNE NATIONAL LABORATORY (1990). 4125 1451 39 4125 1451 40 * * * * * * *4125 1451 41 1 451 48 04125 1451 42 2 151 200 04125 1451 43 3 16 15 04125 1451 44 3 102 171 04125 1451 45 3 107 10 04125 1451 46 33 16 15 04125 1451 47 33 102 9 04125 1451 48 4125 1 0 49 4125 0 0 50 4.109300+4 9.210510+1 0 0 1 04125 2151 51 4.109300+4 1.000000+0 0 0 1 04125 2151 52 1.000000-5 7.350000+3 1 1 0 04125 2151 53 4.500000+0 6.900000-1 0 0 2 04125 2151 54 9.210510+1 0.000000+0 0 0 888 1484125 2151 55 -1.054000+2 4.000000+0 5.441000-1 3.791000-1 1.650000-1 0.000000+04125 2151 56 1.058000+2 4.000000+0 1.675000-1 5.000000-4 1.670000-1 0.000000+04125 2151 57 1.192000+2 5.000000+0 1.286000-1 3.636000-3 1.250000-1 0.000000+04125 2151 58 1.930000+2 5.000000+0 1.678000-1 3.382000-2 1.340000-1 0.000000+04125 2151 59 3.355000+2 4.000000+0 1.748000-1 1.778000-2 1.570000-1 0.000000+04125 2151 60 3.650000+2 5.000000+0 1.505000-1 4.727000-4 1.500000-1 0.000000+04125 2151 61 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0.000000+0 0.000000+0 0 0 0 64225 1451 2 1.000000+0 0.000000+0 0 0 10 64225 1451 3 0.000000+0 0.000000+0 0 0 25 34225 1451 4 42-MO- 92 HEDL,RCN EVAL-FEB80 SCHENTER,SCHMITTROTH, ET AL 4225 1451 5 DIST-JAN90 900129 4225 1451 6 ----ENDF/B-VI MATERIAL 4225 4225 1451 7 -----INCIDENT NEUTRON DATA 4225 1451 8 ------ENDF-6 FORMAT 4225 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4225 1451 10 ACTIVATION II 4225 1451 11 ******************************************************************4225 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4225 1451 13 * * * * * * *4225 1451 14 HEDL EVAL- SCHENTER,JOHNSON,MANN,SCHMITTROTH 4225 1451 15 RCN EVAL- GRUPPELAAR 4225 1451 16 4225 1451 17 FILE CONTENTS 4225 1451 18 MF=2, MT=151 RESONANCE PARAMETERS FROM BNL-325, 3RD ED. (1) 4225 1451 19 4225 1451 20 MF=3,MT=102 CAPTURE EVALUATED THROUGH USE OF FERRET (4), A 4225 1451 21 GENERALIZED LEAST SQUARES COMPUTER CODE USING WHERE 4225 1451 22 AVAILABLE DIFFERENTIAL, INTEGRAL, AND THEORETICAL DATA. 4225 1451 23 4225 1451 24 REFERENCES 4225 1451 25 1. SF MUGHABGHAB AND DI GARBER,BNL-325,3RD ED, VOL 1 (1973) 4225 1451 26 4. F SCHMITTROTH, HEDL-TME 79-40 (1979) 4225 1451 27 5. F SCHMITTROTH, HEDL TME 73-79 (1973) 4225 1451 28 4225 1451 29 1 451 32 04225 1451 30 2 151 34 04225 1451 31 3 102 11 04225 1451 32 4225 1 0 33 4225 0 0 34 4.209200+4 9.121000+1 0 0 1 04225 2151 35 4.209200+4 1.000000+0 0 0 1 04225 2151 36 1.000000-5 1.939200+4 1 1 0 04225 2151 37 0.000000+0 6.344300-1 0 0 2 04225 2151 38 9.121000+1 0.000000+0 0 0 48 84225 2151 39 3.470000+2 5.000000-1 1.719000-1 7.900000-3 1.640000-1 0.000000+04225 2151 40 3.169000+3 5.000000-1 8.015000+0 7.800000+0 2.150000-1 0.000000+04225 2151 41 6.800000+3 5.000000-1 7.600000-1 5.800000-1 1.800000-1 0.000000+04225 2151 42 7.120000+3 5.000000-1 7.100000-1 5.200000-1 1.900000-1 0.000000+04225 2151 43 1.149400+4 5.000000-1 1.116200+1 1.100000+1 1.620000-1 0.000000+04225 2151 44 1.370000+4 5.000000-1 3.213200+1 3.200000+1 1.320000-1 0.000000+04225 2151 45 1.650000+4 5.000000-1 6.266600+1 6.250000+1 1.660000-1 0.000000+04225 2151 46 1.810000+4 5.000000-1 8.164000+0 8.000000+0 1.640000-1 0.000000+04225 2151 47 9.121000+1 0.000000+0 1 0 120 204225 2151 48 1.868800+3 1.500000+0 1.875000-1 2.350000-2 1.640000-1 0.000000+04225 2151 49 2.322600+3 1.500000+0 1.890000-1 2.500000-2 1.640000-1 0.000000+04225 2151 50 3.060000+3 5.000000-1 2.390000-1 7.499900-2 1.640000-1 0.000000+04225 2151 51 4.286000+3 1.500000+0 7.449900-1 5.249900-1 2.200000-1 0.000000+04225 2151 52 5.568000+3 1.500000+0 5.500000-1 2.500000-1 3.000000-1 0.000000+04225 2151 53 6.024000+3 1.500000+0 4.540000-1 2.900000-1 1.640000-1 0.000000+04225 2151 54 6.470000+3 5.000000-1 1.208000+0 1.100000+0 1.080000-1 0.000000+04225 2151 55 8.789000+3 1.500000+0 1.420000+0 1.250000+0 1.700000-1 0.000000+04225 2151 56 8.893000+3 5.000000-1 3.719900+0 3.499900+0 2.200000-1 0.000000+04225 2151 57 9.127000+3 5.000000-1 1.830000+0 1.600000+0 2.300000-1 0.000000+04225 2151 58 1.054600+4 1.500000+0 6.000000-1 2.300000-1 3.700000-1 0.000000+04225 2151 59 1.107900+4 1.500000+0 3.850000-1 1.800000-1 2.050000-1 0.000000+04225 2151 60 1.280000+4 1.500000+0 2.740000-1 1.100000-1 1.640000-1 0.000000+04225 2151 61 1.410000+4 5.000000-1 5.354900+0 5.199900+0 1.550000-1 0.000000+04225 2151 62 1.450000+4 1.500000+0 2.740000-1 1.100000-1 1.640000-1 0.000000+04225 2151 63 1.567000+4 5.000000-1 6.171900+0 5.999900+0 1.720000-1 0.000000+04225 2151 64 1.572000+4 1.500000+0 1.110000+0 9.499900-1 1.600000-1 0.000000+04225 2151 65 1.730000+4 1.500000+0 5.000000-1 1.250000-1 3.750000-1 0.000000+04225 2151 66 1.800000+4 1.500000+0 5.649900-1 3.999900-1 1.650000-1 0.000000+04225 2151 67 1.920000+4 1.500000+0 3.180000+0 3.000000+0 1.800000-1 0.000000+04225 2151 68 4225 2 0 69 4225 0 0 70 4.209200+4 9.121000+1 0 0 0 04225 3102 71 8.066700+6 8.066700+6 0 0 1 244225 3102 72 24 5 0 0 0 04225 3102 73 1.000000-5 1.358000+0 2.530000-2 2.700000-2 1.939200+4 3.080000-74225 3102 74 1.939200+4 7.380600-2 3.000000+4 6.342400-2 4.000000+4 5.739100-24225 3102 75 6.000000+4 4.761300-2 8.000000+4 4.002100-2 1.000000+5 3.544000-24225 3102 76 1.500000+5 3.296600-2 2.000000+5 3.164600-2 3.000000+5 3.441900-24225 3102 77 4.000000+5 3.676200-2 6.000000+5 4.065300-2 8.000000+5 3.465700-24225 3102 78 1.000000+6 2.489400-2 1.500000+6 2.849300-2 2.000000+6 2.725200-24225 3102 79 3.000000+6 1.443400-2 4.000000+6 9.843000-3 6.000000+6 4.275400-34225 3102 80 1.000000+7 2.119700-3 1.500000+7 2.926300-3 2.000000+7 2.926300-34225 3102 81 4225 3 0 82 4225 0 0 83 0 0 0 84 4.209800+4 9.706440+1 1 0 0 04243 1451 1 0.000000+0 1.000000+0 0 0 0 64243 1451 2 1.000000+0 0.000000+0 0 0 10 64243 1451 3 0.000000+0 0.000000+0 0 0 25 34243 1451 4 42-MO- 98 HEDL,RCN EVAL-FEB80 SCHENTER,SCHMITTROTH, ET AL 4243 1451 5 DIST-JAN90 900129 4243 1451 6 ----ENDF/B-VI MATERIAL 4243 4243 1451 7 -----INCIDENT NEUTRON DATA 4243 1451 8 ------ENDF-6 FORMAT 4243 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4243 1451 10 ACTIVATION II 4243 1451 11 ******************************************************************4243 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4243 1451 13 * * * * * * *4243 1451 14 HEDL EVAL- SCHENTER,JOHNSON,MANN,SCHMITTROTH 4243 1451 15 RCN EVAL- GRUPPELAAR 4243 1451 16 4243 1451 17 FILE CONTENTS 4243 1451 18 MF=2, MT=151 RESONANCE PARAMETERS FROM BNL-325, 3RD ED. (1) 4243 1451 19 4243 1451 20 MF=3,MT=102 CAPTURE EVALUATED THROUGH USE OF FERRET (4), A 4243 1451 21 GENERALIZED LEAST SQUARES COMPUTER CODE USING WHERE 4243 1451 22 AVAILABLE DIFFERENTIAL, INTEGRAL, AND THEORETICAL DATA. 4243 1451 23 4243 1451 24 REFERENCES 4243 1451 25 1. SF MUGHABGHAB AND DI GARBER,BNL-325,3RD ED, VOL 1 (1973) 4243 1451 26 4. F SCHMITTROTH, HEDL-TME 79-40 (1979) 4243 1451 27 5. F SCHMITTROTH, HEDL TME 73-79 (1973) 4243 1451 28 4243 1451 29 1 451 32 04243 1451 30 2 151 28 04243 1451 31 3 102 20 04243 1451 32 4243 1 0 33 4243 0 0 34 4.209800+4 9.706440+1 0 0 1 04243 2151 35 4.209800+4 1.000000+0 0 0 1 04243 2151 36 1.000000-5 4.982400+3 1 1 0 04243 2151 37 0.000000+0 5.560800-1 0 0 2 04243 2151 38 9.706440+1 0.000000+0 0 0 30 54243 2151 39 4.674000+2 5.000000-1 7.100000-1 6.000000-1 1.100000-1 0.000000+04243 2151 40 1.526500+3 5.000000-1 8.750000-1 8.000000-1 7.500000-2 0.000000+04243 2151 41 2.549000+3 5.000000-1 1.370000+0 1.300000+0 7.000000-2 0.000000+04243 2151 42 3.293000+3 5.000000-1 4.880000+0 4.800000+0 8.000000-2 0.000000+04243 2151 43 4.482000+3 5.000000-1 4.020000-1 3.090000-1 9.300000-2 0.000000+04243 2151 44 9.706440+1 0.000000+0 1 0 102 174243 2151 45 1.210000+1 1.500000+0 1.250300-1 3.000000-5 1.250000-1 0.000000+04243 2151 46 4.018000+2 1.500000+0 1.416000-1 1.600000-3 1.400000-1 0.000000+04243 2151 47 4.293000+2 5.000000-1 2.300000-1 7.000000-2 1.600000-1 0.000000+04243 2151 48 6.125000+2 5.000000-1 2.100000-1 6.500000-2 1.450000-1 0.000000+04243 2151 49 8.181000+2 1.500000+0 1.700000-1 8.000000-2 9.000000-2 0.000000+04243 2151 50 1.122500+3 1.500000+0 1.502500-1 1.025000-2 1.400000-1 0.000000+04243 2151 51 1.922000+3 1.000000+0 1.555300-1 1.553300-2 1.400000-1 0.000000+04243 2151 52 2.021200+3 1.000000+0 1.416700-1 1.666700-3 1.400000-1 0.000000+04243 2151 53 2.176600+3 5.000000-1 2.900000-1 1.450000-1 1.450000-1 0.000000+04243 2151 54 2.461700+3 5.000000-1 2.250000-1 1.200000-1 1.050000-1 0.000000+04243 2151 55 2.615000+3 1.500000+0 1.550000-1 1.500000-2 1.400000-1 0.000000+04243 2151 56 2.947000+3 5.000000-1 1.640000-1 2.400000-2 1.400000-1 0.000000+04243 2151 57 3.264000+3 5.000000-1 2.300000-1 9.000000-2 1.400000-1 0.000000+04243 2151 58 3.797000+3 1.500000+0 2.475000-1 1.575000-1 9.000000-2 0.000000+04243 2151 59 4.013000+3 1.500000+0 1.900000-1 1.100000-1 8.000000-2 0.000000+04243 2151 60 4.574000+3 1.500000+0 3.800000-1 2.700000-1 1.100000-1 0.000000+04243 2151 61 4.843000+3 1.500000+0 6.115000-1 5.115000-1 1.000000-1 0.000000+04243 2151 62 4243 2 0 63 4243 0 0 64 4.209800+4 9.706440+1 0 0 0 04243 3102 65 5.928000+6 5.928000+6 0 0 1 504243 3102 66 50 5 0 0 0 04243 3102 67 1.000000-5 3.122400+0 2.530000-2 6.207700-2 4.982400+3 1.398900-44243 3102 68 4.982400+3 3.610800-1 5.000000+3 3.603000-1 7.000000+3 2.927800-14243 3102 69 1.000000+4 2.349700-1 2.000000+4 1.524600-1 2.400000+4 1.370300-14243 3102 70 3.000000+4 1.202600-1 5.000000+4 8.576600-2 7.000000+4 6.509900-24243 3102 71 1.000000+5 4.845600-2 1.300000+5 4.249800-2 1.600000+5 3.816300-24243 3102 72 2.000000+5 3.369300-2 2.400000+5 3.320700-2 3.000000+5 3.262200-24243 3102 73 3.700000+5 3.422500-2 4.500000+5 3.601100-2 5.500000+5 3.809600-24243 3102 74 7.000000+5 3.392400-2 7.425700+5 3.214900-2 7.951100+5 3.020800-24243 3102 75 8.318300+5 2.778800-2 8.374200+5 2.741900-2 8.500000+5 2.661500-24243 3102 76 8.839600+5 2.461200-2 1.000000+6 1.923900-2 1.300000+6 1.824500-24243 3102 77 1.444700+6 1.786000-2 1.525600+6 1.746900-2 1.600000+6 1.676800-24243 3102 78 1.778100+6 1.531400-2 1.828600+6 1.494900-2 1.899400+6 1.446900-24243 3102 79 1.980200+6 1.396000-2 2.000000+6 1.384100-2 2.010500+6 1.379300-24243 3102 80 2.040800+6 1.365700-2 2.050000+6 1.361600-2 2.061000+6 1.356800-24243 3102 81 2.400000+6 1.226300-2 3.000000+6 1.057500-2 5.000000+6 4.445900-34243 3102 82 7.000000+6 2.299900-3 1.000000+7 1.135200-3 1.200000+7 1.280100-34243 3102 83 1.500000+7 1.482800-3 2.000000+7 2.149100-3 0.000000+0 0.000000+04243 3102 84 4243 3 0 85 4243 0 0 86 0 0 0 87 4.210000+4 9.904920+1 1 0 0 04249 1451 1 0.000000+0 1.000000+0 0 0 0 64249 1451 2 1.000000+0 0.000000+0 0 0 10 64249 1451 3 0.000000+0 0.000000+0 0 0 25 34249 1451 4 42-MO-100 HEDL,RCN EVAL-FEB80 SCHENTER,SCHMITTROTH, ET AL 4249 1451 5 DIST-JAN90 900129 4249 1451 6 ----ENDF/B-VI MATERIAL 4249 4249 1451 7 -----INCIDENT NEUTRON DATA 4249 1451 8 ------ENDF-6 FORMAT 4249 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4249 1451 10 ACTIVATION II 4249 1451 11 ******************************************************************4249 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4249 1451 13 * * * * * * *4249 1451 14 HEDL EVAL- SCHENTER,JOHNSON,MANN,SCHMITTROTH 4249 1451 15 RCN EVAL- GRUPPELAAR 4249 1451 16 4249 1451 17 FILE CONTENTS 4249 1451 18 MF=2, MT=151 RESONANCE PARAMETERS FROM BNL-325, 3RD ED. (1) 4249 1451 19 4249 1451 20 MF=3,MT=102 CAPTURE EVALUATED THROUGH USE OF FERRET (4), A 4249 1451 21 GENERALIZED LEAST SQUARES COMPUTER CODE USING WHERE 4249 1451 22 AVAILABLE DIFFERENTIAL, INTEGRAL, AND THEORETICAL DATA. 4249 1451 23 4249 1451 24 REFERENCES 4249 1451 25 1. SF MUGHABGHAB AND DI GARBER,BNL-325,3RD ED, VOL 1 (1973) 4249 1451 26 4. F SCHMITTROTH, HEDL-TME 79-40 (1979) 4249 1451 27 5. F SCHMITTROTH, HEDL TME 73-79 (1973) 4249 1451 28 4249 1451 29 1 451 32 04249 1451 30 2 151 23 04249 1451 31 3 102 18 04249 1451 32 4249 1 0 33 4249 0 0 34 4.210000+4 9.904920+1 0 0 1 04249 2151 35 4.210000+4 1.000000+0 0 0 1 04249 2151 36 1.000000-5 3.676100+3 1 1 0 04249 2151 37 0.000000+0 5.598500-1 0 0 2 04249 2151 38 9.904920+1 0.000000+0 0 0 18 34249 2151 39 3.638000+2 5.000000-1 8.680000-1 8.000000-1 6.800000-2 0.000000+04249 2151 40 1.937200+3 5.000000-1 1.305000+0 1.250000+0 5.500000-2 0.000000+04249 2151 41 3.006000+3 5.000000-1 3.051000+0 3.000000+0 5.100000-2 0.000000+04249 2151 42 9.904920+1 0.000000+0 1 0 84 144249 2151 43 9.740000+1 1.000000+0 1.502500-1 2.533300-4 1.500000-1 0.000000+04249 2151 44 5.071000+2 1.000000+0 1.528700-1 2.866700-3 1.500000-1 0.000000+04249 2151 45 5.358000+2 1.000000+0 1.057300-1 2.733300-3 1.030000-1 0.000000+04249 2151 46 7.856800+2 1.000000+0 1.537300-1 3.733300-3 1.500000-1 0.000000+04249 2151 47 1.069100+3 5.000000-1 4.530000-1 3.500000-1 1.030000-1 0.000000+04249 2151 48 1.260700+3 5.000000-1 3.900000-1 3.000000-1 9.000000-2 0.000000+04249 2151 49 1.697000+3 5.000000-1 1.118000+0 1.000000+0 1.180000-1 0.000000+04249 2151 50 1.764800+3 1.000000+0 1.633300-1 1.333300-2 1.500000-1 0.000000+04249 2151 51 2.061700+3 1.000000+0 1.542000-1 4.200000-3 1.500000-1 0.000000+04249 2151 52 2.420000+3 1.000000+0 3.940000-1 2.760000-1 1.180000-1 0.000000+04249 2151 53 2.630500+3 1.000000+0 2.180000-1 1.420000-1 7.600000-2 0.000000+04249 2151 54 2.950000+3 1.000000+0 1.880000-1 3.800000-2 1.500000-1 0.000000+04249 2151 55 3.065000+3 1.000000+0 1.616700-1 9.666700-2 6.500000-2 0.000000+04249 2151 56 3.261500+3 1.000000+0 3.036700-1 2.206700-1 8.300000-2 0.000000+04249 2151 57 4249 2 0 58 4249 0 0 59 4.210000+4 9.904920+1 0 0 0 04249 3102 60 5.391000+6 5.391000+6 0 0 1 444249 3102 61 44 5 0 0 0 04249 3102 62 1.000000-5 5.326400+0 2.530000-2 1.058900-1 3.676100+3 2.778000-44249 3102 63 3.676100+3 2.909600-1 5.000000+3 2.569000-1 7.000000+3 2.242000-14249 3102 64 1.000000+4 1.909300-1 2.000000+4 1.244700-1 2.400000+4 1.100700-14249 3102 65 3.000000+4 9.470000-2 5.000000+4 6.292200-2 7.000000+4 4.743400-24249 3102 66 1.000000+5 3.816300-2 1.300000+5 3.292600-2 1.600000+5 3.018300-24249 3102 67 2.000000+5 2.951300-2 2.400000+5 3.008500-2 3.000000+5 3.080100-24249 3102 68 3.700000+5 3.263100-2 4.500000+5 3.062500-2 5.414100+5 2.680500-24249 3102 69 5.500000+5 2.650300-2 6.105500+5 2.412000-2 6.322400+5 2.264500-24249 3102 70 6.526200+5 2.138200-2 7.000000+5 1.883700-2 7.010100+5 1.878800-24249 3102 71 8.500000+5 1.456300-2 1.000000+6 1.395300-2 1.070700+6 1.327100-24249 3102 72 1.151500+6 1.258100-2 1.300000+6 1.150900-2 1.470000+6 1.051700-24249 3102 73 1.474700+6 1.049200-2 1.600000+6 1.035400-2 2.000000+6 1.032500-24249 3102 74 2.400000+6 8.594100-3 3.000000+6 6.865400-3 5.000000+6 2.904500-34249 3102 75 7.000000+6 2.002600-3 1.000000+7 1.192600-3 1.200000+7 1.293300-34249 3102 76 1.500000+7 1.428300-3 2.000000+7 2.186800-3 0.000000+0 0.000000+04249 3102 77 4249 3 0 78 4249 0 0 79 0 0 0 80 4.710700+4 1.059870+2 1 0 0 04725 1451 1 0.000000+0 0.000000+0 0 0 0 64725 1451 2 1.000000+0 0.000000+0 0 0 10 64725 1451 3 0.000000+0 0.000000+0 0 0 127 44725 1451 4 47-AG-107 BNL,HEDL EVAL-JUN83 A.PRINCE,R.E.SCHENTER 4725 1451 5 DIST-JAN90 900129 4725 1451 6 ----ENDF/B-VI MATERIAL 4725 4725 1451 7 -----INCIDENT NEUTRON DATA 4725 1451 8 ------ENDF-6 FORMAT 4725 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4725 1451 10 ACTIVATION II 4725 1451 11 ******************************************************************4725 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4725 1451 13 * * * * * * *4725 1451 14 EVALUATION OF A. PRINCE 7/80 WHICH SUPERSEDES ENDF/V MAT 1371 4725 1451 15 BY BNL/HEDL (SCHENTER,BHAT,PRINCE AND JOHNSON). CHANGES IN 4725 1451 16 THE CAPTURE AND ELASTIC KEEPING THE TOTAL CROSS SECTION 4725 1451 17 CONSTANT WERE ALSO MADE BY R. SCHENTER. THESE CHANGES REFLECT 4725 1451 18 THE USE OF RESULTS OF RECENT MEASUREMENTS BY MACKLIN AND 4725 1451 19 POENITZ ON ISOTOPIC AND ELEMENTAL CAPTURE (REF.22 AND REF. 23). 4725 1451 20 ***** ***** *****4725 1451 21 FILE 2 RESONANCE PARAMETERS 4725 1451 22 4725 1451 23 RESONANCE PARAMETERS BASED ON NEW EXPTL.DATA (REF.1) 4725 1451 24 L=0 NUMBER OF RESONANCES IS 74 4725 1451 25 AVERAGE TOTAL WIDTH = 2.3298-01 EV. 4725 1451 26 AVERAGE REDUCED NEUTRON WIDTH = 2.82367-03 EV. 4725 1451 27 AVERAGE GAMMA WIDTH = 1.39069-01 EV. 4725 1451 28 AVERAGE LEVEL SPACING=3.65767+01 EV. 4725 1451 29 S-WAVE STRENGTH FUNCTION = 3.7851-05 4725 1451 30 0.025 EV CAPTURE CROSS SECTION (CALC)= 3.7616+01BARNS 4725 1451 31 RESONANCE ABSORPTION INTEGRAL (0.5 EV CUT-OFF)= 1.0487+02 B 4725 1451 32 EFFECTIVE SCATTERING RADIUS = 6.60 FM. 4725 1451 33 ***** ***** *****4725 1451 34 FILE 3 SMOOTH CROSS SECTIONS 4725 1451 35 4725 1451 36 ALL DATA RE-EVALUATED BASED ON LATEST EXPERIMENTAL DATA 4725 1451 37 AND NUCLEAR MODEL CALCS. 4725 1451 38 MT=1 TOTAL CROSS SECTION IN ENERGY RANGE 0.25 MEV TO 4.5 MEV 4725 1451 39 BASED ON EXPERIMENTAL DATA OF REF 2. 4725 1451 40 FROM 4.5 TO 20.0 MEV OPTICAL MODEL CALCS. COMBINED WITH 4725 1451 41 EXPTL DATA FROM BNL-325 4725 1451 42 MT=2 ELASTIC CROSS SECTIONS DERIVED FROM ANGLE INTEGRATED 4725 1451 43 EXPTL DATA OF REF.2 AND BNL 325 SUPPLEMENTED WITH OPTICAL4725 1451 44 MODEL CALCS. AT HIGHER ENERGIES (5.0 TO 20.0 MEV) THE 4725 1451 45 ELASTIC CROSS SECTION WAS CHOSEN TO BE CONSISTENT WITH 4725 1451 46 TOTAL MINUS NON-ELASTIC EXPTL DATA (BNL-325) 4725 1451 47 MT=3 NON ELASTIC CROSS SECTIONS DETERMINED FROM EXPTL DATA 4725 1451 48 OF REF.2 IN REGION 0.25 TO 4.5 MEV. FROM 5.0 TO 20.0 MEV 4725 1451 49 OPTICAL MODEL CALCS. COMBINED WITH BNL-325 EXPTL DATA. 4725 1451 50 MT=4 TOTAL INELASTIC CROSS SECTION BASED ON EXPTL DATA OF 4725 1451 51 REF.2 AND REF.3 COMBINED WITH HAUSER-FESHBACH CALCS. 4725 1451 52 MT=16 N-2N CROSS SECTIONS WERE DETERMINED FROM RECENT EXPTL 4725 1451 53 DATA OF REFS.4 TO 8 AND BNL 325. IN REGIONS LACKING 4725 1451 54 EXPTL DATA, MODEL CALCS WERE PERFORMED. 4725 1451 55 MT=17 N-3N CROSS SECTIONS WERE BASED PRIMARILY ON MODEL CALCS 4725 1451 56 NORMALIZED TO EXPTL DATA OF REFS.7 AND 9. 4725 1451 57 MT=22,28,104,105,106 DETERMINED FROM STATISTICAL MODEL CALCS. 4725 1451 58 MT=51 TO 63 DISCRETE INELASTIC CROSS SECTIONS, CALCULATED USING 4725 1451 59 HAUSER-FESHBACH THEORY WITH WIDTH FLUCTUATION 104725 1451 60 CORRECTIONS DERIVED BY REFS. 10 AND 11, WERE COMBINED 4725 1451 61 WITH EXPTL. DATA OF REFS.2 ,3 AND 12. 4725 1451 62 LEVEL EXCITATION ENERGIES UP TO 1.65 TAKEN FROM REFS.134725 1451 63 14 AND 15. 4725 1451 64 MT=91 CONTINUUM INELASTIC CROSS SECTION WITH 1.143 MEV CUTOFF 4725 1451 65 TAKEN AS DIFFERENCE BETWEEN TOTAL INELASTIC AND DISCRETE. 4725 1451 66 LEVEL EXCITATIONS 4725 1451 67 MT=102 RADIATIVE CAPTURE CROSS SECTION USING RESULTS MAINLY 4725 1451 68 FROM REF.22. AND 23. 4725 1451 69 MT=103 N-PROTON CROSS SECTION-HAUSER-FESHBACH AND STATISTICAL 4725 1451 70 MODEL CALCS. WERE NORMALIZED TO 14.0 MEV DATA OF REF.18 4725 1451 71 MT=107 N-ALPHA CROSS SECTION- CALCULATED IN SAME MANNER AS MT1034725 1451 72 AND COMBINED WITH EXPTL. DATA OF REFS.19 AND 20. 4725 1451 73 TOTAL GAS PRODUCTION MT=203,204,206,207 DERIVED FROM 4725 1451 74 RESULTS OF H,D,T HE-3 AND HE-4 CONTAINED IN MT=103 TO 1074725 1451 75 AND MT=22,28 4725 1451 76 ***** ***** *****4725 1451 77 FILE 4- ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS 4725 1451 78 MT=2 SAME AS BNL/HEDL ENDF/V 1979 EVALUATION REF.17 4725 1451 79 MT=16,17,22,28,51 TO 91 ANGULAR DISTRIBUTIONS ASSUMED TO BE 4725 1451 80 ISOTROPIC 4725 1451 81 FILE 5- ENERGY DISTRIBUTION OF SECONDARY NEUTRONS 4725 1451 82 MT=16,17,22,28 AND 91 ENERGY DISTRIBUTIONS PRESENTED AS 4725 1451 83 HISTOGRAM BASED ON CALCS. USING NUCLEAR TEMPERATURES 4725 1451 84 DETERMINED FROM REF.21 4725 1451 85 ***** ***** *****4725 1451 86 SUMMARY 4725 1451 87 FILES 2 AND 3 ARE COMPLETELY NEW EVALUATIONS RESULTING 4725 1451 88 FROM IMPROVED NUCLEAR MODEL CALCS. AND THE MOST RECENT 4725 1451 89 EXPERIMENTAL DATA. 4725 1451 90 FILE 4 REMAINS THE SAME AS THE EARLIER VERSION EXCEPT FOR 4725 1451 91 5 ADDITIONAL INELASTIC LEVEL EXCITATIONS AND THE INCLUSION 4725 1451 92 OF MT= 17,22 AND 28 4725 1451 93 FILE 5 ALSO HAS BEEN EXPANDED TO INCLUDE MT=17,22 AND 28 4725 1451 94 ***** ***** *****4725 1451 95 CODES USED 4725 1451 96 1. CERBERO 2 IMPROVED VERSION OF THE CERBERO COMPUTER CODE 4725 1451 97 FOR CALCULATION OF NUCLEAR REACTION CROSS SECTION 4725 1451 98 F.FABBRI ET AL RT/FI(77)6 CNEN 1977 4725 1451 99 2. ERINNI AN OPTICAL MODEL FORTRAN IV CODE FOR THE CALCULATION4725 1451 100 OF MULTIPLE CASCADING PARTICLE EMISSIONS F.FABBRI AND 4725 1451 101 G.REFFO RT/FI(77)4 CNEN 1977 4725 1451 102 3. SCAT4U MODIFIED VERSION OF SCAT2 AN OPTICAL MODEL PROGRAM 4725 1451 103 O.BERSILLON- BRUYERES-LE-CHATEL (PRIVATE COMMUNICATION) 4725 1451 104 4. THRES2 MODIFIED VERSION OF THRESH- S.PEARLSTEIN 1975 4725 1451 105 (PRI. COMM.) 4725 1451 106 ***** ***** *****4725 1451 107 REFERENCES 4725 1451 108 1. S.MUGHAGHAB (PRIVATE COMM.)1980 4725 1451 109 2. A.SMITH,ET AL REPORT ANL/NOM-46(JAN.1979) 4725 1451 110 3. E.BARNARD,ET AL, HARWELL CONF.(1978) PROL.-78-HA 4725 1451 111 4. E.RONDAIAH, J.PHYS.A MATH-NUC.GEN.7(12)1457(1974) 4725 1451 112 5. W.MANNHART AND H.VONACH, Z.PHYS.A272,279(1975) 4725 1451 113 6. W.AUGUSTYNIACK,ET AL, NUCL.PHYS.A247,231(1975) 4725 1451 114 7. B.P.BAYHURST,ET AL, PHYS.REV.C12,451(1975) 4725 1451 115 8. S.C.MISRA AND U.C.GUPTA,J.PHYS.G NUCL.PHYS.5,855(1979) 4725 1451 116 9. H.LISKIEN,NUCL.PHYS.A118,379(1968) 4725 1451 117 10. J.W.TEPEL,ET AL,PHYS.LETT.49B,1(1974) 4725 1451 118 11. H.M.HOFFMAN,ET AL,ANN.PHYS.90,403(1975) 4725 1451 119 12. W.G.VONACH AND A.B.SMITH,NUCL.PHYS.78,389(1966) 4725 1451 120 13. C.M.LEDERER,ET AL TABEL OF ISOTOPES(7TH-ED.) WILEY (1978) 4725 1451 121 14. H-W.SCHUH,ET AL,ZEIT F.PHYSIK A293,301(1979) 4725 1451 122 15. Z.MATUMOTO,ET AL,JAERI-M7734(1978) 4725 1451 123 16. Y.D.HARRER,ET AL RPT.TREE 1259(CFRMF INFU)1978 4725 1451 124 17. R.E.SCHENTER,ET AL ENDF/V SUMMARY DOCUMENTATION 47-107-1 1979 4725 1451 125 18. R.PRASAD AND D.C.SARKER, NUOVO CIM.3A,467(1961) 4725 1451 126 19. A.RUBBIND AND D.ZUBKE,NUCL PHYS.85,606(1966) 4725 1451 127 20. M.BORMANN,ET AL,NUCL.PHYS.A186,65(1972) 4725 1451 128 21. A.G.GILBERT AND A.G.W.CAMERON,CAN.J.PHYS.43,1446(1965) 4725 1451 129 22. R.L.MACKLIN,NUCL.SCI.AND.ENG.82,400(1982) 4725 1451 130 23. W.P.POENITZ,SPEC.MEET.ON.FAST.CAPTURE,ANL-83-4,239(1982) 4725 1451 131 1 451 135 04725 1451 132 2 151 79 04725 1451 133 3 102 20 04725 1451 134 3 103 19 04725 1451 135 4725 1 0 136 4725 0 0 137 4.710700+4 1.059870+2 0 0 1 04725 2151 138 4.710700+4 1.000000+0 0 0 1 04725 2151 139 1.000000-5 2.682760+3 1 2 0 04725 2151 140 5.000000-1 6.600000-1 0 0 1 04725 2151 141 1.059870+2 0.000000+0 0 0 444 744725 2151 142 -1.110000+1 1.000000+0 1.737800-1 3.278000-2 1.410000-1 0.000000+04725 2151 143 1.630000+1 0.000000+0 1.576000-1 1.160000-2 1.460000-1 0.000000+04725 2151 144 4.150000+1 1.000000+0 1.423700-1 5.366700-3 1.370000-1 0.000000+04725 2151 145 4.480000+1 0.000000+0 1.504800-1 3.480000-3 1.470000-1 0.000000+04725 2151 146 5.140000+1 1.000000+0 1.559300-1 2.293300-2 1.330000-1 0.000000+04725 2151 147 8.260000+1 1.000000+0 1.390900-1 1.866700-5 1.390700-1 0.000000+04725 2151 148 1.281000+2 1.000000+0 1.391400-1 7.333300-5 1.390700-1 0.000000+04725 2151 149 1.442000+2 0.000000+0 1.500000-1 2.000000-2 1.300000-1 0.000000+04725 2151 150 1.550000+2 1.000000+0 1.391100-1 4.000000-5 1.390700-1 0.000000+04725 2151 151 1.624000+2 1.000000+0 1.392300-1 1.666700-4 1.390700-1 0.000000+04725 2151 152 1.671000+2 1.000000+0 1.392200-1 1.533300-4 1.390700-1 0.000000+04725 2151 153 1.735000+2 1.000000+0 1.859300-1 4.393300-2 1.420000-1 0.000000+04725 2151 154 2.025000+2 1.000000+0 1.642700-1 1.026700-2 1.540000-1 0.000000+04725 2151 155 2.182000+2 0.000000+0 1.394300-1 3.600000-4 1.390700-1 0.000000+04725 2151 156 2.514000+2 1.000000+0 1.496000-1 1.053300-2 1.390700-1 0.000000+04725 2151 157 2.594000+2 1.000000+0 1.111800-1 1.800000-4 1.110000-1 0.000000+04725 2151 158 2.647000+2 1.000000+0 1.530700-1 3.066700-3 1.500000-1 0.000000+04725 2151 159 2.705000+2 0.000000+0 1.392300-1 1.640000-4 1.390700-1 0.000000+04725 2151 160 3.110000+2 1.000000+0 2.513300-1 1.173300-1 1.340000-1 0.000000+04725 2151 161 3.290000+2 1.000000+0 1.392900-1 2.200000-4 1.390700-1 0.000000+04725 2151 162 3.473000+2 1.000000+0 1.394400-1 3.733300-4 1.390700-1 0.000000+04725 2151 163 3.562000+2 0.000000+0 1.395900-1 5.200000-4 1.390700-1 0.000000+04725 2151 164 3.618000+2 1.000000+0 1.978700-1 2.286700-2 1.750000-1 0.000000+04725 2151 165 3.743000+2 1.000000+0 1.393300-1 2.600000-4 1.390700-1 0.000000+04725 2151 166 3.821000+2 1.000000+0 1.393300-1 2.600000-4 1.390700-1 0.000000+04725 2151 167 4.020000+2 0.000000+0 1.400300-1 9.600000-4 1.390700-1 0.000000+04725 2151 168 4.100000+2 1.000000+0 1.392800-1 2.133300-4 1.390700-1 0.000000+04725 2151 169 4.447000+2 1.000000+0 1.615300-1 2.246700-2 1.390700-1 0.000000+04725 2151 170 4.614000+2 1.000000+0 1.545300-1 1.546700-2 1.390700-1 0.000000+04725 2151 171 4.667000+2 1.000000+0 2.186700-1 8.066700-2 1.380000-1 0.000000+04725 2151 172 4.723000+2 0.000000+0 1.950700-1 5.600000-2 1.390700-1 0.000000+04725 2151 173 4.762000+2 1.000000+0 1.414000-1 2.333300-3 1.390700-1 0.000000+04725 2151 174 4.797000+2 1.000000+0 1.392000-1 1.333300-4 1.390700-1 0.000000+04725 2151 175 5.124000+2 0.000000+0 1.734700-1 3.440000-2 1.390700-1 0.000000+04725 2151 176 5.250000+2 1.000000+0 1.392700-1 2.000000-4 1.390700-1 0.000000+04725 2151 177 5.322000+2 1.000000+0 1.391700-1 1.066700-4 1.390700-1 0.000000+04725 2151 178 5.545000+2 0.000000+0 5.630700-1 4.240000-1 1.390700-1 0.000000+04725 2151 179 5.768000+2 1.000000+0 1.677300-1 2.866700-2 1.390700-1 0.000000+04725 2151 180 5.876000+2 0.000000+0 3.160000-1 1.980000-1 1.180000-1 0.000000+04725 2151 181 6.051000+2 1.000000+0 1.412000-1 2.133300-3 1.390700-1 0.000000+04725 2151 182 6.256000+2 1.000000+0 1.557300-1 1.666700-2 1.390700-1 0.000000+04725 2151 183 6.534000+2 1.000000+0 1.524000-1 1.333300-2 1.390700-1 0.000000+04725 2151 184 6.747000+2 1.000000+0 1.733300-1 4.333300-2 1.300000-1 0.000000+04725 2151 185 6.959000+2 1.000000+0 1.548700-1 1.580000-2 1.390700-1 0.000000+04725 2151 186 7.035000+2 1.000000+0 1.436700-1 4.600000-3 1.390700-1 0.000000+04725 2151 187 7.215000+2 0.000000+0 1.412700-1 2.200000-3 1.390700-1 0.000000+04725 2151 188 7.347000+2 1.000000+0 1.398000-1 7.333300-4 1.390700-1 0.000000+04725 2151 189 7.530000+2 1.000000+0 1.830700-1 4.400000-2 1.390700-1 0.000000+04725 2151 190 8.130000+2 1.000000+0 1.436000-1 4.533300-3 1.390700-1 0.000000+04725 2151 191 8.489000+2 0.000000+0 1.564700-1 1.740000-2 1.390700-1 0.000000+04725 2151 192 8.823000+2 1.000000+0 2.184000-1 7.933300-2 1.390700-1 0.000000+04725 2151 193 8.867000+2 1.000000+0 1.470700-1 8.000000-3 1.390700-1 0.000000+04725 2151 194 9.149000+2 1.000000+0 1.439300-1 4.866700-3 1.390700-1 0.000000+04725 2151 195 9.354000+2 0.000000+0 7.870700-1 6.480000-1 1.390700-1 0.000000+04725 2151 196 9.460000+2 1.000000+0 1.804000-1 4.133300-2 1.390700-1 0.000000+04725 2151 197 9.900000+2 1.000000+0 2.190700-1 8.000000-2 1.390700-1 0.000000+04725 2151 198 1.048000+3 1.000000+0 2.037300-1 6.466700-2 1.390700-1 0.000000+04725 2151 199 1.135000+3 0.000000+0 2.870700-1 1.480000-1 1.390700-1 0.000000+04725 2151 200 1.148000+3 1.000000+0 1.664000-1 2.733300-2 1.390700-1 0.000000+04725 2151 201 1.179000+3 1.000000+0 2.697300-1 1.306700-1 1.390700-1 0.000000+04725 2151 202 1.415000+3 1.000000+0 2.644000-1 1.253300-1 1.390700-1 0.000000+04725 2151 203 1.592000+3 0.000000+0 2.990700-1 1.600000-1 1.390700-1 0.000000+04725 2151 204 1.627000+3 1.000000+0 2.224000-1 8.333300-2 1.390700-1 0.000000+04725 2151 205 1.643000+3 1.000000+0 2.417300-1 1.026700-1 1.390700-1 0.000000+04725 2151 206 1.719000+3 1.000000+0 2.304000-1 9.133300-2 1.390700-1 0.000000+04725 2151 207 1.836000+3 0.000000+0 3.110700-1 1.720000-1 1.390700-1 0.000000+04725 2151 208 1.905000+3 1.000000+0 3.424000-1 2.033300-1 1.390700-1 0.000000+04725 2151 209 1.938000+3 1.000000+0 5.790700-1 4.400000-1 1.390700-1 0.000000+04725 2151 210 1.988000+3 1.000000+0 2.344000-1 9.533300-2 1.390700-1 0.000000+04725 2151 211 2.046000+3 0.000000+0 8.790700-1 7.400000-1 1.390700-1 0.000000+04725 2151 212 2.176000+3 1.000000+0 3.790700-1 2.400000-1 1.390700-1 0.000000+04725 2151 213 2.312000+3 1.000000+0 2.477300-1 1.086700-1 1.390700-1 0.000000+04725 2151 214 2.391000+3 1.000000+0 6.590700-1 5.200000-1 1.390700-1 0.000000+04725 2151 215 2.659000+3 0.000000+0 1.439100+0 1.300000+0 1.390700-1 0.000000+04725 2151 216 4725 2 0 217 4725 0 0 218 4.710700+4 1.059870+2 0 0 0 04725 3102 219 7.276000+6 7.276000+6 0 0 1 494725 3102 220 49 2 0 0 0 04725 3102 221 1.000000-5 0.000000+0 2.530000-2 0.000000+0 2.682760+3 0.000000+04725 3102 222 2.682760+3 2.140000+0 2.682770+3 2.140100+0 3.000000+3 2.030000+04725 3102 223 3.500000+3 1.920000+0 4.000000+3 1.800000+0 5.000000+3 1.650000+04725 3102 224 1.000000+4 1.220000+0 2.000000+4 9.800000-1 5.000000+4 6.400000-14725 3102 225 7.000000+4 5.400000-1 1.000000+5 4.800000-1 2.000000+5 3.200000-14725 3102 226 3.000000+5 2.470000-1 4.000000+5 2.000000-1 5.000000+5 1.600000-14725 3102 227 6.000000+5 1.420000-1 7.000000+5 1.350000-1 8.000000+5 1.280000-14725 3102 228 9.000000+5 1.200000-1 1.000000+6 1.170000-1 1.100000+6 1.110000-14725 3102 229 1.200000+6 1.070000-1 1.300000+6 1.030000-1 1.400000+6 1.010000-14725 3102 230 1.500000+6 1.000000-1 1.600000+6 9.800000-2 1.700000+6 9.600000-24725 3102 231 1.800000+6 9.400000-2 1.900000+6 9.275000-2 2.000000+6 9.259000-24725 3102 232 2.100000+6 9.183000-2 2.200000+6 9.064000-2 2.500000+6 8.558000-24725 3102 233 3.000000+6 7.427000-2 3.500000+6 6.166000-2 4.000000+6 4.940000-24725 3102 234 4.500000+6 3.825000-2 5.000000+6 2.857000-2 6.000000+6 1.428000-24725 3102 235 8.000000+6 7.560000-3 1.000000+7 4.920000-3 1.200000+7 3.320000-34725 3102 236 1.400000+7 2.450000-3 1.600000+7 1.960000-3 1.800000+7 1.620000-34725 3102 237 2.000000+7 1.350000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+04725 3102 238 4725 3 0 239 4.710700+4 1.059870+2 0 0 0 04725 3103 240 7.475000+5 7.475000+5 0 0 1 474725 3103 241 47 2 0 0 0 04725 3103 242 1.000000-5 0.000000+0 2.530000-2 0.000000+0 1.000000+4 0.000000+04725 3103 243 1.000000+4 1.780000-6 1.000000+5 6.600000-6 2.000000+5 1.050000-54725 3103 244 3.000000+5 1.400000-5 5.000000+5 1.985000-5 1.000000+6 3.974000-54725 3103 245 1.500000+6 5.578000-5 2.000000+6 7.778000-5 2.500000+6 1.085000-44725 3103 246 3.000000+6 1.511000-4 3.500000+6 2.103000-4 4.000000+6 2.927000-44725 3103 247 4.500000+6 4.039000-4 5.000000+6 5.598000-4 5.500000+6 7.821000-44725 3103 248 6.000000+6 1.100000-3 6.500000+6 1.500000-3 7.000000+6 1.767000-34725 3103 249 7.500000+6 2.415000-3 8.000000+6 3.248000-3 8.500000+6 4.295000-34725 3103 250 9.000000+6 5.513000-3 9.500000+6 6.945000-3 1.000000+7 8.462000-34725 3103 251 1.050000+7 1.002000-2 1.100000+7 1.152000-2 1.150000+7 1.280000-24725 3103 252 1.200000+7 1.385000-2 1.250000+7 1.457000-2 1.300000+7 1.498000-24725 3103 253 1.350000+7 1.511000-2 1.400000+7 1.500000-2 1.450000+7 1.468000-24725 3103 254 1.500000+7 1.423000-2 1.550000+7 1.368000-2 1.600000+7 1.306000-24725 3103 255 1.650000+7 1.241000-2 1.700000+7 1.173000-2 1.750000+7 1.107000-24725 3103 256 1.800000+7 1.041000-2 1.850000+7 9.765000-3 1.900000+7 9.124000-34725 3103 257 1.950000+7 8.526000-3 2.000000+7 7.949000-3 0.000000+0 0.000000+04725 3103 258 4725 3 0 259 4725 0 0 260 0 0 0 261 4.710900+4 1.079690+2 1 0 0 04731 1451 1 0.000000+0 0.000000+0 0 0 0 64731 1451 2 1.000000+0 0.000000+0 0 0 10 64731 1451 3 0.000000+0 0.000000+0 0 0 108 44731 1451 4 47-AG-109 BNL,HEDL EVAL-JUN83 A.PRINCE,R.E.SCHENTER 4731 1451 5 DIST-JAN90 900130 4731 1451 6 ----ENDF/B-VI MATERIAL 4731 4731 1451 7 -----INCIDENT NEUTRON DATA 4731 1451 8 ------ENDF-6 FORMAT 4731 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4731 1451 10 ACTIVATION II 4731 1451 11 ******************************************************************4731 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4731 1451 13 * * * * * * *4731 1451 14 EVALUATION OF A. PRINCE 7/80 WHICH SUPERSEDES ENDF/V MAT 1373 4731 1451 15 BY BNL/HEDL (SCHENTER,BHAT,PRINCE AND JOHNSON). CHANGES IN 4731 1451 16 THE CAPTURE AND ELASTIC KEEPING THE TOTAL CROSS SECTION 4731 1451 17 CONSTANT WERE ALSO MADE BY R. SCHENTER. THESE CHANGES REFLECT 4731 1451 18 THE USE OF RESULTS OF RECENT MEASUREMENTS BY MACKLIN AND 4731 1451 19 POENITZ ON ISOTOPIC AND ELEMENTAL CAPTURE (REF.13 AND REF. 14). 4731 1451 20 ***** ***** *****4731 1451 21 FILE 2 RESONANCE PARAMETERS 4731 1451 22 RESONANCE PARAMETERS BASED ON NEW EXPTL DATA (REF.1) 4731 1451 23 L=0 NUMBER OF RESONANCES IS 83 4731 1451 24 AVERAGE TOTAL WIDTH =2.11512-01 EV 4731 1451 25 AVERAGE REDUCED NEUTRON WIDTH =2.80735-03 EV. 4731 1451 26 AVERAGE GAMMA WIDTH =1.320-01 EV. 4731 1451 27 AVERAGE LEVEL SPACING=3.04977+01 EV. 4731 1451 28 S-WAVE STRENGTH FUNCTION =4.55065-05 4731 1451 29 0.025 EV CAPTURE CROSS SECTION =9.0720+01 BARNS 4731 1451 30 RESONANCE ABSORPTION INTEGRAL (0.5 EV CUT-OFF)= 1.4675+03 B 4731 1451 31 EFFECTIVE SCATTERING RADIUS =6.60 FM. 4731 1451 32 ***** ***** *****4731 1451 33 FILE 3 SMOOTH CROSS SECTIONS 4731 1451 34 4731 1451 35 ALL DATA RE-EVALUATED FROM LATEST EXPTL. DATA COUPLED WITH 4731 1451 36 NUCLEAR MODEL CALCS. 4731 1451 37 MT=1 TOTAL CROSS SECTIONS (ENERGY RANGE 0.25 MEV TO 20.0 MEV 4731 1451 38 BASED ON AG-107 EXPTL. DATA OF REF.2, BNL-325 AND OPTICAL 4731 1451 39 MODEL CALCS. 4731 1451 40 MT=2 ELASTIC SCATTERING CROSS SECTIONS DERIVED FROM ANGLE 4731 1451 41 INTEGRATED EXPTL DATA OF REF.2,BNL-325 AND OPTICAL MODEL 4731 1451 42 CALCS. 4731 1451 43 MT=4 TOTAL INELASTIC CROSS SECTION BASED ON EXPTL. RESULTS OF 4731 1451 44 REF.2,3 AND HAUSER-FESHBACH CALCS. 4731 1451 45 MT=16 N-2N CROSS SECTIONS WERE DETERMINED PRIMARILY FROM THE 4731 1451 46 EXPTL. DATA OF REF.4.,BNL-325 AND STATISTICAL MODEL CALCS. 4731 1451 47 MT=17,22,28,104,105,106 DETERMINED FROM STATISTICAL MODEL CALCS. 4731 1451 48 MT=51 TO 70 DISCRETE INELASTIC CROSS SECTIONS, CALCULATED USING 4731 1451 49 HAUSER-FESHBACH THEORY WITH WIDTH FLUCTUATION CORRECTIONS 4731 1451 50 DERIVED BY REFS.5 AND 6, WERE COMBINED WITH EXPTL. DATA OF 4731 1451 51 REFS.2,3 AND 7. 4731 1451 52 LEVEL EXCITATION INFORMATION UP TO ENERGY= 1.66 MEV TAKEN 4731 1451 53 FROM REFS.8,9 AND 10. 4731 1451 54 MT=91 CONTINUUM INELASTIC CROSS SECTION WITH 0.911 MEV CUTOFF 4731 1451 55 TAKEN AS DIFFERENCE BETWEEN TOTAL INELASTIC AND DISCRETE 4731 1451 56 LEVEL EXCITATIONS. 4731 1451 57 MT=102 RADIATIVE CAPTURE CROSS SECTION USING RESULTS MAINLY 4731 1451 58 FROM REF.13. AND 14. 4731 1451 59 MT=103 N-PROTON CROSS SECTIONS- HAUSER-FESHBACH AND EVAPORATION 4731 1451 60 MODEL CALCS. WERE COMBINED WITH EXPTL. DATA OF REF.4. AND 4731 1451 61 EXPTL DATA IN BNL-325 4731 1451 62 MT=107 N-ALPHA CROSS SECTION CALCS. IN SAME MANNER AS MT=103 4731 1451 63 MT=203,204,206,207 DERIVED FROM RESULTS OF H,D,T,HE-3 AND HE-4 4731 1451 64 CONTAINED IN MT=1-3 TO 107 AND MT=22 AND 28. 4731 1451 65 ***** ***** *****4731 1451 66 FILE 4- ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS 4731 1451 67 MT=2 SAME AS BNL/HEDL EVALUATION REF.11 4731 1451 68 MT=16,17,22,28,51 TO 91 ANGULAR DISTRIBUTIONS ASSUMED TO BE 4731 1451 69 ISOTROPIC 4731 1451 70 FILE 5- ENERGY DISTRIBUTION OF SECONDARY NEUTRONS 4731 1451 71 MT=16,17,22,28 AND 91 ENERGY DISTRIBUTIONS PRESENTED AS 4731 1451 72 HISTOGRAMS BASED ON CALCS. USING NUCLEAR TEMPERATURES 4731 1451 73 FROM REF.12. 4731 1451 74 ***** ***** *****4731 1451 75 SUMMARY 4731 1451 76 FILES 1,2 AND 3 ARE COMPLETELY NEW EVALUATIONS RESOLTING 4731 1451 77 FROM THE MOST RECENT EXPTL. DATA AND IMPROVED MODEL CALCS. 4731 1451 78 FILE 4 INCLUDES 15 ADDITIONAL LEVEL EXCITATIONS AND THE 4731 1451 79 ADDITION OF MT=17,22 AND 28. 4731 1451 80 FILE 5 ALSO EXPANEDED TO INCLUDE MT=17,22 AND 28. 4731 1451 81 FILE 8 & 9 BRANCHING RATIOS FOR (N,G) TAKEN FROM HAUSER- 4731 1451 82 FESHBACH CALCULATIONS (MANN, HEDL). 4731 1451 83 ***** ***** *****4731 1451 84 CODES USED 4731 1451 85 1. CERBERO 2 IMPROVED VERSION OF THE CERBERO COMPUTER CODE 4731 1451 86 FOR CALCULATION OF NUCLEAR REACTION CROSS SECTIONS 4731 1451 87 F.FABBRI,ET AL, RT/FI(77)6 CNEN 1977 4731 1451 88 2. ERINNI AN OPTICAL MODEL FORTRAN IV CODE FOR THE CALCULATION4731 1451 89 OF MULTIPLE CASCADING PARTICLE EMISSIONS F.FABBRI AND 4731 1451 90 G.REFFO RT/FI(77)4 CNEN 1977 4731 1451 91 3. SCAT4U BNL MODIFIED VERSION OF SCAT2 AN OPTICAL MODEL 4731 1451 92 PROGRAM O.DERSILLON- BRUYERS-LE-CHATEL(PRI. COMM.)1979 4731 1451 93 4. THRES2 MODIFIED VERSION OF THRESH -S.PEARLSTEIN BNL 1975 4731 1451 94 (PRI. COMM.) 4731 1451 95 ***** ***** *****4731 1451 96 REFERENCES 4731 1451 97 1. S.MUGHABGHAB BNL(PRIV. COMMUNICATION) 4731 1451 98 2. A.B.SMITH,ET AL, ANL/NDM-46(JAN.1979) 4731 1451 99 3. E.BARNARD ET AL, HARWELL CONF.(1978) PROL.-78-HA 4731 1451 100 4. W.AUGUSTYNIAK,ET AL, NUCL. PHYS.A247,231(1975) 4731 1451 101 5. J.W.TEPEL,ET AL, PHYS.LETT.49B,1(1974) 4731 1451 102 6. H.M.HOFFMAN,ET AL, ANN, PHYS.90,403(1975) 4731 1451 103 7. W.G.VONACH AND A.B.SMITH, NUCL. PHYS.78,389(1966) 4731 1451 104 8. C.M.LEDERER,ET AL, TABLE OF ISOTOPES(7TH-ED.) WILEY(1978) 4731 1451 105 9. H-W.SCHUH,ET AL, ZEIT.F.PHYSIK A293,301(1979) 4731 1451 106 10. Z.MATUMATO,ET AL, JAERI-M7734(1978) 4731 1451 107 11. R.E.SCHENTER,ET AL, ENDF/V SUMMARY DOCUMENTATION 47-107-1 4731 1451 108 HEDL(1979) 4731 1451 109 12. A.G.GILBERT AND A.G.W.CAMERON, CAN. J. PHYS.43,1446(1965) 4731 1451 110 13. R.L.MACKLIN,NUCL.SCI.AND.ENG.82,400(1982) 4731 1451 111 14. W.P.POENITZ,SPEC.MEET.ON.FAST.CAPTURE,ANL-83-4,239(1982) 4731 1451 112 1 451 116 04731 1451 113 2 151 88 04731 1451 114 3 16 11 04731 1451 115 3 102 20 04731 1451 116 4731 1 0 117 4731 0 0 118 4.710900+4 1.079690+2 0 0 1 04731 2151 119 4.710900+4 1.000000+0 0 0 1 04731 2151 120 1.000000-5 2.508980+3 1 2 0 04731 2151 121 5.000000-1 6.600000-1 0 0 1 04731 2151 122 1.079690+2 0.000000+0 0 0 498 834731 2151 123 5.190000+0 1.000000+0 1.487330-1 1.273300-2 1.360000-1 0.000000+04731 2151 124 3.040000+1 1.000000+0 1.373300-1 7.333300-3 1.300000-1 0.000000+04731 2151 125 4.010000+1 1.000000+0 1.360000-1 5.000000-3 1.310000-1 0.000000+04731 2151 126 5.570000+1 0.000000+0 1.762000-1 3.720000-2 1.390000-1 0.000000+04731 2151 127 7.080000+1 1.000000+0 1.466700-1 2.666700-2 1.200000-1 0.000000+04731 2151 128 8.350000+1 0.000000+0 1.320700-1 7.400000-5 1.320000-1 0.000000+04731 2151 129 8.770000+1 1.000000+0 1.362700-1 6.266700-3 1.300000-1 0.000000+04731 2151 130 9.150000+1 1.000000+0 1.320300-1 3.333300-5 1.320000-1 0.000000+04731 2151 131 1.063000+2 1.000000+0 1.321300-1 1.333300-4 1.320000-1 0.000000+04731 2151 132 1.135000+2 0.000000+0 1.321200-1 1.160000-4 1.320000-1 0.000000+04731 2151 133 1.339000+2 1.000000+0 2.000000-1 8.000000-2 1.200000-1 0.000000+04731 2151 134 1.397000+2 0.000000+0 1.378000-1 4.800000-3 1.330000-1 0.000000+04731 2151 135 1.698000+2 1.000000+0 1.322600-1 2.600000-4 1.320000-1 0.000000+04731 2151 136 1.731000+2 1.000000+0 1.830000-1 4.300000-2 1.400000-1 0.000000+04731 2151 137 2.096000+2 1.000000+0 1.570000-1 2.400000-2 1.330000-1 0.000000+04731 2151 138 2.513000+2 1.000000+0 1.313300-1 1.133300-2 1.200000-1 0.000000+04731 2151 139 2.590000+2 1.000000+0 1.124000-1 1.400000-3 1.110000-1 0.000000+04731 2151 140 2.647000+2 0.000000+0 1.327200-1 7.200000-4 1.320000-1 0.000000+04731 2151 141 2.726000+2 1.000000+0 1.335300-1 1.533300-3 1.320000-1 0.000000+04731 2151 142 2.910000+2 0.000000+0 1.760000-1 3.600000-2 1.400000-1 0.000000+04731 2151 143 2.933000+2 1.000000+0 1.322300-1 2.266700-4 1.320000-1 0.000000+04731 2151 144 3.009000+2 1.000000+0 1.329300-1 9.333300-4 1.320000-1 0.000000+04731 2151 145 3.165000+2 1.000000+0 2.986700-1 1.666700-1 1.320000-1 0.000000+04731 2151 146 3.221000+2 1.000000+0 1.321500-1 1.466700-4 1.320000-1 0.000000+04731 2151 147 3.278000+2 1.000000+0 1.368000-1 4.800000-3 1.320000-1 0.000000+04731 2151 148 3.402000+2 0.000000+0 1.325200-1 5.200000-4 1.320000-1 0.000000+04731 2151 149 3.870000+2 1.000000+0 1.903300-1 4.333300-2 1.470000-1 0.000000+04731 2151 150 3.916000+2 1.000000+0 1.322100-1 2.133300-4 1.320000-1 0.000000+04731 2151 151 3.980000+2 1.000000+0 1.620000-1 2.200000-2 1.400000-1 0.000000+04731 2151 152 4.044000+2 0.000000+0 3.460000-1 2.000000-1 1.460000-1 0.000000+04731 2151 153 4.286000+2 1.000000+0 1.446700-1 1.266700-2 1.320000-1 0.000000+04731 2151 154 4.410000+2 1.000000+0 1.321300-1 1.266700-4 1.320000-1 0.000000+04731 2151 155 4.697000+2 0.000000+0 2.700000-1 1.380000-1 1.320000-1 0.000000+04731 2151 156 4.870000+2 1.000000+0 1.486700-1 1.666700-2 1.320000-1 0.000000+04731 2151 157 4.952000+2 1.000000+0 1.326000-1 6.000000-4 1.320000-1 0.000000+04731 2151 158 5.006000+2 1.000000+0 2.746700-1 1.506700-1 1.240000-1 0.000000+04731 2151 159 5.154000+2 0.000000+0 3.140000-1 1.820000-1 1.320000-1 0.000000+04731 2151 160 5.267000+2 1.000000+0 1.329300-1 9.333300-4 1.320000-1 0.000000+04731 2151 161 5.572000+2 1.000000+0 1.493300-1 1.733300-2 1.320000-1 0.000000+04731 2151 162 5.607000+2 0.000000+0 3.910000-1 2.640000-1 1.270000-1 0.000000+04731 2151 163 5.655000+2 1.000000+0 2.300000-1 9.200000-2 1.380000-1 0.000000+04731 2151 164 6.081000+2 1.000000+0 1.903300-1 3.333300-2 1.570000-1 0.000000+04731 2151 165 6.224000+2 0.000000+0 3.100000-1 2.000000-1 1.100000-1 0.000000+04731 2151 166 6.345000+2 1.000000+0 1.326700-1 6.666700-4 1.320000-1 0.000000+04731 2151 167 6.483000+2 1.000000+0 1.326700-1 6.666700-4 1.320000-1 0.000000+04731 2151 168 6.695000+2 1.000000+0 1.344700-1 2.466700-3 1.320000-1 0.000000+04731 2151 169 6.815000+2 1.000000+0 1.348000-1 2.800000-3 1.320000-1 0.000000+04731 2151 170 6.874000+2 1.000000+0 1.334000-1 1.400000-3 1.320000-1 0.000000+04731 2151 171 7.138000+2 1.000000+0 1.330700-1 1.066700-3 1.320000-1 0.000000+04731 2151 172 7.261000+2 0.000000+0 1.920000-1 6.000000-2 1.320000-1 0.000000+04731 2151 173 7.303000+2 1.000000+0 1.330700-1 1.066700-3 1.320000-1 0.000000+04731 2151 174 7.476000+2 1.000000+0 2.040000-1 7.200000-2 1.320000-1 0.000000+04731 2151 175 7.520000+2 1.000000+0 1.786700-1 4.666700-2 1.320000-1 0.000000+04731 2151 176 7.847000+2 0.000000+0 6.920000-1 5.600000-1 1.320000-1 0.000000+04731 2151 177 8.038000+2 1.000000+0 1.660000-1 3.400000-2 1.320000-1 0.000000+04731 2151 178 8.314000+2 1.000000+0 1.360000-1 4.000000-3 1.320000-1 0.000000+04731 2151 179 8.618300+2 1.000000+0 1.426700-1 1.066700-2 1.320000-1 0.000000+04731 2151 180 8.830000+2 0.000000+0 3.520000-1 2.200000-1 1.320000-1 0.000000+04731 2151 181 9.028000+2 1.000000+0 1.440000-1 1.200000-2 1.320000-1 0.000000+04731 2151 182 9.330000+2 1.000000+0 2.053300-1 7.333300-2 1.320000-1 0.000000+04731 2151 183 9.493000+2 1.000000+0 1.400000-1 8.000000-3 1.320000-1 0.000000+04731 2151 184 9.610000+2 0.000000+0 1.940000-1 6.200000-2 1.320000-1 0.000000+04731 2151 185 9.760000+2 1.000000+0 2.006700-1 6.866700-2 1.320000-1 0.000000+04731 2151 186 1.009000+3 1.000000+0 2.206700-1 8.866700-2 1.320000-1 0.000000+04731 2151 187 1.057000+3 1.000000+0 1.720000-1 4.000000-2 1.320000-1 0.000000+04731 2151 188 1.062000+3 0.000000+0 2.520000-1 1.200000-1 1.320000-1 0.000000+04731 2151 189 1.116000+3 1.000000+0 1.853300-1 5.333300-2 1.320000-1 0.000000+04731 2151 190 1.204000+3 1.000000+0 3.053300-1 1.733300-1 1.320000-1 0.000000+04731 2151 191 1.219000+3 1.000000+0 3.186700-1 1.866700-1 1.320000-1 0.000000+04731 2151 192 1.236000+3 0.000000+0 4.120000-1 2.800000-1 1.320000-1 0.000000+04731 2151 193 1.300000+3 1.000000+0 2.153300-1 8.333300-2 1.320000-1 0.000000+04731 2151 194 1.383000+3 1.000000+0 1.920000-1 6.000000-2 1.320000-1 0.000000+04731 2151 195 1.415000+3 1.000000+0 2.620000-1 1.300000-1 1.320000-1 0.000000+04731 2151 196 1.484000+3 0.000000+0 2.480000-1 1.160000-1 1.320000-1 0.000000+04731 2151 197 1.512000+3 1.000000+0 2.353300-1 1.033300-1 1.320000-1 0.000000+04731 2151 198 1.587000+3 1.000000+0 2.920000-1 1.600000-1 1.320000-1 0.000000+04731 2151 199 1.678000+3 1.000000+0 2.253300-1 9.333300-2 1.320000-1 0.000000+04731 2151 200 1.914000+3 0.000000+0 1.092000+0 9.600000-1 1.320000-1 0.000000+04731 2151 201 2.091000+3 1.000000+0 2.520000-1 1.200000-1 1.320000-1 0.000000+04731 2151 202 2.129000+3 1.000000+0 3.853300-1 2.533300-1 1.320000-1 0.000000+04731 2151 203 2.329000+3 1.000000+0 4.733300-1 3.413300-1 1.320000-1 0.000000+04731 2151 204 2.350000+3 0.000000+0 2.580000-1 1.260000-1 1.320000-1 0.000000+04731 2151 205 2.506000+3 1.000000+0 1.553300-1 2.333300-2 1.320000-1 0.000000+04731 2151 206 4731 2 0 207 4731 0 0 208 4.710900+4 1.079690+2 0 0 0 04731 3 16 209 -9.186000+6-9.186000+6 0 0 1 234731 3 16 210 23 2 0 0 0 04731 3 16 211 9.271000+6 0.000000+0 9.500000+6 1.240000-2 1.000000+7 1.550000-14731 3 16 212 1.050000+7 3.760000-1 1.100000+7 6.210000-1 1.150000+7 8.410000-14731 3 16 213 1.200000+7 1.009000+0 1.250000+7 1.133000+0 1.300000+7 1.224000+04731 3 16 214 1.350000+7 1.293000+0 1.400000+7 1.336000+0 1.450000+7 1.369000+04731 3 16 215 1.500000+7 1.386000+0 1.550000+7 1.390000+0 1.600000+7 1.387000+04731 3 16 216 1.650000+7 1.376000+0 1.700000+7 1.356000+0 1.750000+7 1.328000+04731 3 16 217 1.800000+7 1.288000+0 1.850000+7 1.236000+0 1.900000+7 1.169000+04731 3 16 218 1.950000+7 1.088000+0 2.000000+7 9.900000-1 0.000000+0 0.000000+04731 3 16 219 4731 3 0 220 4.710900+4 1.079690+2 0 0 0 04731 3102 221 6.825000+6 6.825000+6 0 0 1 494731 3102 222 49 2 0 0 0 04731 3102 223 1.000000-5 0.000000+0 2.530000-2 0.000000+0 2.508980+3 0.000000+04731 3102 224 2.508980+3 2.460000+0 2.508990+3 2.459900+0 3.000000+3 2.180000+04731 3102 225 3.500000+3 1.980000+0 4.000000+3 1.830000+0 5.000000+3 1.640000+04731 3102 226 1.000000+4 1.280000+0 2.000000+4 9.700000-1 5.000000+4 6.400000-14731 3102 227 7.000000+4 5.200000-1 1.000000+5 4.400000-1 2.000000+5 3.400000-14731 3102 228 3.000000+5 2.400000-1 4.000000+5 1.900000-1 5.000000+5 1.600000-14731 3102 229 6.000000+5 1.400000-1 7.000000+5 1.220000-1 8.000000+5 1.070000-14731 3102 230 9.000000+5 9.500000-2 1.000000+6 8.000000-2 1.100000+6 7.300000-24731 3102 231 1.200000+6 6.900000-2 1.300000+6 6.500000-2 1.400000+6 6.100000-24731 3102 232 1.500000+6 6.000000-2 1.600000+6 5.800000-2 1.700000+6 5.500000-24731 3102 233 1.800000+6 5.200000-2 1.900000+6 5.100000-2 2.000000+6 4.900000-24731 3102 234 2.100000+6 4.700000-2 2.200000+6 4.400000-2 2.500000+6 3.900000-24731 3102 235 3.000000+6 3.100000-2 3.500000+6 2.700000-2 4.000000+6 2.200000-24731 3102 236 4.500000+6 2.000000-2 5.000000+6 1.700000-2 6.000000+6 1.100000-24731 3102 237 8.000000+6 8.870000-3 1.000000+7 5.420000-3 1.200000+7 3.860000-34731 3102 238 1.400000+7 3.030000-3 1.600000+7 2.590000-3 1.800000+7 2.310000-34731 3102 239 2.000000+7 2.090000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+04731 3102 240 4731 3 0 241 4731 0 0 242 0 0 0 243 4.911500+4 1.139200+2 1 0 0 14931 1451 1 0.000000+0 0.000000+0 0 0 0 64931 1451 2 1.000000+0 0.000000+0 0 0 10 64931 1451 3 0.000000+0 0.000000+0 0 0 107 94931 1451 4 49-IN-115 HEDL,ANL EVAL-MAR90 F.SCHMITTROTH,D.L.SMITH,S.CHIBA 4931 1451 5 DIST-JUN90 900329 4931 1451 6 ----ENDF/B-VI MATERIAL 4931 4931 1451 7 -----INCIDENT NEUTRON DATA 4931 1451 8 ------ENDF-6 FORMAT 4931 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************4931 1451 10 ACTIVATION II 4931 1451 11 ******************************************************************4931 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 4931 1451 13 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 4931 1451 14 4931 1451 15 IN-115(N,N')IN-115M DOSIMETRY REACTION 4931 1451 16 4931 1451 17 EVALUATED BY S.CHIBA AND D.L. SMITH, ANL, JANUARY 1990 4931 1451 18 4931 1451 19 PRODUCTION OF THE ISOMER IN-115M BY THE (N,N') PROCESS IS 4931 1451 20 ROUTINELY EMPLOYED FOR NEUTRON DOSIMETRY APPLICATIONS. THIS 4931 1451 21 ISOMER IS THE FIRST-EXCITED STATE OF THE ISOTOPE IN-115 (336 KEV 4931 1451 22 EXCITATION ENERGY). THE REACTION THRESHOLD ENERGY IS 339 KEV. 4931 1451 23 THE ISOTOPIC ABUNDANCE OF IN-115 IN NATURAL INDIUM IS 95.7 4931 1451 24 PERCENT. THE HALF LIFE OF IN-115M IS 4.486 HOURS. THE DECAY 4931 1451 25 MODES ARE - BETA MINUS (5 PERCENT) ISOMERIC TRANSITION (95.0 4931 1451 26 PERCENT). THE NUMBER OF DECAY 336-KEV GAMMA RAYS EMITTED PER 4931 1451 27 DISINTEGRATION OF IN-115M IS 0.459. 4931 1451 28 4931 1451 29 DOCUMENTATION FOR THIS EVALUATION IS PROVIDED BY A.B. SMITH ET 4931 1451 30 AL., REPORT ANL/NDM-115, ARGONNE NATIONAL LABORATORY (1990). 4931 1451 31 EVALUATED RESULTS FOR THIS REACTION ARE BASED ON EXPERIMENTAL 4931 1451 32 DATA. NUCLEAR MODEL CALCULATIONS WERE USED TO ESTIMATE THE CROSS 4931 1451 33 SECTION SHAPE NEAR THRESHOLD. THIS EVALUATION WAS CARRIED OUT 4931 1451 34 USING THE STATISTICAL LEAST-SQUARES METHOD. THE CODE GMA, AS 4931 1451 35 DEVELOPED BY W. POENITZ (1981) AND LATER REVISED BY M. SUGIMOTO 4931 1451 36 (1987) AND S. CHIBA (1990), WAS EMPLOYED FOR THIS ANALYSIS. 4931 1451 37 4931 1451 38 * * * * * * *4931 1451 39 CAPTURE TO 54 MIN. ISOMERIC STATE DESCRIPTION MODIFIED BY 4931 1451 40 R. SCHENTER ON 2/20/84. THIS WAS DONE BY ADDING FILE9 WITH 4931 1451 41 Y=.79 AND PUTTING THE TOTAL CAPTURE WIDTH IN FILE2 AND THE TOTAL 4931 1451 42 CAPTURE CROSS SECTION IN FILE3. 4931 1451 43 P.C.TO NORMALIZATION+STANDARDS SUBCOMITTEE (N,N')D.L.SMITH MT=51 4931 1451 44 P.C.TO NORMALIZATION+STANDARDS SUBCOMITTEE (N,G)F.SCHMITTROTH 4931 1451 45 MF=2 MT=151 4931 1451 46 MF=2 MT=102 4931 1451 47 * * * * * 4931 1451 48 4931 1451 49 FILE INFORMATION 4931 1451 50 4931 1451 51 MF=1 MT=451 ATOMIC MASS FROM REF(1). 4931 1451 52 4931 1451 53 MF=2 MT=151 EVALUATION OF RESOLVED RESONANCE PARAMETERS 4931 1451 54 BASED ON NEW BNL-325, REF(2). 4931 1451 55 4931 1451 56 MF=3 MT= 51 EVALUATION OF THE 4.486 H ISOMER BASED ENTIRELY ON 4931 1451 57 REPORTED EXPERIMENTAL DATA.DOCUMENTATION AVAILABLE 4931 1451 58 AS ANL/NDM-26 BY D.L.SMITH REFERENCES 4931 1451 59 USED LISTED BELOW 10 TO 25. 4931 1451 60 MF=3 MT=102 VERSION-V UNRESOLVED REGION CONTAINS ADJUSTED DATA 4931 1451 61 SEE DOCUMENTATION 4931 1451 62 RADIATIVE NEUTRON CAPTURE TO THE IN 116M(54 MIN.) 4931 1451 63 STATE. 4931 1451 64 E GREATER THAN EH, 4931 1451 65 EVALUATION BASED ON EXPERIMENTAL DATA, REF.(3-7) 4931 1451 66 AND THEORETICAL CALCULATIONS, REF.(8,9). 4931 1451 67 E LESS THAT EH, 4931 1451 68 A 1/V COMPONENT WAS ADDED TO GIVE THE CORRECT 4931 1451 69 2200M/S CROSS SECTION TO THE 54 MIN. STATE(THE 4931 1451 70 2.2 SEC. STATE CROSS SECTION WAS INCLUDED). 4931 1451 71 RADIATIVE CAPTURE TO THE 2.2 SEC. STATE OF IN 116 WAS 4931 1451 72 INCLUDED AS PART OF THE CAPTURE TO THE 54 MIN. STATE 4931 1451 73 FOR BOTH THERMAL AND FAST ENERGIES. 4931 1451 74 RESULTS WERE DIVIDED BY .79 TO GIVE THE TOTAL CAP- 4931 1451 75 TURE CROSS SECTION IN FILE3. FILE9 COMBINED WITH 4931 1451 76 FILE3 IS REQUIRED TO GIVE CAPTURE TO 54 MIN. 4931 1451 77 ISOMERIC STATE. 4931 1451 78 4931 1451 79 2200M/S CAPTURE CROSS SECTION,BARNS TO THE 54 MIN. STATE 4931 1451 80 (FROM RESONANCE PARAMETERS) = 166.413 4931 1451 81 4931 1451 82 COMPUTED RESONANCE INTEGRAL =2587.345 4931 1451 83 4931 1451 84 REFERENCES. 4931 1451 85 1. A.H.WAPSTRA AND N.B.GOVE,NUCL. DATA TABLES,VOL.9,PART 1(1971).4931 1451 86 2. S.F.MUGHABGHAB AND D.I.GARBER,BNL-325,3RD ED.,VOL.1(1973) 4931 1451 87 3. H.A.GRENCH AND H.O.MENLOVE,PHYS.REV.,VOL.165(1968)1298. 4931 1451 88 4. H.O.MENLOVE,ET AL.,PHYS.REV.,VOL.163(1967)1299. 4931 1451 89 5. S.A.COX, PHYS.REV.,VOL.133(1964)B378. 4931 1451 90 6. A.E.JOHNSRUD,ET AL.,PHYS.REV.,VOL.116(1959)927. 4931 1451 91 7. G.PETO ET AL., J.NUCL.EN.,VOL.21(1967)797. 4931 1451 92 8. F.SCHMITTROTH, HEDL-TME 71-106(AUGUST 1971). 4931 1451 93 9. F.SCHMITTROTH, HEDL-TME 73-79,ENDF-195(NOVEMBER 1973). 4931 1451 94 10. D.L.SMITH ET.AL. ANL/NDM-14,1975 4931 1451 95 11. D.C.SANTRY AND J.P.BUTLER CAN.J.PHYS.54,757,1975 4931 1451 96 12. K.KOBAYASHI ET.AL. J.NUC.EN.27,741,73 4931 1451 97 13. A.PASZIT AND J.CSIKAI SOV.J.NUC.PHYS.15,232,1972 4931 1451 98 14. J.K.TEMPERLY AND D.E.BARNES BRL-1491,1970 4931 1451 99 15. P.DECOWSKI ET.AL.INR-1197 POLAND 1970 4931 1451 100 16. I.KIMURA ET.AL. J.NUC.SCI.TECH.JAP.6,485,69 4931 1451 101 17. R.C.BARRALL ET.AL. AFWL-TR-68-134,1969 4931 1451 102 18. H.ROETZER NUC.PHYS.A109,694,1968 4931 1451 103 19. B.MINETTI AND A.PAQUARETTI Z.PHYS.217,83,1968 4931 1451 104 20. H.A.GRENCH AND H.O.MENLOVE PHYS.REV.165,1298,1968 4931 1451 105 21. H.O.MENLOVE ET.AL. PHYS.REV.163,1308,1967 4931 1451 106 22. W.NAGEL AND A.H.W.ATEN JR. PHYSICA 31,1091,1965 4931 1451 107 23. A.A.ABEL AND C.GOODMAN PHYS.REV.93,197,1954 4931 1451 108 24. H.C.MARTIN AND B.C.DIVEN PHYS.REV.93,199,1954 4931 1451 109 25. S.G.COHEN NATURE 161,475,1948 4931 1451 110 4931 1451 111 1 451 120 04931 1451 112 2 151 145 04931 1451 113 3 102 16 04931 1451 114 8 4 4 14931 1451 115 8 102 5 04931 1451 116 9 102 4 04931 1451 117 10 4 14 14931 1451 118 33 102 6 04931 1451 119 40 4 87 14931 1451 120 4931 1 0 121 4931 0 0 122 4.911500+4 1.139200+2 0 0 1 04931 2151 123 4.911500+4 1.000000+0 0 0 1 04931 2151 124 1.000000-5 1.003800+3 1 1 0 04931 2151 125 4.500000+0 6.500000-1 0 0 2 04931 2151 126 1.139200+2 0.000000+0 0 0 534 894931 2151 127 1.457000+0 5.000000+0 7.503600-2 3.036400-3 7.200000-2 0.000000+04931 2151 128 3.860000+0 4.000000+0 8.135400-2 3.544400-4 8.100000-2 0.000000+04931 2151 129 9.120000+0 5.000000+0 8.157300-2 1.572700-3 8.000000-2 0.000000+04931 2151 130 1.210000+1 4.500000+0 1.401100-1 1.120000-4 1.400000-1 0.000000+04931 2151 131 2.273000+1 4.500000+0 8.204000-2 1.040000-3 8.100000-2 0.000000+04931 2151 132 2.300000+1 4.500000+0 8.088000-2 1.180000-3 7.970000-2 0.000000+04931 2151 133 3.960000+1 4.500000+0 8.000000-2 4.000000-3 7.600000-2 0.000000+04931 2151 134 4.636000+1 4.500000+0 7.996000-2 2.600000-4 7.970000-2 0.000000+04931 2151 135 4.814000+1 4.500000+0 9.060000-2 6.000000-4 9.000000-2 0.000000+04931 2151 136 6.300000+1 4.500000+0 9.584000-2 8.400000-4 9.500000-2 0.000000+04931 2151 137 6.950000+1 4.500000+0 8.010000-2 4.000000-4 7.970000-2 0.000000+04931 2151 138 8.087000+1 4.500000+0 7.150000-2 1.500000-3 7.000000-2 0.000000+04931 2151 139 8.328000+1 4.500000+0 7.960000-2 6.600000-3 7.300000-2 0.000000+04931 2151 140 9.434000+1 4.500000+0 9.290000-2 2.900000-3 9.000000-2 0.000000+04931 2151 141 1.258900+2 4.500000+0 6.880000-2 3.800000-3 6.500000-2 0.000000+04931 2151 142 1.328100+2 4.500000+0 1.854000-1 5.400000-3 1.800000-1 0.000000+04931 2151 143 1.502900+2 4.500000+0 8.960000-2 4.600000-3 8.500000-2 0.000000+04931 2151 144 1.646700+2 4.500000+0 1.000000-1 1.800000-2 8.200000-2 0.000000+04931 2151 145 1.680800+2 4.500000+0 8.180000-2 2.100000-3 7.970000-2 0.000000+04931 2151 146 1.779200+2 4.500000+0 8.300000-2 3.000000-3 8.000000-2 0.000000+04931 2151 147 1.869600+2 4.500000+0 1.200000-1 2.000000-2 1.000000-1 0.000000+04931 2151 148 2.056000+2 4.500000+0 1.027000-1 2.300000-2 7.970000-2 0.000000+04931 2151 149 2.118800+2 4.500000+0 8.022000-2 5.200000-4 7.970000-2 0.000000+04931 2151 150 2.240300+2 4.500000+0 9.200000-2 3.200000-2 6.000000-2 0.000000+04931 2151 151 2.268100+2 4.500000+0 8.102000-2 1.320000-3 7.970000-2 0.000000+04931 2151 152 2.501700+2 4.500000+0 1.450000-1 6.000000-2 8.500000-2 0.000000+04931 2151 153 2.669600+2 4.500000+0 8.370000-2 4.000000-3 7.970000-2 0.000000+04931 2151 154 2.888800+2 4.500000+0 9.970000-2 2.000000-2 7.970000-2 0.000000+04931 2151 155 2.943300+2 4.500000+0 1.237000-1 4.400000-2 7.970000-2 0.000000+04931 2151 156 3.194900+2 4.500000+0 9.470000-2 1.500000-2 7.970000-2 0.000000+04931 2151 157 3.398000+2 4.500000+0 8.160000-2 1.900000-3 7.970000-2 0.000000+04931 2151 158 3.541300+2 4.500000+0 8.598000-2 6.280000-3 7.970000-2 0.000000+04931 2151 159 3.621000+2 4.500000+0 9.058000-2 1.088000-2 7.970000-2 0.000000+04931 2151 160 3.709400+2 4.500000+0 8.660000-2 6.900000-3 7.970000-2 0.000000+04931 2151 161 3.829700+2 4.500000+0 8.092000-2 1.220000-3 7.970000-2 0.000000+04931 2151 162 3.842000+2 4.500000+0 8.556000-2 5.860000-3 7.970000-2 0.000000+04931 2151 163 4.023500+2 4.500000+0 1.111000-1 3.140000-2 7.970000-2 0.000000+04931 2151 164 4.115600+2 4.500000+0 1.111000-1 3.140000-2 7.970000-2 0.000000+04931 2151 165 4.230000+2 4.500000+0 9.016000-2 1.046000-2 7.970000-2 0.000000+04931 2151 166 4.371600+2 4.500000+0 8.074000-2 1.040000-3 7.970000-2 0.000000+04931 2151 167 4.489000+2 4.500000+0 9.224000-2 1.254000-2 7.970000-2 0.000000+04931 2151 168 4.538900+2 4.500000+0 1.007000-1 2.100000-2 7.970000-2 0.000000+04931 2151 169 4.568200+2 4.500000+0 9.890000-2 1.920000-2 7.970000-2 0.000000+04931 2151 170 4.696500+2 4.500000+0 8.514000-2 5.440000-3 7.970000-2 0.000000+04931 2151 171 4.775500+2 4.500000+0 8.284000-2 3.140000-3 7.970000-2 0.000000+04931 2151 172 4.982000+2 4.500000+0 8.262000-2 2.920000-3 7.970000-2 0.000000+04931 2151 173 5.037300+2 4.500000+0 1.047000-1 2.500000-2 7.970000-2 0.000000+04931 2151 174 5.153800+2 4.500000+0 8.304000-2 3.340000-3 7.970000-2 0.000000+04931 2151 175 5.254600+2 4.500000+0 9.392000-2 1.422000-2 7.970000-2 0.000000+04931 2151 176 5.479200+2 4.500000+0 8.514000-2 5.440000-3 7.970000-2 0.000000+04931 2151 177 5.511000+2 4.500000+0 8.138000-2 1.680000-3 7.970000-2 0.000000+04931 2151 178 5.718600+2 4.500000+0 1.152400-1 3.554000-2 7.970000-2 0.000000+04931 2151 179 5.801900+2 4.500000+0 8.764000-2 7.940000-3 7.970000-2 0.000000+04931 2151 180 5.890900+2 4.500000+0 8.640000-2 6.700000-3 7.970000-2 0.000000+04931 2151 181 6.022200+2 4.500000+0 8.180000-2 2.100000-3 7.970000-2 0.000000+04931 2151 182 6.141300+2 4.500000+0 1.173400-1 3.764000-2 7.970000-2 0.000000+04931 2151 183 6.195900+2 4.500000+0 9.642000-2 1.672000-2 7.970000-2 0.000000+04931 2151 184 6.439300+2 4.500000+0 8.450000-2 4.800000-3 7.970000-2 0.000000+04931 2151 185 6.470700+2 4.500000+0 8.542000-2 5.720000-3 7.970000-2 0.000000+04931 2151 186 6.548000+2 4.500000+0 8.870000-2 9.000000-3 7.970000-2 0.000000+04931 2151 187 6.740300+2 4.500000+0 9.098000-2 1.128000-2 7.970000-2 0.000000+04931 2151 188 6.832300+2 4.500000+0 8.284000-2 3.140000-3 7.970000-2 0.000000+04931 2151 189 6.946200+2 4.500000+0 8.388000-2 4.180000-3 7.970000-2 0.000000+04931 2151 190 7.047500+2 4.500000+0 8.200000-2 2.300000-3 7.970000-2 0.000000+04931 2151 191 7.078300+2 4.500000+0 8.556000-2 5.860000-3 7.970000-2 0.000000+04931 2151 192 7.198500+2 4.500000+0 8.284000-2 3.140000-3 7.970000-2 0.000000+04931 2151 193 7.278400+2 4.500000+0 8.304000-2 3.340000-3 7.970000-2 0.000000+04931 2151 194 7.332500+2 4.500000+0 9.204000-2 1.234000-2 7.970000-2 0.000000+04931 2151 195 7.526600+2 4.500000+0 8.200000-2 2.300000-3 7.970000-2 0.000000+04931 2151 196 7.740200+2 4.500000+0 1.006000-1 2.090000-2 7.970000-2 0.000000+04931 2151 197 7.835400+2 4.500000+0 9.558000-2 1.588000-2 7.970000-2 0.000000+04931 2151 198 7.895800+2 4.500000+0 9.642000-2 1.672000-2 7.970000-2 0.000000+04931 2151 199 7.950800+2 4.500000+0 8.550000-2 5.800000-3 7.970000-2 0.000000+04931 2151 200 8.157300+2 4.500000+0 8.304000-2 3.340000-3 7.970000-2 0.000000+04931 2151 201 8.194100+2 4.500000+0 8.806000-2 8.360000-3 7.970000-2 0.000000+04931 2151 202 8.297900+2 4.500000+0 9.058000-2 1.088000-2 7.970000-2 0.000000+04931 2151 203 8.367000+2 4.500000+0 9.746000-2 1.776000-2 7.970000-2 0.000000+04931 2151 204 8.535200+2 4.500000+0 1.382400-1 5.854000-2 7.970000-2 0.000000+04931 2151 205 8.610800+2 4.500000+0 1.027000-1 2.300000-2 7.970000-2 0.000000+04931 2151 206 8.638500+2 4.500000+0 9.850000-2 1.880000-2 7.970000-2 0.000000+04931 2151 207 8.750900+2 4.500000+0 8.660000-2 6.900000-3 7.970000-2 0.000000+04931 2151 208 8.916200+2 4.500000+0 9.558000-2 1.588000-2 7.970000-2 0.000000+04931 2151 209 8.989600+2 4.500000+0 8.326000-2 3.560000-3 7.970000-2 0.000000+04931 2151 210 9.139000+2 4.500000+0 9.350000-2 1.380000-2 7.970000-2 0.000000+04931 2151 211 9.234300+2 4.500000+0 8.598000-2 6.280000-3 7.970000-2 0.000000+04931 2151 212 9.481200+2 4.500000+0 1.319000-1 5.220000-2 7.970000-2 0.000000+04931 2151 213 9.565700+2 4.500000+0 1.110600-1 3.136000-2 7.970000-2 0.000000+04931 2151 214 9.779900+2 4.500000+0 1.160000-1 3.630000-2 7.970000-2 0.000000+04931 2151 215 9.979699+2 4.500000+0 1.131000-1 3.340000-2 7.970000-2 0.000000+04931 2151 216 1.139200+2 0.000000+0 1 0 300 504931 2151 217 7.308000+1 4.500000+0 7.971200-2 1.200000-5 7.970000-2 0.000000+04931 2151 218 8.636000+1 4.500000+0 7.975200-2 5.200000-5 7.970000-2 0.000000+04931 2151 219 1.008300+2 4.500000+0 7.974400-2 4.400000-5 7.970000-2 0.000000+04931 2151 220 1.109000+2 4.500000+0 7.974800-2 4.800000-5 7.970000-2 0.000000+04931 2151 221 1.144300+2 4.500000+0 7.980400-2 1.040000-4 7.970000-2 0.000000+04931 2151 222 1.207100+2 4.500000+0 7.970800-2 8.000000-6 7.970000-2 0.000000+04931 2151 223 1.440400+2 4.500000+0 7.984600-2 1.460000-4 7.970000-2 0.000000+04931 2151 224 1.457600+2 4.500000+0 7.976000-2 6.000000-5 7.970000-2 0.000000+04931 2151 225 1.585900+2 4.500000+0 7.984600-2 1.460000-4 7.970000-2 0.000000+04931 2151 226 1.740800+2 4.500000+0 7.990000-2 2.000000-4 7.970000-2 0.000000+04931 2151 227 1.922400+2 4.500000+0 7.973200-2 3.200000-5 7.970000-2 0.000000+04931 2151 228 1.944500+2 4.500000+0 7.982400-2 1.240000-4 7.970000-2 0.000000+04931 2151 229 1.988300+2 4.500000+0 7.977200-2 7.200000-5 7.970000-2 0.000000+04931 2151 230 2.140900+2 4.500000+0 7.987600-2 1.760000-4 7.970000-2 0.000000+04931 2151 231 2.392800+2 4.500000+0 7.995400-2 2.540000-4 7.970000-2 0.000000+04931 2151 232 2.467400+2 4.500000+0 7.989200-2 1.920000-4 7.970000-2 0.000000+04931 2151 233 2.767700+2 4.500000+0 7.983600-2 1.360000-4 7.970000-2 0.000000+04931 2151 234 2.822800+2 4.500000+0 7.988600-2 1.860000-4 7.970000-2 0.000000+04931 2151 235 3.025200+2 4.500000+0 7.980400-2 1.040000-4 7.970000-2 0.000000+04931 2151 236 3.083700+2 4.500000+0 7.982600-2 1.260000-4 7.970000-2 0.000000+04931 2151 237 3.295700+2 4.500000+0 7.990000-2 2.000000-4 7.970000-2 0.000000+04931 2151 238 3.367300+2 4.500000+0 7.990000-2 2.000000-4 7.970000-2 0.000000+04931 2151 239 3.451800+2 4.500000+0 7.973000-2 3.000000-5 7.970000-2 0.000000+04931 2151 240 3.606000+2 4.500000+0 7.990000-2 2.000000-4 7.970000-2 0.000000+04931 2151 241 3.668700+2 4.500000+0 8.004000-2 3.400000-4 7.970000-2 0.000000+04931 2151 242 3.791000+2 4.500000+0 8.032800-2 6.280000-4 7.970000-2 0.000000+04931 2151 243 4.312100+2 4.500000+0 7.992000-2 2.200000-4 7.970000-2 0.000000+04931 2151 244 4.735800+2 4.500000+0 8.026000-2 5.600000-4 7.970000-2 0.000000+04931 2151 245 4.880100+2 4.500000+0 8.034000-2 6.400000-4 7.970000-2 0.000000+04931 2151 246 4.936700+2 4.500000+0 8.020000-2 5.000000-4 7.970000-2 0.000000+04931 2151 247 5.018800+2 4.500000+0 8.074000-2 1.040000-3 7.970000-2 0.000000+04931 2151 248 5.062100+2 4.500000+0 8.078000-2 1.080000-3 7.970000-2 0.000000+04931 2151 249 5.131500+2 4.500000+0 7.979800-2 9.800000-5 7.970000-2 0.000000+04931 2151 250 5.301100+2 4.500000+0 8.064000-2 9.400000-4 7.970000-2 0.000000+04931 2151 251 5.597000+2 4.500000+0 8.034000-2 6.400000-4 7.970000-2 0.000000+04931 2151 252 5.626100+2 4.500000+0 8.064000-2 9.400000-4 7.970000-2 0.000000+04931 2151 253 5.696200+2 4.500000+0 8.022000-2 5.200000-4 7.970000-2 0.000000+04931 2151 254 6.099900+2 4.500000+0 8.054000-2 8.400000-4 7.970000-2 0.000000+04931 2151 255 6.991500+2 4.500000+0 8.092000-2 1.220000-3 7.970000-2 0.000000+04931 2151 256 7.241000+2 4.500000+0 8.070000-2 1.000000-3 7.970000-2 0.000000+04931 2151 257 7.600600+2 4.500000+0 8.078000-2 1.080000-3 7.970000-2 0.000000+04931 2151 258 8.006300+2 4.500000+0 8.060000-2 9.000000-4 7.970000-2 0.000000+04931 2151 259 8.125500+2 4.500000+0 8.020000-2 5.000000-4 7.970000-2 0.000000+04931 2151 260 8.694400+2 4.500000+0 8.128000-2 1.580000-3 7.970000-2 0.000000+04931 2151 261 8.825800+2 4.500000+0 8.046000-2 7.600000-4 7.970000-2 0.000000+04931 2151 262 9.067600+2 4.500000+0 8.028000-2 5.800000-4 7.970000-2 0.000000+04931 2151 263 9.319400+2 4.500000+0 8.198000-2 2.280000-3 7.970000-2 0.000000+04931 2151 264 9.437400+2 4.500000+0 8.080000-2 1.100000-3 7.970000-2 0.000000+04931 2151 265 9.738100+2 4.500000+0 8.094000-2 1.240000-3 7.970000-2 0.000000+04931 2151 266 9.817600+2 4.500000+0 8.260000-2 2.900000-3 7.970000-2 0.000000+04931 2151 267 4931 2 0 268 4931 0 0 269 4.911500+4 1.139200+2 0 0 0 04931 3102 270 6.598000+6 6.598000+6 0 0 1 374931 3102 271 37 5 0 0 0 04931 3102 272 1.000000-5 2.489500+2 2.530000-2 4.949400+0 1.003800+3 2.484800-24931 3102 273 1.003800+3 2.405200+0 2.000000+3 1.745600+0 3.000000+3 1.509200+04931 3102 274 5.000000+3 1.303800+0 7.000000+3 1.203900+0 1.000000+4 1.100200+04931 3102 275 2.000000+4 8.691900-1 2.400000+4 8.347800-1 3.000000+4 7.600600-14931 3102 276 5.000000+4 5.796800-1 7.000000+4 4.759000-1 1.000000+5 3.854300-14931 3102 277 1.300000+5 3.305100-1 1.600000+5 2.917300-1 2.000000+5 2.649200-14931 3102 278 2.400000+5 2.222300-1 3.000000+5 1.982800-1 3.700000+5 1.855300-14931 3102 279 4.500000+5 1.817800-1 5.500000+5 1.925700-1 7.000000+5 2.066100-14931 3102 280 8.500000+5 2.269000-1 1.000000+6 2.312500-1 1.300000+6 2.273900-14931 3102 281 1.600000+6 1.975300-1 2.000000+6 1.564300-1 2.400000+6 1.168100-14931 3102 282 3.000000+6 6.887000-2 5.000000+6 1.676800-2 7.000000+6 4.232000-34931 3102 283 1.000000+7 1.439400-3 1.200000+7 1.133600-3 1.500000+7 1.270000-34931 3102 284 2.000000+7 6.194800-4 0.000000+0 0.000000+0 0.000000+0 0.000000+04931 3102 285 4931 3 0 286 4931 0 0 287 4.911500+4 1.139200+2 0 0 1 04931 8 4 288 4.911500+4 3.360000+5 10 1 12 49314931 8 4 289 2.691600+2 3.000000+0 4.911500+4 9.500000-1 3.360000+5 1.000000+04931 8 4 290 2.691600+2 1.000000+0 5.011500+4 5.000000-2 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4.112500-4 4.112500-4 4.299400-4493140 4 344 4.318900-4 4.235200-4 4.218500-4 3.922700-4 4.143200-4 3.978500-4493140 4 345 4.218500-4 3.950600-4 4.017600-4 4.134800-4 4.084600-4 3.914400-4493140 4 346 3.950600-4 4.062200-4 4.452800-4 4.603500-4 4.921600-4 4.982900-4493140 4 347 2.946200-4 1.473100-4 1.355900-4 3.306200-4 3.515400-4 4.609100-4493140 4 348 1.123600-2 4.971400-4 4.829400-4 5.539600-4 4.284500-4 5.266100-4493140 4 349 5.037100-4 5.020200-4 4.770000-4 4.731800-4 4.846300-4 4.375700-4493140 4 350 4.401100-4 4.519800-4 4.452000-4 4.339600-4 4.401100-4 4.006800-4493140 4 351 3.746000-4 3.882800-4 4.045000-4 4.028000-4 2.192100-4 1.189300-4493140 4 352 1.058900-4 2.679700-4 2.849300-4 3.252100-4 4.489000-3 6.239700-4493140 4 353 4.982800-4 6.223000-4 5.362700-4 5.644100-4 5.429000-4 5.155700-4493140 4 354 4.818600-4 4.414000-4 4.036100-4 4.084300-4 4.180800-4 4.132600-4493140 4 355 4.022000-4 4.052200-4 3.677000-4 3.411600-4 3.537600-4 3.690400-4493140 4 356 3.666200-4 1.975200-4 1.061300-4 9.587700-5 2.381900-4 2.588900-4493140 4 357 2.925200-4 4.489000-3 4.803200-4 6.511100-4 5.331900-4 5.680300-4493140 4 358 5.453800-4 5.185800-4 4.818600-4 4.317500-4 3.987800-4 4.052200-4493140 4 359 4.146000-4 4.100400-4 3.991200-4 4.020000-4 3.639400-4 3.411600-4493140 4 360 3.515500-4 3.690400-4 3.666200-4 1.945700-4 1.061300-4 9.587700-5493140 4 361 2.381900-4 2.532600-4 2.925200-4 4.489000-3 4.206300-4 5.270200-4493140 4 362 4.992800-4 5.057200-4 4.793900-4 4.735600-4 4.848100-4 4.389800-4493140 4 363 4.422000-4 4.529200-4 4.470200-4 4.361000-4 4.405900-4 3.995900-4493140 4 364 3.691700-4 3.825000-4 4.003900-4 3.971800-4 2.122600-4 1.149700-4493140 4 365 1.031100-4 2.593600-4 2.757700-4 3.162400-4 7.396000-3 5.024100-4493140 4 366 5.572800-4 5.250300-4 5.108400-4 4.692200-4 4.024800-4 3.880300-4493140 4 367 3.962900-4 4.024800-4 4.024800-4 3.876900-4 3.901000-4 3.660200-4493140 4 368 3.496800-4 3.632600-4 3.808100-4 3.790900-4 1.967700-4 1.078400-4493140 4 369 9.752400-5 2.377900-4 2.528400-4 2.942900-4 2.116000-3 5.216400-4493140 4 370 5.174100-4 4.926600-4 4.791400-4 4.669900-4 4.294600-4 4.349800-4493140 4 371 4.461100-4 4.416000-4 4.284900-4 4.327700-4 3.992800-4 3.705800-4493140 4 372 3.840500-4 4.040600-4 3.985400-4 2.084700-4 1.138500-4 1.030900-4493140 4 373 2.543800-4 2.743400-4 3.094000-4 2.916000-3 5.214800-4 5.005800-4493140 4 374 4.770900-4 4.529500-4 4.199000-4 4.263800-4 4.352400-4 4.302700-4493140 4 375 4.185500-4 4.212000-4 3.780000-4 3.529400-4 3.635300-4 3.810200-4493140 4 376 3.775700-4 2.019600-4 1.087000-4 9.914400-5 2.474300-4 2.676200-4493140 4 377 3.058600-4 1.369000-3 4.928400-4 4.737100-4 4.555400-4 4.235800-4493140 4 378 4.289000-4 4.386700-4 4.342300-4 4.221000-4 4.244600-4 3.843600-4493140 4 379 3.571200-4 3.687400-4 3.862800-4 3.824300-4 2.018700-4 1.098900-4493140 4 380 9.890100-5 2.455300-4 2.641800-4 3.012500-4 2.025000-3 4.673300-4493140 4 381 4.568400-4 4.363200-4 4.449600-4 4.527900-4 4.492800-4 4.367700-4493140 4 382 4.352400-4 3.855600-4 3.591000-4 3.712500-4 3.904200-4 3.847500-4493140 4 383 2.059200-4 1.113800-4 1.008500-4 2.524100-4 2.721600-4 3.079800-4493140 4 384 9.610000-4 4.542100-4 4.389600-4 4.471400-4 4.537800-4 4.531000-4493140 4 385 4.384900-4 4.382200-4 3.966800-4 3.687100-4 3.805600-4 3.995300-4493140 4 386 3.946300-4 2.127800-4 1.135500-4 1.029500-4 2.644900-4 2.838400-4493140 4 387 3.182500-4 1.296000-3 4.553300-4 4.648300-4 4.708100-4 4.674200-4493140 4 388 4.554000-4 4.510100-4 3.971500-4 3.707300-4 3.825400-4 4.017600-4493140 4 389 3.980900-4 2.122600-4 1.140500-4 1.040000-4 2.616500-4 2.812300-4493140 4 390 3.186000-4 5.760000-4 4.659800-4 4.705000-4 4.705900-4 4.559500-4493140 4 391 4.504300-4 4.011800-4 3.721000-4 3.849100-4 4.043500-4 3.985400-4493140 4 392 2.101400-4 1.140500-4 1.030300-4 2.597500-4 2.782100-4 3.143500-4493140 4 393 5.760000-4 4.842200-4 4.838400-4 4.692000-4 4.608000-4 4.052200-4493140 4 394 3.803000-4 3.928300-4 4.129900-4 4.067500-4 2.133100-4 1.156300-4493140 4 395 1.049800-4 2.635400-4 2.822400-4 3.200200-4 6.760000-4 4.885900-4493140 4 396 4.736200-4 4.661300-4 4.142300-4 3.892700-4 4.024000-4 4.230700-4493140 4 397 4.169400-4 2.230800-4 1.201200-4 1.088100-4 2.772900-4 2.992100-4493140 4 398 3.374800-4 5.760000-4 4.725100-4 4.665600-4 4.193300-4 3.930700-4493140 4 399 4.070900-4 4.276800-4 4.213400-4 2.185900-4 1.195900-4 1.075700-4493140 4 400 2.673400-4 2.862700-4 3.256800-4 5.290000-4 4.554000-4 3.967000-4493140 4 401 3.705800-4 3.825400-4 4.024100-4 3.959200-4 2.135300-4 1.146100-4493140 4 402 1.037100-4 2.671000-4 2.859400-4 3.229700-4 5.760000-4 4.065600-4493140 4 403 3.812200-4 3.928300-4 4.112600-4 4.067500-4 2.196500-4 1.188000-4493140 4 404 1.075700-4 2.730200-4 2.923200-4 3.285100-4 7.840000-4 4.415600-4493140 4 405 4.573800-4 4.394900-4 4.415600-4 2.303800-4 1.358300-4 1.209600-4493140 4 406 2.676500-4 2.869400-4 3.237900-4 1.444000-3 4.865500-4 4.473400-4493140 4 407 4.635200-4 2.658500-4 1.630200-4 1.456900-4 2.972000-4 3.192000-4493140 4 408 3.587200-4 1.089000-3 4.573800-4 4.715000-4 2.439400-4 1.535500-4493140 4 409 1.363200-4 2.633100-4 2.799700-4 3.193100-4 1.296000-3 4.801700-4493140 4 410 2.534400-4 1.496900-4 1.331600-4 2.900900-4 3.114700-4 3.525800-4493140 4 411 1.444000-3 2.574900-4 1.642700-4 1.456900-4 2.731800-4 2.904700-4493140 4 412 3.318200-4 1.936000-3 3.760700-4 3.314500-4 4.796900-4 4.841800-4493140 4 413 4.672800-4 1.089000-3 4.205500-4 2.111700-4 1.968100-4 1.674400-4493140 4 414 7.290000-4 2.090300-4 1.950500-4 1.688600-4 6.241000-3 9.887600-4493140 4 415 7.550800-4 7.056000-3 8.127800-4 1.392400-2 0.000000+0 0.000000+0493140 4 416 493140 0 417 4931 0 0 418 0 0 0 419 5.012000+4 1.188720+2 1 0 0 05049 1451 1 0.000000+0 0.000000+0 0 0 0 65049 1451 2 1.000000+0 0.000000+0 0 0 10 65049 1451 3 0.000000+0 0.000000+0 0 0 34 35049 1451 4 50-SN-120 HEDL EVAL-OCT74 R.E.SCHENTER AND F.SCHMITTROTH 5049 1451 5 DIST-FEB90 900130 5049 1451 6 ----ENDF/B-VI MATERIAL 5049 5049 1451 7 -----INCIDENT NEUTRON DATA 5049 1451 8 ------ENDF-6 FORMAT 5049 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************5049 1451 10 ACTIVATION II 5049 1451 11 ******************************************************************5049 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 5049 1451 13 * * * * * * *5049 1451 14 FILE INFORMATION 5049 1451 15 5049 1451 16 MF=2 MT=151 RESONANCE PARAMETERS FROM NEW BNL-325 REF.(3). 5049 1451 17 5049 1451 18 MF=3 MT=102 NEUTRON CAPTURE EVALUATED USING METHODS (NCAP CODE) 5049 1451 19 IN REFS.(1,2) FOR E%EH. A 1/V COMPONENT WAS ADDED TO5049 1451 20 GIVE THE 2200M/S CROSS SECTION OF REF.(3) FOR E EH. 5049 1451 21 THE CALCULATED RESONANCE INTEGRAL AGREES(TO WITHIN 5049 1451 22 1 SIGMA) WITH THE VALUE GIVEN IN REF.(3). 5049 1451 23 5049 1451 24 REFERENCES 5049 1451 25 1. F SCHMITTROTH AND RE SCHENTER,HEDL TME 73-63(AUG 1973). 5049 1451 26 2. F SCHMITTROTH,HEDL TME 73-79(NOV 1973). 5049 1451 27 3. SF MUGHABGHAB AND DI GARBER,BNL 325,3ED,V1(JUNE 1973). 5049 1451 28 5049 1451 29 2200M/S CAPTURE CROSS SECTION,BARNS. 5049 1451 30 (FROM RESONANCE PARAMETERS) = .002 5049 1451 31 (FROM 1/V COMPONENT) = .139 5049 1451 32 TOTAL = .141 5049 1451 33 5049 1451 34 COMPUTED RESONANCE INTEGRAL = 1.249 5049 1451 35 5049 1451 36 BRANCHING RATIOES FOR (N,G) FROM HAUSER-FESHBACH CALCULATIONS 5049 1451 37 (MANN,HEDL) 5049 1451 38 1 451 41 05049 1451 39 2 151 54 05049 1451 40 3 102 18 05049 1451 41 5049 1 0 42 5049 0 0 43 5.012000+4 1.188720+2 0 0 1 05049 2151 44 5.012000+4 1.000000+0 0 0 1 05049 2151 45 1.000000-5 1.427100+4 1 1 0 05049 2151 46 0.000000+0 5.949400-1 0 0 2 05049 2151 47 1.188720+2 0.000000+0 0 0 42 75049 2151 48 9.520000+2 5.000000-1 1.900000-1 9.000000-2 1.000000-1 0.000000+05049 2151 49 3.122000+3 5.000000-1 7.700000-1 6.700000-1 1.000000-1 0.000000+05049 2151 50 7.308000+3 5.000000-1 5.667600-1 4.667600-1 1.000000-1 0.000000+05049 2151 51 8.943000+3 5.000000-1 7.752000+0 7.652000+0 1.000000-1 0.000000+05049 2151 52 1.148000+4 5.000000-1 4.032200-1 3.032200-1 1.000000-1 0.000000+05049 2151 53 1.179000+4 5.000000-1 6.972000-1 5.972000-1 1.000000-1 0.000000+05049 2151 54 1.305000+4 5.000000-1 7.157400-1 6.157400-1 1.000000-1 0.000000+05049 2151 55 1.188720+2 0.000000+0 1 0 246 415049 2151 56 6.732000+1 1.000000+0 1.000200-1 2.333300-5 1.000000-1 0.000000+05049 2151 57 1.500000+2 1.000000+0 1.000300-1 3.000000-5 1.000000-1 0.000000+05049 2151 58 3.652000+2 1.000000+0 1.016700-1 1.666700-3 1.000000-1 0.000000+05049 2151 59 4.270000+2 5.000000-1 1.110000-1 1.100000-2 1.000000-1 0.000000+05049 2151 60 9.200000+2 1.500000+0 1.110000-1 1.100000-2 1.000000-1 0.000000+05049 2151 61 1.288000+3 1.000000+0 1.100000-1 1.000000-2 1.000000-1 0.000000+05049 2151 62 1.424000+3 1.000000+0 1.140000-1 1.400000-2 1.000000-1 0.000000+05049 2151 63 1.720000+3 1.000000+0 2.033300-1 1.033300-1 1.000000-1 0.000000+05049 2151 64 2.835000+3 1.000000+0 1.213300-1 2.133300-2 1.000000-1 0.000000+05049 2151 65 3.283000+3 1.000000+0 1.019300-1 1.933300-3 1.000000-1 0.000000+05049 2151 66 3.853000+3 1.000000+0 1.633300-1 6.333300-2 1.000000-1 0.000000+05049 2151 67 4.250000+3 1.000000+0 1.233300-1 2.333300-2 1.000000-1 0.000000+05049 2151 68 4.327000+3 1.000000+0 1.173300-1 1.733300-2 1.000000-1 0.000000+05049 2151 69 4.365000+3 1.000000+0 3.666700-1 2.666700-1 1.000000-1 0.000000+05049 2151 70 5.030000+3 1.000000+0 1.500000-1 5.000000-2 1.000000-1 0.000000+05049 2151 71 5.070000+3 1.000000+0 4.900000-1 3.900000-1 1.000000-1 0.000000+05049 2151 72 5.192000+3 1.000000+0 1.451500-1 4.515300-2 1.000000-1 0.000000+05049 2151 73 6.680000+3 1.000000+0 1.593900-1 5.939300-2 1.000000-1 0.000000+05049 2151 74 6.826000+3 1.000000+0 1.110100-1 1.101300-2 1.000000-1 0.000000+05049 2151 75 6.981000+3 1.000000+0 1.590500-1 5.904700-2 1.000000-1 0.000000+05049 2151 76 7.118000+3 1.000000+0 1.315000-1 3.150000-2 1.000000-1 0.000000+05049 2151 77 7.501000+3 1.000000+0 1.681300-1 6.813300-2 1.000000-1 0.000000+05049 2151 78 8.160000+3 1.000000+0 6.690900-1 5.690900-1 1.000000-1 0.000000+05049 2151 79 8.608000+3 1.000000+0 1.767000-1 7.670000-2 1.000000-1 0.000000+05049 2151 80 8.664000+3 1.000000+0 1.459200-1 4.592000-2 1.000000-1 0.000000+05049 2151 81 9.117000+3 1.000000+0 1.350100-1 3.501300-2 1.000000-1 0.000000+05049 2151 82 9.543000+3 1.000000+0 1.240300+0 1.140300+0 1.000000-1 0.000000+05049 2151 83 1.032000+4 1.000000+0 2.787900-1 1.787900-1 1.000000-1 0.000000+05049 2151 84 1.088000+4 1.000000+0 5.311400-1 4.311400-1 1.000000-1 0.000000+05049 2151 85 1.128000+4 1.000000+0 6.551100-1 5.551100-1 1.000000-1 0.000000+05049 2151 86 1.166000+4 1.000000+0 2.000600-1 1.000600-1 1.000000-1 0.000000+05049 2151 87 1.235000+4 1.000000+0 1.400100-1 4.000700-2 1.000000-1 0.000000+05049 2151 88 1.268000+4 1.000000+0 1.315300-1 3.152700-2 1.000000-1 0.000000+05049 2151 89 1.287000+4 1.000000+0 5.303400-1 4.303400-1 1.000000-1 0.000000+05049 2151 90 1.426000+4 1.000000+0 2.066800-1 1.066800-1 1.000000-1 0.000000+05049 2151 91 1.473000+4 1.000000+0 2.642500-1 1.642500-1 1.000000-1 0.000000+05049 2151 92 1.562000+4 1.000000+0 1.200000-1 2.000000-2 1.000000-1 0.000000+05049 2151 93 1.614000+4 1.000000+0 3.974800+0 3.874800+0 1.000000-1 0.000000+05049 2151 94 1.660000+4 1.000000+0 3.535800+0 3.435800+0 1.000000-1 0.000000+05049 2151 95 1.671000+4 1.000000+0 2.740800-1 1.740800-1 1.000000-1 0.000000+05049 2151 96 1.717000+4 1.000000+0 6.604500+0 6.504500+0 1.000000-1 0.000000+05049 2151 97 5049 2 0 98 5049 0 0 99 5.012000+4 1.188720+2 0 0 0 05049 3102 100 6.172000+6 6.172000+6 0 0 1 435049 3102 101 43 5 0 0 0 05049 3102 102 1.000000-5 6.972400+0 2.530000-2 1.386200-1 1.427100+4 1.845700-45049 3102 103 1.427100+4 5.413200-2 2.000000+4 4.206000-2 5.000000+4 2.345000-25049 3102 104 1.000000+5 1.830000-2 2.000000+5 1.649000-2 3.700000+5 1.693000-25049 3102 105 7.000000+5 1.971000-2 1.000000+6 2.477000-2 1.179800+6 2.327000-25049 3102 106 1.283400+6 2.254200-2 1.312800+6 2.235000-2 1.386800+6 2.189100-25049 3102 107 1.600000+6 2.074000-2 1.885700+6 2.312900-2 2.000000+6 2.405000-25049 3102 108 2.117700+6 2.145100-2 2.208400+6 1.972600-2 2.309300+6 1.804000-25049 3102 109 2.379900+6 1.698500-2 2.420200+6 1.642500-2 2.460500+6 1.589100-25049 3102 110 2.490800+6 1.550700-2 2.510900+6 1.526000-2 2.571500+6 1.454900-25049 3102 111 2.652100+6 1.367800-2 2.672300+6 1.347200-2 2.712600+6 1.307500-25049 3102 112 2.742900+6 1.278800-2 2.763100+6 1.260100-2 2.783200+6 1.242000-25049 3102 113 2.833600+6 1.198200-2 2.860000+6 1.176200-2 2.874000+6 1.164800-25049 3102 114 3.000000+6 1.069000-2 5.000000+6 4.383000-3 7.000000+6 1.791200-35049 3102 115 1.000000+7 1.486400-3 1.200000+7 1.727700-3 1.500000+7 2.126800-35049 3102 116 2.000000+7 2.867400-3 0.000000+0 0.000000+0 0.000000+0 0.000000+05049 3102 117 5049 3 0 118 5049 0 0 119 0 0 0 120 5.012200+4 1.208560+2 1 0 0 05055 1451 1 0.000000+0 0.000000+0 0 0 0 65055 1451 2 1.000000+0 0.000000+0 0 0 10 65055 1451 3 0.000000+0 0.000000+0 0 0 34 35055 1451 4 50-SN-122 HEDL EVAL-OCT74 R.E.SCHENTER AND F.SCHMITTROTH 5055 1451 5 DIST-FEB90 900130 5055 1451 6 ----ENDF/B-VI MATERIAL 5055 5055 1451 7 -----INCIDENT NEUTRON DATA 5055 1451 8 ------ENDF-6 FORMAT 5055 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************5055 1451 10 ACTIVATION II 5055 1451 11 ******************************************************************5055 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 5055 1451 13 * * * * * * *5055 1451 14 FILE INFORMATION 5055 1451 15 5055 1451 16 MF=2 MT=151 RESONANCE PARAMETERS FROM NEW BNL-325 REF.(3). 5055 1451 17 5055 1451 18 MF=3 MT=102 NEUTRON CAPTURE EVALUATED USING METHODS (NCAP CODE) 5055 1451 19 IN REFS.(1,2) FOR E%EH. A 1/V COMPONENT WAS ADDED TO5055 1451 20 GIVE THE 2200M/S CROSS SECTION OF REF.(3) FOR E EH. 5055 1451 21 THE CALCULATED RESONANCE INTEGRAL AGREES(TO WITHIN 5055 1451 22 1 SIGMA) WITH THE VALUE GIVEN IN REF.(3). 5055 1451 23 5055 1451 24 REFERENCES 5055 1451 25 1. F SCHMITTROTH AND RE SCHENTER,HEDL TME 73-63(AUG 1973). 5055 1451 26 2. F SCHMITTROTH,HEDL TME 73-79(NOV 1973). 5055 1451 27 3. SF MUGHABGHAB AND DI GARBER,BNL 325,3ED,V1(JUNE 1973). 5055 1451 28 5055 1451 29 2200M/S CAPTURE CROSS SECTION,BARNS. 5055 1451 30 (FROM RESONANCE PARAMETERS) = .014 5055 1451 31 (FROM 1/V COMPONENT) = .167 5055 1451 32 TOTAL = .181 5055 1451 33 5055 1451 34 COMPUTED RESONANCE INTEGRAL = .766 5055 1451 35 5055 1451 36 BRANCHING RATIOES FOR (N,G) FROM HAUSER-FESHBACH CALCULATIONS 5055 1451 37 (MANN,HEDL) 5055 1451 38 1 451 41 05055 1451 39 2 151 12 05055 1451 40 3 102 15 05055 1451 41 5055 1 0 42 5055 0 0 43 5.012200+4 1.208560+2 0 0 1 05055 2151 44 5.012200+4 1.000000+0 0 0 1 05055 2151 45 1.000000-5 8.603900+3 1 1 0 05055 2151 46 0.000000+0 5.982500-1 0 0 2 05055 2151 47 1.208560+2 0.000000+0 0 0 18 35055 2151 48 1.756000+3 5.000000-1 3.500000+0 3.400000+0 1.000000-1 0.000000+05055 2151 49 5.400000+3 5.000000-1 5.100000+0 5.000000+0 1.000000-1 0.000000+05055 2151 50 6.865000+3 5.000000-1 1.910000+1 1.900000+1 1.000000-1 0.000000+05055 2151 51 1.208560+2 0.000000+0 1 0 18 35055 2151 52 1.069000+2 1.500000+0 1.003900-1 3.850000-4 1.000000-1 0.000000+05055 2151 53 2.599000+2 5.000000-1 1.017500-1 1.750000-3 1.000000-1 0.000000+05055 2151 54 3.450000+3 1.000000+0 1.800000-1 8.000000-2 1.000000-1 0.000000+05055 2151 55 5055 2 0 56 5055 0 0 57 5.012200+4 1.208560+2 0 0 0 05055 3102 58 5.946000+6 5.946000+6 0 0 1 355055 3102 59 35 5 0 0 0 05055 3102 60 1.000000-5 8.400500+0 2.530000-2 1.670100-1 8.603900+3 2.863900-45055 3102 61 8.603900+3 5.806100-2 1.000000+4 5.218000-2 2.000000+4 3.113000-25055 3102 62 5.000000+4 1.806000-2 1.000000+5 1.441000-2 2.000000+5 1.264000-25055 3102 63 3.700000+5 1.279000-2 7.000000+5 1.488000-2 1.000000+6 1.887000-25055 3102 64 1.149400+6 1.751400-2 1.252400+6 1.672700-2 1.279400+6 1.653700-25055 3102 65 1.351800+6 1.605600-2 1.600000+6 1.467000-2 2.000000+6 1.712000-25055 3102 66 2.107300+6 1.567500-2 2.157700+6 1.506200-2 2.268600+6 1.384100-25055 3102 67 2.278700+6 1.373800-2 2.359400+6 1.295400-2 2.419900+6 1.241300-25055 3102 68 2.440000+6 1.224100-2 2.510600+6 1.166500-2 2.570000+6 1.121400-25055 3102 69 2.581200+6 1.113200-2 3.000000+6 8.638000-3 5.000000+6 3.461000-35055 3102 70 7.000000+6 1.618300-3 1.000000+7 1.423300-3 1.200000+7 1.660300-35055 3102 71 1.500000+7 2.051800-3 2.000000+7 2.778100-3 0.000000+0 0.000000+05055 3102 72 5055 3 0 73 5055 0 0 74 0 0 0 75 5.012400+4 1.228410+2 1 0 0 05061 1451 1 0.000000+0 0.000000+0 0 0 0 65061 1451 2 1.000000+0 0.000000+0 0 0 10 65061 1451 3 0.000000+0 0.000000+0 0 0 34 35061 1451 4 50-SN-124 HEDL EVAL-OCT74 R.E.SCHENTER AND F.SCHMITTROTH 5061 1451 5 DIST-FEB90 900131 5061 1451 6 ----ENDF/B-VI MATERIAL 5061 5061 1451 7 -----INCIDENT NEUTRON DATA 5061 1451 8 ------ENDF-6 FORMAT 5061 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************5061 1451 10 ACTIVATION II 5061 1451 11 ******************************************************************5061 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 5061 1451 13 * * * * * * *5061 1451 14 FILE INFORMATION 5061 1451 15 5061 1451 16 MF=2 MT=151 RESONANCE PARAMETERS FROM NEW BNL-325 REF.(3). 5061 1451 17 5061 1451 18 MF=3 MT=102 NEUTRON CAPTURE EVALUATED USING METHODS (NCAP CODE) 5061 1451 19 IN REFS.(1,2) FOR E%EH. A 1/V COMPONENT WAS ADDED TO5061 1451 20 GIVE THE 2200M/S CROSS SECTION OF REF.(3) FOR E EH. 5061 1451 21 THE CALCULATED RESONANCE INTEGRAL AGREES(TO WITHIN 5061 1451 22 1 SIGMA) WITH THE VALUE GIVEN IN REF.(3). 5061 1451 23 5061 1451 24 REFERENCES 5061 1451 25 1. F SCHMITTROTH AND RE SCHENTER,HEDL TME 73-63(AUG 1973). 5061 1451 26 2. F SCHMITTROTH,HEDL TME 73-79(NOV 1973). 5061 1451 27 3. SF MUGHABGHAB AND DI GARBER,BNL 325,3ED,V1(JUNE 1973). 5061 1451 28 5061 1451 29 2200M/S CAPTURE CROSS SECTION,BARNS. 5061 1451 30 (FROM RESONANCE PARAMETERS) = .016 5061 1451 31 (FROM 1/V COMPONENT) = .118 5061 1451 32 TOTAL = .134 5061 1451 33 5061 1451 34 COMPUTED RESONANCE INTEGRAL = 7.158 5061 1451 35 5061 1451 36 BRANCHING RATIOES FOR (N,G) FROM HAUSER-FESHBACH CALCULATIONS 5061 1451 37 (MANN,HEDL) 5061 1451 38 1 451 41 05061 1451 39 2 151 11 05061 1451 40 3 102 14 05061 1451 41 5061 1 0 42 5061 0 0 43 5.012400+4 1.228410+2 0 0 1 05061 2151 44 5.012400+4 1.000000+0 0 0 1 05061 2151 45 1.000000-5 6.506700+3 1 1 0 05061 2151 46 0.000000+0 6.014900-1 0 0 2 05061 2151 47 1.228410+2 0.000000+0 0 0 12 25061 2151 48 2.380000+3 5.000000-1 2.939000+0 2.700000+0 2.390000-1 0.000000+05061 2151 49 3.390000+3 5.000000-1 1.639000+0 1.400000+0 2.390000-1 0.000000+05061 2151 50 1.228410+2 0.000000+0 1 0 18 35061 2151 51 6.200000+1 5.000000-1 2.453000-1 6.300000-3 2.390000-1 0.000000+05061 2151 52 5.790000+2 1.000000+0 2.400000-1 1.000000-3 2.390000-1 0.000000+05061 2151 53 9.500000+2 1.000000+0 2.430000-1 4.000000-3 2.390000-1 0.000000+05061 2151 54 5061 2 0 55 5061 0 0 56 5.012400+4 1.228410+2 0 0 0 05061 3102 57 5.732000+6 5.732000+6 0 0 1 325061 3102 58 32 5 0 0 0 05061 3102 59 1.000000-5 5.936500+0 2.530000-2 1.180200-1 6.506700+3 2.327300-45061 3102 60 6.506700+3 8.791600-2 1.000000+4 6.572000-2 2.000000+4 3.975000-25061 3102 61 5.000000+4 2.310000-2 1.000000+5 1.823000-2 2.000000+5 1.569000-25061 3102 62 3.700000+5 1.579000-2 7.000000+5 1.851000-2 1.000000+6 2.342000-25061 3102 63 1.320700+6 2.253900-2 1.427100+6 2.229900-2 1.467700+6 2.221300-25061 3102 64 1.548800+6 2.204900-2 1.600000+6 2.195000-2 2.000000+6 2.378000-25061 3102 65 2.127200+6 2.189600-2 2.147300+6 2.162200-2 2.228000+6 2.058000-25061 3102 66 2.349000+6 1.917400-2 2.459900+6 1.802600-2 2.470000+6 1.792700-25061 3102 67 2.480000+6 1.783100-2 3.000000+6 1.382000-2 5.000000+6 4.421000-35061 3102 68 7.000000+6 1.678700-3 1.000000+7 1.365500-3 1.200000+7 1.598300-35061 3102 69 1.500000+7 1.982500-3 2.000000+7 2.694900-3 0.000000+0 0.000000+05061 3102 70 5061 3 0 71 5061 0 0 72 0 0 0 73 5.312700+4 1.258140+2 1 0 0 05325 1451 1 0.000000+0 0.000000+0 0 0 0 65325 1451 2 1.000000+0 0.000000+0 0 0 10 65325 1451 3 0.000000+0 0.000000+0 0 0 43 45325 1451 4 53-I -127 HEDL,RCN EVAL-FEB80 SCHENTER,SCHMITTROTH, ET AL 5325 1451 5 DIST-FEB90 900131 5325 1451 6 ----ENDF/B-VI MATERIAL 5325 5325 1451 7 -----INCIDENT NEUTRON DATA 5325 1451 8 ------ENDF-6 FORMAT 5325 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************5325 1451 10 ACTIVATION II 5325 1451 11 ******************************************************************5325 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 5325 1451 13 * * * * * * *5325 1451 14 HEDL EVAL- SCHENTER,JOHNSON,MANN,SCHMITTROTH 5325 1451 15 RCN EVAL- GRUPPELAAR 5325 1451 16 5325 1451 17 FILE CONTENTS 5325 1451 18 MF=2, MT=151 RESONANCE PARAMETERS FROM BNL-325, 3RD ED. (1) 5325 1451 19 5325 1451 20 MF=3,MT=102 CAPTURE EVALUATED THROUGH USE OF FERRET (4), A 5325 1451 21 GENERALIZED LEAST SQUARES COMPUTER CODE USING WHERE 5325 1451 22 AVAILABLE DIFFERENTIAL, INTEGRAL, AND THEORETICAL DATA. 5325 1451 23 5325 1451 24 REFERENCES 5325 1451 25 1. SF MUGHABGHAB AND DI GARBER,BNL-325,3RD ED, VOL 1 (1973) 5325 1451 26 4. F SCHMITTROTH, HEDL-TME 79-40 (1979) 5325 1451 27 5. F SCHMITTROTH, HEDL TME 73-79 (1973) 5325 1451 28 5325 1451 29 I-127(N,2N) 5325 1451 30 P.C.TO NORMALIZATION AND STANDARDS SUBCOMMITTEE AUG 72 5325 1451 31 REFERENCES 5325 1451 32 M.BORMANN, ET AL., Z. PHYS. 166, 477 (1962). 5325 1451 33 H.L.MARTIN AND R.F.TACHEK, PHYS. REV., 89, 1302 (1953). 5325 1451 34 E.B.PAUL AND R.L.CLARKE, CAN. J. PHYS., 31, 367 (1953). 5325 1451 35 R.C.BARRALL,J.A.HOLMES, AND M.SILBERGELD, KIRTLAND USAF BASE, 5325 1451 36 NEW MEXICO, AFWL-TR-68-134 (1969). 5325 1451 37 R.C.BARRALL,M.SILBERGELD, AND D.G.GARDNER, NUCL. PHYS., A-138, 5325 1451 38 387 (1969). 5325 1451 39 HAVLIK, ACTA PHYSICA AUSTRIACA, 34, 209 (1971). 5325 1451 40 S.PEARLSTEIN, NUCL. SCI. ENG., 23, 238 (1965). 5325 1451 41 D.G.GARDNER, PRIVATE COMMUNICATION. 5325 1451 42 D.DEREGGE,R.DAMS, AND J.HOSTE, RADIOCHIMICA ACTA, BAND 9, HEFT 5325 1451 43 2/3, 57 (1968). 5325 1451 44 F.NASYROV, SOVIET J. ATOMIC ENERGY, 25, 1251 (1968) (ENGLISH 5325 1451 45 TRANSL.). 5325 1451 46 D.C.SANTRY ET.AL. INDC(CAN)13,2(1973) 5325 1451 47 1 451 51 05325 1451 48 2 151 85 05325 1451 49 3 16 27 05325 1451 50 3 102 24 05325 1451 51 5325 1 0 52 5325 0 0 53 5.312700+4 1.258140+2 0 0 1 05325 2151 54 5.312700+4 1.000000+0 0 0 1 05325 2151 55 1.000000-5 9.955900+2 1 1 0 05325 2151 56 2.500000+0 6.063000-1 0 0 2 05325 2151 57 1.258140+2 0.000000+0 0 0 360 605325 2151 58 2.050000+1 3.000000+0 1.212000-1 1.200000-3 1.200000-1 0.000000+05325 2151 59 3.130000+1 2.000000+0 1.428000-1 2.280000-2 1.200000-1 0.000000+05325 2151 60 3.780000+1 2.000000+0 1.740000-1 5.400000-2 1.200000-1 0.000000+05325 2151 61 4.550000+1 2.000000+0 1.476000-1 2.760000-2 1.200000-1 0.000000+05325 2151 62 6.610000+1 2.000000+0 1.228800-1 2.880000-3 1.200000-1 0.000000+05325 2151 63 7.850000+1 2.000000+0 1.620000-1 4.200000-2 1.200000-1 0.000000+05325 2151 64 9.030000+1 3.000000+0 1.431400-1 2.314300-2 1.200000-1 0.000000+05325 2151 65 1.396000+2 3.000000+0 1.757100-1 5.571400-2 1.200000-1 0.000000+05325 2151 66 1.685000+2 2.500000+0 2.370000-1 1.170000-1 1.200000-1 0.000000+05325 2151 67 1.738000+2 3.000000+0 1.222600-1 2.260000-3 1.200000-1 0.000000+05325 2151 68 1.780300+2 3.000000+0 1.208000-1 8.005700-4 1.200000-1 0.000000+05325 2151 69 1.953000+2 2.000000+0 2.460000-1 1.260000-1 1.200000-1 0.000000+05325 2151 70 2.061000+2 3.000000+0 1.495300-1 2.953300-2 1.200000-1 0.000000+05325 2151 71 2.370500+2 3.000000+0 1.543100-1 3.431200-2 1.200000-1 0.000000+05325 2151 72 2.446400+2 2.500000+0 1.309500-1 1.094900-2 1.200000-1 0.000000+05325 2151 73 2.649500+2 2.500000+0 1.558100-1 3.581000-2 1.200000-1 0.000000+05325 2151 74 2.709700+2 2.500000+0 1.265800-1 6.584500-3 1.200000-1 0.000000+05325 2151 75 2.992100+2 2.500000+0 1.321100-1 1.210800-2 1.200000-1 0.000000+05325 2151 76 3.106000+2 2.500000+0 1.376200-1 1.762400-2 1.200000-1 0.000000+05325 2151 77 3.287000+2 2.500000+0 1.225400-1 2.538200-3 1.200000-1 0.000000+05325 2151 78 3.622000+2 2.500000+0 1.257100-1 5.709500-3 1.200000-1 0.000000+05325 2151 79 3.745000+2 2.500000+0 2.438500-1 1.238500-1 1.200000-1 0.000000+05325 2151 80 3.858300+2 2.500000+0 3.301800-1 2.101800-1 1.200000-1 0.000000+05325 2151 81 4.200000+2 2.500000+0 1.433600-1 2.336300-2 1.200000-1 0.000000+05325 2151 82 4.269300+2 2.500000+0 2.253800-1 1.053800-1 1.200000-1 0.000000+05325 2151 83 4.347800+2 2.500000+0 1.637900-1 4.378800-2 1.200000-1 0.000000+05325 2151 84 4.482900+2 2.500000+0 1.665800-1 4.658000-2 1.200000-1 0.000000+05325 2151 85 4.546100+2 2.500000+0 1.210700-1 1.066100-3 1.200000-1 0.000000+05325 2151 86 4.758200+2 2.500000+0 1.287300-1 8.725300-3 1.200000-1 0.000000+05325 2151 87 4.801200+2 2.500000+0 1.322700-1 1.227100-2 1.200000-1 0.000000+05325 2151 88 4.991600+2 2.500000+0 1.579800-1 3.798100-2 1.200000-1 0.000000+05325 2151 89 5.154700+2 2.500000+0 1.586000-1 3.859700-2 1.200000-1 0.000000+05325 2151 90 5.182500+2 2.500000+0 1.564200-1 3.642400-2 1.200000-1 0.000000+05325 2151 91 5.329300+2 2.500000+0 1.961800-1 7.618100-2 1.200000-1 0.000000+05325 2151 92 5.658000+2 2.500000+0 2.532100-1 1.332100-1 1.200000-1 0.000000+05325 2151 93 5.691400+2 2.500000+0 1.390900-1 1.908500-2 1.200000-1 0.000000+05325 2151 94 5.839600+2 2.500000+0 1.224200-1 2.416500-3 1.200000-1 0.000000+05325 2151 95 6.192000+2 2.500000+0 1.772300-1 5.723300-2 1.200000-1 0.000000+05325 2151 96 6.320000+2 2.500000+0 1.541900-1 3.419000-2 1.200000-1 0.000000+05325 2151 97 6.444800+2 2.500000+0 1.291400-1 9.139200-3 1.200000-1 0.000000+05325 2151 98 6.586400+2 2.500000+0 1.251300-1 5.132800-3 1.200000-1 0.000000+05325 2151 99 6.689700+2 2.500000+0 1.634500-1 4.345200-2 1.200000-1 0.000000+05325 2151 100 7.019800+2 2.500000+0 2.180300-1 9.803100-2 1.200000-1 0.000000+05325 2151 101 7.085000+2 2.500000+0 4.127900-1 2.927900-1 1.200000-1 0.000000+05325 2151 102 7.309300+2 2.500000+0 2.173300-1 9.732900-2 1.200000-1 0.000000+05325 2151 103 7.441300+2 2.500000+0 2.782200-1 1.582200-1 1.200000-1 0.000000+05325 2151 104 7.623000+2 2.500000+0 2.967000-1 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1.540000+7 1.721800+05325 3 16 159 1.560000+7 1.735300+0 1.580000+7 1.745200+0 1.600000+7 1.750000+05325 3 16 160 1.620000+7 1.748200+0 1.640000+7 1.738600+0 1.660000+7 1.719800+05325 3 16 161 1.680000+7 1.690700+0 1.700000+7 1.650000+0 1.720000+7 1.597000+05325 3 16 162 1.740000+7 1.533600+0 1.760000+7 1.462200+0 1.780000+7 1.385200+05325 3 16 163 1.800000+7 1.305000+0 1.820000+7 1.223900+0 1.840000+7 1.143200+05325 3 16 164 1.860000+7 1.064100+0 1.880000+7 9.876400-1 1.900000+7 9.150000-15325 3 16 165 1.920000+7 8.471100-1 1.940000+7 7.841700-1 1.960000+7 7.261700-15325 3 16 166 1.980000+7 6.731100-1 2.000000+7 6.250000-1 0.000000+0 0.000000+05325 3 16 167 5325 3 0 168 5.312700+4 1.258140+2 0 0 0 05325 3102 169 6.825700+6 6.825700+6 0 0 1 615325 3102 170 61 5 0 0 0 05325 3102 171 1.000000-5 1.443500+2 2.530000-2 2.869900+0 9.955900+2 1.446700-25325 3102 172 9.955900+2 3.326700+0 1.000000+3 3.326700+0 2.000000+3 3.322400+05325 3102 173 3.000000+3 2.089700+0 5.000000+3 1.892600+0 7.000000+3 1.374500+05325 3102 174 1.000000+4 1.163500+0 2.000000+4 8.898200-1 2.400000+4 8.160500-15325 3102 175 3.000000+4 7.340400-1 5.000000+4 5.560000-1 5.805800+4 5.076300-15325 3102 176 7.000000+4 4.414600-1 7.886400+4 4.024400-1 9.676700+4 3.445000-15325 3102 177 1.000000+5 3.360200-1 1.300000+5 2.874400-1 1.392200+5 2.759500-15325 3102 178 1.600000+5 2.526200-1 2.000000+5 2.170200-1 2.044100+5 2.136400-15325 3102 179 2.400000+5 1.903000-1 3.000000+5 1.620400-1 3.700000+5 1.479800-15325 3102 180 3.779800+5 1.466200-1 4.212200+5 1.382000-1 4.500000+5 1.322200-15325 3102 181 5.500000+5 1.155800-1 6.233200+5 1.050800-1 6.336000+5 1.034300-15325 3102 182 6.561700+5 9.998300-2 7.000000+5 9.391100-2 7.222000+5 9.111300-25325 3102 183 7.505200+5 8.778000-2 8.500000+5 7.980400-2 9.988800+5 7.301400-25325 3102 184 1.000000+6 7.296900-2 1.052700+6 7.147100-2 1.103300+6 7.013000-25325 3102 185 1.132900+6 6.938400-2 1.192400+6 6.796500-2 1.228300+6 6.715500-25325 3102 186 1.239300+6 6.691400-2 1.244800+6 6.679500-2 1.284700+6 6.594900-25325 3102 187 1.300000+6 6.563500-2 1.372200+6 6.421800-2 1.373000+6 6.420300-25325 3102 188 1.600000+6 5.959900-2 2.000000+6 5.213500-2 2.400000+6 4.004700-25325 3102 189 3.000000+6 2.899700-2 5.000000+6 7.526000-3 7.000000+6 3.230200-35325 3102 190 1.000000+7 1.653100-3 1.200000+7 1.863100-3 1.500000+7 2.156800-35325 3102 191 2.000000+7 2.984400-3 0.000000+0 0.000000+0 0.000000+0 0.000000+05325 3102 192 5325 3 0 193 5325 0 0 194 0 0 0 195 5.713900+4 1.377130+2 1 0 0 05728 1451 1 0.000000+0 0.000000+0 0 0 0 65728 1451 2 1.000000+0 0.000000+0 0 0 10 65728 1451 3 0.000000+0 0.000000+0 0 0 25 35728 1451 4 57-LA-139 HEDL EVAL-FEB80 SCHENTER,SCHMITTROTH, ET AL 5728 1451 5 DIST-FEB90 900131 5728 1451 6 ----ENDF/B-VI MATERIAL 5728 5728 1451 7 -----INCIDENT NEUTRON DATA 5728 1451 8 ------ENDF-6 FORMAT 5728 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************5728 1451 10 ACTIVATION II 5728 1451 11 ******************************************************************5728 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 5728 1451 13 * * * * * * *5728 1451 14 HEDL EVAL- SCHENTER,JOHNSON,MANN,SCHMITTORTH 5728 1451 15 RCN EVAL- GRUPPELAAR 5728 1451 16 5728 1451 17 FILE CONTENTS 5728 1451 18 MF=2, MT=151 RESONANCE PARAMETERS FROM BNL-325, 3RD ED. (1) 5728 1451 19 5728 1451 20 MF=3,MT=102 CAPTURE EVALUATED THROUGH USE OF FERRET (4), A 5728 1451 21 GENERALIZED LEAST SQUARES COMPUTER CODE USING WHERE 5728 1451 22 AVAILABLE DIFFERENTIAL, INTEGRAL, AND THEORETICAL DATA. 5728 1451 23 5728 1451 24 REFERENCES 5728 1451 25 1. SF MUGHABGHAB AND DI GARBER,BNL-325,3RD ED, VOL 1 (1973) 5728 1451 26 4. F SCHMITTROTH, HEDL-TME 79-40 (1979) 5728 1451 27 5. F SCHMITTROTH, HEDL TME 73-79 (1973) 5728 1451 28 5728 1451 29 1 451 32 05728 1451 30 2 151 75 05728 1451 31 3 102 22 05728 1451 32 5728 1 0 33 5728 0 0 34 5.713900+4 1.377130+2 0 0 1 05728 2151 35 5.713900+4 1.000000+0 0 0 1 05728 2151 36 1.000000-5 9.029300+3 1 1 0 05728 2151 37 3.500000+0 6.248500-1 0 0 2 05728 2151 38 1.377130+2 0.000000+0 0 0 198 335728 2151 39 -3.750000+1 4.000000+0 6.768300-1 6.259800-1 5.085000-2 0.000000+05728 2151 40 7.217000+1 3.000000+0 9.600000-2 3.600000-2 6.000000-2 0.000000+05728 2151 41 8.748000+2 3.500000+0 8.000000-2 2.000000-2 6.000000-2 0.000000+05728 2151 42 1.179800+3 3.000000+0 2.185700+0 2.125700+0 6.000000-2 0.000000+05728 2151 43 2.116000+3 3.000000+0 3.602900+0 3.542900+0 6.000000-2 0.000000+05728 2151 44 2.149700+3 4.000000+0 9.755600-1 9.155600-1 6.000000-2 0.000000+05728 2151 45 2.379500+3 3.500000+0 1.340000-1 7.400000-2 6.000000-2 0.000000+05728 2151 46 2.467700+3 3.500000+0 9.800000-1 9.200000-1 6.000000-2 0.000000+05728 2151 47 2.854600+3 3.500000+0 4.700000-1 4.100000-1 6.000000-2 0.000000+05728 2151 48 2.997500+3 4.000000+0 1.072700+1 1.066700+1 6.000000-2 0.000000+05728 2151 49 3.286500+3 3.500000+0 1.900000+0 1.840000+0 6.000000-2 0.000000+05728 2151 50 3.481800+3 4.000000+0 1.250400+1 1.244400+1 6.000000-2 0.000000+05728 2151 51 3.726000+3 3.500000+0 2.700000-1 2.100000-1 6.000000-2 0.000000+05728 2151 52 3.749500+3 3.500000+0 5.200000+0 5.140000+0 6.000000-2 0.000000+05728 2151 53 4.356800+3 3.500000+0 5.010000+0 4.950000+0 6.000000-2 0.000000+05728 2151 54 4.646000+3 3.500000+0 3.570000+0 3.510000+0 6.000000-2 0.000000+05728 2151 55 4.810700+3 3.500000+0 2.000000-1 1.400000-1 6.000000-2 0.000000+05728 2151 56 5.347500+3 3.500000+0 1.460000+0 1.400000+0 6.000000-2 0.000000+05728 2151 57 5.517400+3 3.500000+0 2.900000-1 2.300000-1 6.000000-2 0.000000+05728 2151 58 5.517400+3 3.500000+0 2.800000-1 2.200000-1 6.000000-2 0.000000+05728 2151 59 5.827300+3 3.500000+0 1.260000+0 1.200000+0 6.000000-2 0.000000+05728 2151 60 5.973100+3 3.500000+0 4.400000-1 3.800000-1 6.000000-2 0.000000+05728 2151 61 6.455500+3 3.500000+0 4.160000+0 4.100000+0 6.000000-2 0.000000+05728 2151 62 6.552500+3 3.500000+0 1.810000+0 1.750000+0 6.000000-2 0.000000+05728 2151 63 6.856800+3 3.500000+0 3.640000+0 3.580000+0 6.000000-2 0.000000+05728 2151 64 7.128900+3 3.500000+0 3.240000+0 3.180000+0 6.000000-2 0.000000+05728 2151 65 7.432000+3 3.500000+0 3.200000-1 2.600000-1 6.000000-2 0.000000+05728 2151 66 7.457100+3 3.500000+0 2.460000+0 2.400000+0 6.000000-2 0.000000+05728 2151 67 7.894200+3 3.500000+0 3.300000-1 2.700000-1 6.000000-2 0.000000+05728 2151 68 8.020600+3 3.500000+0 2.060000+0 2.000000+0 6.000000-2 0.000000+05728 2151 69 8.060000+3 3.500000+0 4.200000-1 3.600000-1 6.000000-2 0.000000+05728 2151 70 8.514300+3 3.500000+0 5.060000+0 5.000000+0 6.000000-2 0.000000+05728 2151 71 8.903600+3 3.500000+0 7.160000+0 7.100000+0 6.000000-2 0.000000+05728 2151 72 1.377130+2 0.000000+0 1 0 216 365728 2151 73 7.340000-1 3.500000+0 4.500000-2 7.300000-8 4.500000-2 0.000000+05728 2151 74 2.438000+2 3.500000+0 6.021000-2 2.100000-4 6.000000-2 0.000000+05728 2151 75 3.393000+2 3.500000+0 6.032000-2 3.200000-4 6.000000-2 0.000000+05728 2151 76 6.171000+2 3.500000+0 8.800000-2 2.800000-2 6.000000-2 0.000000+05728 2151 77 7.019000+2 3.500000+0 6.740000-2 7.400000-3 6.000000-2 0.000000+05728 2151 78 9.042000+2 3.500000+0 6.760000-2 7.600000-3 6.000000-2 0.000000+05728 2151 79 9.620000+2 3.500000+0 7.590000-2 1.590000-2 6.000000-2 0.000000+05728 2151 80 1.207500+3 3.500000+0 7.210000-2 1.210000-2 6.000000-2 0.000000+05728 2151 81 1.255400+3 3.500000+0 7.940000-2 1.940000-2 6.000000-2 0.000000+05728 2151 82 1.425400+3 3.500000+0 6.350000-2 3.500000-3 6.000000-2 0.000000+05728 2151 83 1.431500+3 3.500000+0 6.520000-2 5.200000-3 6.000000-2 0.000000+05728 2151 84 1.634800+3 3.500000+0 8.700000-2 2.700000-2 6.000000-2 0.000000+05728 2151 85 1.649400+3 3.500000+0 7.680000-2 1.680000-2 6.000000-2 0.000000+05728 2151 86 1.824400+3 3.500000+0 6.730000-2 7.300000-3 6.000000-2 0.000000+05728 2151 87 1.915000+3 3.500000+0 7.400000-2 1.400000-2 6.000000-2 0.000000+05728 2151 88 1.969500+3 3.500000+0 6.900000-2 9.000000-3 6.000000-2 0.000000+05728 2151 89 2.175200+3 3.500000+0 8.020000-2 2.020000-2 6.000000-2 0.000000+05728 2151 90 2.663200+3 3.500000+0 1.190000-1 5.900000-2 6.000000-2 0.000000+05728 2151 91 3.420800+3 3.500000+0 7.700000-2 1.700000-2 6.000000-2 0.000000+05728 2151 92 4.271400+3 3.500000+0 1.230000-1 6.300000-2 6.000000-2 0.000000+05728 2151 93 4.611500+3 3.500000+0 1.600000-1 1.000000-1 6.000000-2 0.000000+05728 2151 94 4.729500+3 3.500000+0 1.800000-1 1.200000-1 6.000000-2 0.000000+05728 2151 95 5.177600+3 3.500000+0 1.770000-1 1.170000-1 6.000000-2 0.000000+05728 2151 96 5.839500+3 3.500000+0 2.200000-1 1.600000-1 6.000000-2 0.000000+05728 2151 97 5.854800+3 3.500000+0 2.000000-1 1.400000-1 6.000000-2 0.000000+05728 2151 98 6.329600+3 3.500000+0 1.600000-1 1.000000-1 6.000000-2 0.000000+05728 2151 99 6.982900+3 3.500000+0 5.400000-1 4.800000-1 6.000000-2 0.000000+05728 2151 100 6.983000+3 3.500000+0 3.600000-1 3.000000-1 6.000000-2 0.000000+05728 2151 101 7.047200+3 3.500000+0 1.800000-1 1.200000-1 6.000000-2 0.000000+05728 2151 102 7.087900+3 3.500000+0 3.200000-1 2.600000-1 6.000000-2 0.000000+05728 2151 103 7.541600+3 3.500000+0 2.900000-1 2.300000-1 6.000000-2 0.000000+05728 2151 104 8.165100+3 3.500000+0 2.800000-1 2.200000-1 6.000000-2 0.000000+05728 2151 105 8.350000+3 3.500000+0 5.150000-1 4.550000-1 6.000000-2 0.000000+05728 2151 106 8.661400+3 3.500000+0 5.000000-1 4.400000-1 6.000000-2 0.000000+05728 2151 107 8.670000+3 3.500000+0 2.200000-1 1.600000-1 6.000000-2 0.000000+05728 2151 108 8.812300+3 3.500000+0 2.600000-1 2.000000-1 6.000000-2 0.000000+05728 2151 109 5728 2 0 110 5728 0 0 111 5.713900+4 1.377130+2 0 0 0 05728 3102 112 5.161100+6 5.161100+6 0 0 1 565728 3102 113 56 5 0 0 0 05728 3102 114 1.000000-5 1.346000+1 2.530000-2 2.676000-1 9.029300+3 4.479400-45728 3102 115 9.029300+3 1.159800-1 1.000000+4 1.066300-1 2.000000+4 5.817000-25728 3102 116 2.400000+4 5.110100-2 3.000000+4 4.360700-2 5.000000+4 3.011600-25728 3102 117 7.000000+4 2.349300-2 1.000000+5 1.772700-2 1.300000+5 1.512800-25728 3102 118 1.600000+5 1.316200-2 1.662000+5 1.275900-2 1.978200+5 1.106700-25728 3102 119 2.000000+5 1.096800-2 2.211300+5 9.970200-3 2.400000+5 9.224200-35728 3102 120 2.495200+5 8.889700-3 3.000000+5 7.462700-3 3.700000+5 7.192200-35728 3102 121 4.500000+5 6.970100-3 5.500000+5 6.763700-3 5.741400+5 6.720300-35728 3102 122 7.000000+5 6.889200-3 8.058100+5 7.105900-3 8.500000+5 7.306000-35728 3102 123 8.561700+5 7.333500-3 1.000000+6 7.950300-3 1.027400+6 7.985400-35728 3102 124 1.077800+6 8.048000-3 1.214800+6 8.206500-3 1.225800+6 8.218600-35728 3102 125 1.227900+6 8.220900-3 1.264100+6 8.259900-3 1.300000+6 8.297700-35728 3102 126 1.391000+6 8.389700-3 1.393000+6 8.391700-3 1.430300+6 8.427900-35728 3102 127 1.431300+6 8.428800-3 1.440400+6 8.437600-3 1.449400+6 8.446100-35728 3102 128 1.485700+6 8.480200-3 1.547200+6 8.158000-3 1.569000+6 8.010800-35728 3102 129 1.570300+6 8.002200-3 1.600000+6 7.809500-3 2.000000+6 5.841900-35728 3102 130 2.400000+6 4.933100-3 3.000000+6 4.011000-3 5.000000+6 2.242800-35728 3102 131 7.000000+6 1.432700-3 1.000000+7 1.017400-3 1.200000+7 9.896701-45728 3102 132 1.500000+7 9.567600-4 2.000000+7 2.797900-3 0.000000+0 0.000000+05728 3102 133 5728 3 0 134 5728 0 0 135 0 0 0 136 6.616400+4 1.625200+2 1 0 0 06649 1451 1 0.000000+0 0.000000+0 0 0 0 66649 1451 2 1.000000+0 0.000000+0 0 0 10 66649 1451 3 0.000000+0 0.000000+0 0 0 108 36649 1451 4 66-DY-164 BNW EVAL-JUN67 B.R.LEONARD,JR. AND K.B.STEWART 6649 1451 5 PRI.COMM.JUNE,1967 DIST-FEB90 900202 6649 1451 6 ----ENDF/B-VI MATERIAL 6649 6649 1451 7 -----INCIDENT NEUTRON DATA 6649 1451 8 ------ENDF-6 FORMAT 6649 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************6649 1451 10 ACTIVATION II 6649 1451 11 ******************************************************************6649 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 6649 1451 13 * * * * * * *6649 1451 14 THIS FILE TRANSFERED FROM ENDF/B-III WITH NO MODIFICATIONS. 6649 1451 15 * * * * * * * 6649 1451 16 DATA MODIFIED JUNE,1970 TO CONFORM TO ENDF/B-II FORMATS 6649 1451 17 * * * * * * * 6649 1451 18 DYSPROSIUM-164 EVALUATION BY B.R.LEONARD AND K.B.STEWART REF.1 6649 1451 19 JUNE 1967 6649 1451 20 MF=1 GENERAL INFORMATION 6649 1451 21 MT=451 ATOMIC MASS =163.9288 I=0 REF.2 6649 1451 22 MT=453 RADIOACTIVE DECAY MT=102 REF.3 MT=103,107 REF.2 6649 1451 23 MF=2 RESONANCE PARAMETERS 6649 1451 24 MT=151 RESOLVED RESONANCE REGION DEFINED FROM 2.229 TO 272.0EV 6649 1451 25 RESONANCE PARAMETERS FROM REF.4 (-1.89EV)AND REF.5 6649 1451 26 (145.5EV). CAPTURE RESONANCE INTEGRAL=361 BARNS 6649 1451 27 (0.45 TO 272 EV) UNICORN(REF.6) CALC. 6649 1451 28 UNRESOLVED RESONANCE REGION DEFINED 272 EV TO 10 KEV 6649 1451 29 S-WAVE PARAMETERS FROM REF.7 6649 1451 30 P-WAVE PARAMETERS REF.1 6649 1451 31 NO SMOOTH CROSS SECTIONS GIVEN FOR RESONANCE REGION 6649 1451 32 MF=3 SMOOTH CROSS SECTIONS 6649 1451 33 MT=1 TOTAL CROSS SECTION 0.0001 EV TO 2.229 EV CALCULATED 6649 1451 34 BY UNICORN FROM RESONANCE PARAMETERS OF FILE 2 FOR 6649 1451 35 0 DEG.K DATA OF REFS.4,5,8,9,10 CONSIDERED. 6649 1451 36 CALCULATED SIGMA TOTAL =2909 BARNS AT 0.0253 EV. 6649 1451 37 10 TO 200 KEV REFS.11,12,13 AND OPTICAL-MODEL CALC.REF.16649 1451 38 USING ABACUS-2(REF.14) POOR FIT TO DATA OF REF.15 6649 1451 39 200 KEV TO 2.5 MEV OPTICAL-MODEL CALCULATION REF.1 6649 1451 40 2.5 TO 15 MEV EYE FIT TO DATA OF REF.16 ELEMENTAL DY. 6649 1451 41 MT=2 ELASTIC SCATTERING 0.0001 EV TO 2.229 EV FROM UNICORN 6649 1451 42 CALCULATION(REF.1).NO BRAGG EFFECTS. 6649 1451 43 10 KEV TO 20 MEV BY SUBTRACTION OF ALL OTHERS FROM TOTAL6649 1451 44 MT=4 INELASTIC SCATTERING FROM ABACUS CALCULATION REF.1 6649 1451 45 MT=16 THRESHOLDS TO 20 MEV CALCULATED 6649 1451 46 ,17 BY PEARLSTEIN REF.17 6649 1451 47 MT=102 CAPTURE 0.0001 EV TO 2.229EV CALCULATED BY UNICORN 6649 1451 48 FROM RESONANCE PARAMETERS OF FILE 2 (REF.1) 6649 1451 49 CALCULATED SIGMA CAPTURE = 2520 BARNS 0.0253 EV 6649 1451 50 10 KEV TO 20 MEV FROM SMOOTH CURVE OF REF.5 THROUGH 6649 1451 51 THE DATA OF REFS.18-21. 6649 1451 52 MT=103 N,P CONSTRUCTED TO PASS THROUGH 1.0 MB AT 14 MEV REF.22 6649 1451 53 MT=107 N,ALPHA CONSTRUCTED TO PASS THROUGH A VALUE OF 4.5 MB 6649 1451 54 AT 14.8 MEV REFS.21 AND 23. 6649 1451 55 MF=4 LEGENDRE POLYNOMIALS 6649 1451 56 MT=2 20 BY 20 TRANSFORMATION MATRIX C.M.-LAB CALCULATED REF.16649 1451 57 BY CHAD. 19 C.M. LEGENDRE COEFF 10 KEV TO 20 MEV CALC. 6649 1451 58 FROM DISTRIBUTIONS OF ABACUS BY MODIFIED VERSION OF 6649 1451 59 CHAD(REF.1). NO COMPOUND-ELASTIC FOR E OVER 5 MEV. 6649 1451 60 MF=5 SECONDARY ENERGY DISTRIBUTIONS 6649 1451 61 MT=4 INELASTIC SCATTERING THRESHOLD TO 2 MEV TO 12 LEVELS 6649 1451 62 (REF.25) FROM H.F. ABACUS CALCULATION(REF.1). 6649 1451 63 2 TO 20 MEV NUCLEAR TEMPERATURES FOR MAXWELLIAN REF.26 6649 1451 64 MT=16 NUCLEAR TEMPERATURES FOR MAXWELLIAN REF.26 6649 1451 65 ,17 THRESHOLDS TO 20 MEV. 6649 1451 66 --------- 6649 1451 67 MF=8 & 9 6649 1451 68 BRANCHING RATIOS FOR (N,G) FROM HAUSER-FESHBACH CALCULATIONS 6649 1451 69 MADE BY FRED MANN, HEDL. 6649 1451 70 REFERENCES 6649 1451 71 1. LEONARD,B.R.,STEWART,K.B.,PNL JUNE 1967 6649 1451 72 2. GOLDMAN,D.T.,CHART OF THE NUCLIDES(JUNE 1964). 6649 1451 73 3. STROMINGER,D.,HOLLANDER,J.M.,SEABORG,G.T.,R.M.P.30,585(1958).6649 1451 74 4. SHER,R.,TASSAN,S.,WEINSTOCK,E.V.,HELLSTEN,A.,NSE11,369(1961).6649 1451 75 5. BNL-325,SECOND EDITION,SUPPL.2,VOL.2C,(AUG.1966). 6649 1451 76 6. OTTER,J.M.,NAA-SR-11980,VOL.6,(JUNE 1966). 6649 1451 77 7. BELL,G.I.,LA-3463-MS(1966). 6649 1451 78 8. MOORE,W.E.,KAPL DATA CITED IN REF.5 6649 1451 79 9. BRUNNER,J.,WIDDER,F.,IAEA CONF NUCL DATA PARIS(1966). 6649 1451 80 10. OKAMOTO,K.,JAERI-1064(1964). 6649 1451 81 11. AUTHORS UNKNOWN, ANL-6580,P30(JUNE 1962). 6649 1451 82 12. HARWELL ACCEL. DATA QUOTED IN BNL-325,SEC.EDIT.SUPPL.1(1960).6649 1451 83 13. GILBOY,W.B.,TOWLE,J.H.,NUCL. PHYS.42,86(1963). 6649 1451 84 14. AUERBACH,E.H.,BNL UNPUBLISHED. 6649 1451 85 15. STUPEGIA,D.C.,ET.AL.,ANL DATA CITED IN REF.5 6649 1451 86 16. FOSTER,D.G.JR.,GLASGOW,D.W.,PNL UNPUBLISHED (1966). 6649 1451 87 17. PEARSTEIN,S.,NSE 23,238(1965)AND PRIV. COMM. (1966). 6649 1451 88 18. CHAUBEY,A.K.,SEHGAL,M.L.,NUCL. PHYS. 66,267(1965). 6649 1451 89 19. WILLE,R.G.,FINK,R.W.,PHYS. REV.118,242(1960). 6649 1451 90 20. JOHNSRUD,A.E.,SILBERT,M.G.,BARSCHALL,H.H.,PHYS.REV.116,927(596649 1451 91 21. BOOTH,R.,BALL,W.P.,MACGREGOR,M.H.,PHYS.REV.112,226(1958). 6649 1451 92 22. KENNA,B.T.,CONRAD,F.J.,SC-RR-229 (JUNE 1966). 6649 1451 93 23. KHURANA,C.S.,GOVIL,I.M.,NUCL. PHYS.69,153(1965). 6649 1451 94 24. BERLAND,R.F.,NAA-SR-11231 (DEC.1965). 6649 1451 95 25. NUCLEAR DATA SHEETS (1965). 6649 1451 96 26. WEINBERG,A.M.,WIGNER,E.P., BOOK (1958). 6649 1451 97 ***************** PROGRAM LINEAR (VERSION 89-1) *****************6649 1451 98 DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.300 PER-CENT 6649 1451 99 ***************** PROGRAM FIXUP (VERSION 89-2) ******************6649 1451 100 *RECONSTRUCTED MT NUMBERS 6649 1451 101 4 =+( 50, 91) 6649 1451 102 103 =+(600,649) 6649 1451 103 104 =+(650,699) 6649 1451 104 105 =+(700,749) 6649 1451 105 106 =+(750,799) 6649 1451 106 107 =+(800,849) 6649 1451 107 101 =+( 18, 18)+(102,116) 6649 1451 108 27 =+(101,101) 6649 1451 109 3 =+( 4, 5)+( 16, 17)+( 22, 37)+( 41, 42) 6649 1451 110 19 =+( 18, 18)-( 20, 21)-( 38, 38) 6649 1451 111 1 =+( 2, 3) 6649 1451 112 1 451 115 06649 1451 113 2 151 47 06649 1451 114 3 102 115 06649 1451 115 6649 1 0 116 6649 0 0 117 6.616400+4 1.625200+2 0 0 1 06649 2151 118 6.616400+4 1.000000+0 0 0 2 06649 2151 119 2.229000+0 2.720000+2 1 1 0 06649 2151 120 0.000000+0 8.050000-1 0 0 1 06649 2151 121 1.625200+2 0.000000+0 0 0 12 26649 2151 122 -1.890000+0 5.000000-1 1.114000-1 5.630000-2 5.510000-2 0.000000+06649 2151 123 1.455000+2 5.000000-1 8.500000-1 7.400000-1 1.100000-1 0.000000+06649 2151 124 2.720000+2 1.000000+4 2 2 0 06649 2151 125 0.000000+0 7.100000-1 0 0 2 06649 2151 126 1.625200+2 0.000000+0 0 0 1 06649 2151 127 5.000000-1 0.000000+0 2 0 66 106649 2151 128 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+06649 2151 129 2.720000+2 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 130 3.000000+2 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 131 5.000000+2 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 132 7.000000+2 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 133 1.000000+3 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 134 2.000000+3 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 135 3.000000+3 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 136 5.000000+3 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 137 7.000000+3 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 138 1.000000+4 2.000000+2 0.000000+0 4.000000-2 1.200000-1 0.000000+06649 2151 139 1.625200+2 0.000000+0 1 0 2 06649 2151 140 5.000000-1 0.000000+0 2 0 66 106649 2151 141 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+06649 2151 142 2.720000+2 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 143 3.000000+2 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 144 5.000000+2 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 145 7.000000+2 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 146 1.000000+3 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 147 2.000000+3 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 148 3.000000+3 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 149 5.000000+3 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 150 7.000000+3 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 151 1.000000+4 2.000000+2 0.000000+0 2.000000-2 1.200000-1 0.000000+06649 2151 152 1.500000+0 0.000000+0 2 0 66 106649 2151 153 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+06649 2151 154 2.720000+2 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 155 3.000000+2 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 156 5.000000+2 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 157 7.000000+2 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 158 1.000000+3 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 159 2.000000+3 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 160 3.000000+3 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 161 5.000000+3 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 162 7.000000+3 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 163 1.000000+4 1.000000+2 0.000000+0 1.000000-2 1.200000-1 0.000000+06649 2151 164 6649 2 0 165 6649 0 0 166 6.616400+4 1.625200+2 0 0 0 06649 3102 167 5.634400+6 5.634400+6 0 0 1 3356649 3102 168 335 2 0 0 0 06649 3102 169 1.000000-5 1.320000+5 1.189210-5 1.209350+5 1.354260-5 1.132490+56649 3102 170 1.492910-5 1.078070+5 1.727950-5 1.001300+5 2.000000-5 9.300000+46649 3102 171 2.242710-5 8.776410+4 2.479120-5 8.342510+4 2.954370-5 7.634170+46649 3102 172 3.369700-5 7.142660+4 3.719090-5 6.794920+4 4.312240-5 6.304780+46649 3102 173 5.000000-5 5.850000+4 5.946040-5 5.357790+4 6.771280-5 5.016010+46649 3102 174 7.464540-5 4.774060+4 8.639760-5 4.432830+4 1.000000-4 4.116000+46649 3102 175 1.095450-4 3.932560+4 1.200000-4 3.757300+4 1.400000-4 3.478500+46649 3102 176 1.600000-4 3.253700+4 1.800000-4 3.067600+4 2.000000-4 2.910100+46649 3102 177 2.200000-4 2.774600+4 2.400000-4 2.656500+4 2.600000-4 2.552200+46649 3102 178 2.800000-4 2.459300+4 3.000000-4 2.375800+4 3.200000-4 2.300400+46649 3102 179 3.400000-4 2.231600+4 3.600000-4 2.168700+4 3.800000-4 2.110800+46649 3102 180 4.000000-4 2.057300+4 4.200000-4 2.007700+4 4.400000-4 1.961500+46649 3102 181 4.600000-4 1.918400+4 4.800000-4 1.877900+4 5.000000-4 1.839900+46649 3102 182 5.200000-4 1.804200+4 5.400000-4 1.770400+4 5.600000-4 1.738500+46649 3102 183 5.800000-4 1.708200+4 6.000000-4 1.679400+4 6.200000-4 1.652100+46649 3102 184 6.400000-4 1.626000+4 6.600000-4 1.601200+4 6.800000-4 1.577400+46649 3102 185 7.000000-4 1.554700+4 7.200000-4 1.532900+4 7.400000-4 1.512000+46649 3102 186 7.600000-4 1.492000+4 7.800000-4 1.472700+4 8.000000-4 1.454100+46649 3102 187 8.200000-4 1.436300+4 8.400000-4 1.419000+4 8.600000-4 1.402400+46649 3102 188 8.800000-4 1.386300+4 9.000000-4 1.370800+4 9.200000-4 1.355800+46649 3102 189 9.400000-4 1.341300+4 9.600000-4 1.327200+4 9.800000-4 1.313600+46649 3102 190 1.000000-3 1.300300+4 1.095450-3 1.242250+4 1.200000-3 1.186800+46649 3102 191 1.400000-3 1.098500+4 1.600000-3 1.027400+4 1.800000-3 9.683901+36649 3102 192 2.000000-3 9.185000+3 2.200000-3 8.755701+3 2.400000-3 8.381201+36649 3102 193 2.522290-3 8.174400+3 2.600000-3 8.050701+3 2.800000-3 7.756201+36649 3102 194 3.000000-3 7.491600+3 3.200000-3 7.252201+3 3.400000-3 7.034100+36649 3102 195 3.600000-3 6.834500+3 3.800000-3 6.650800+3 4.000000-3 6.481000+36649 3102 196 4.200000-3 6.323500+3 4.400000-3 6.176800+3 4.600000-3 6.039800+36649 3102 197 4.800000-3 5.911400+3 5.000000-3 5.790700+3 5.200000-3 5.677000+36649 3102 198 5.400000-3 5.569700+3 5.600000-3 5.468200+3 5.800000-3 5.372000+36649 3102 199 6.000000-3 5.280600+3 6.200000-3 5.193600+3 6.400000-3 5.110700+36649 3102 200 6.600000-3 5.031600+3 6.800000-3 4.956000+3 6.856560-3 4.935300+36649 3102 201 7.000000-3 4.883700+3 7.200000-3 4.814400+3 7.400000-3 4.747900+36649 3102 202 7.600000-3 4.684000+3 7.800000-3 4.622600+3 8.000000-3 4.563500+36649 3102 203 8.200000-3 4.506500+3 8.400000-3 4.451600+3 8.600000-3 4.398600+36649 3102 204 8.800000-3 4.347400+3 9.000000-3 4.298000+3 9.200000-3 4.250100+36649 3102 205 9.400000-3 4.203700+3 9.600000-3 4.158800+3 9.800000-3 4.115300+36649 3102 206 1.000000-2 4.073100+3 1.086540-2 3.904000+3 1.200000-2 3.710400+36649 3102 207 1.400000-2 3.427900+3 1.465000-2 3.348700+3 1.600000-2 3.199800+36649 3102 208 1.800000-2 3.010500+3 1.828240-2 2.986200+3 2.000000-2 2.850000+36649 3102 209 2.181820-2 2.723500+3 2.200000-2 2.711700+3 2.400000-2 2.590800+36649 3102 210 2.530000-2 2.520000+3 2.600000-2 2.484000+3 2.800000-2 2.388600+36649 3102 211 2.878180-2 2.354000+3 3.000000-2 2.302800+3 3.200000-2 2.225100+36649 3102 212 3.231760-2 2.213400+3 3.400000-2 2.154100+3 3.595000-2 2.090700+36649 3102 213 3.600000-2 2.089100+3 3.800000-2 2.029200+3 3.973460-2 1.980800+36649 3102 214 4.000000-2 1.973700+3 4.200000-2 1.922100+3 4.374340-2 1.880100+36649 3102 215 4.400000-2 1.874100+3 4.600000-2 1.829100+3 4.800000-2 1.786900+36649 3102 216 4.807770-2 1.785300+3 5.000000-2 1.747200+3 5.200000-2 1.709700+36649 3102 217 5.288940-2 1.693700+3 5.400000-2 1.674300+3 5.600000-2 1.640700+36649 3102 218 5.800000-2 1.608900+3 5.844380-2 1.602000+3 6.000000-2 1.578600+36649 3102 219 6.200000-2 1.549800+3 6.400000-2 1.522200+3 6.600000-2 1.495900+36649 3102 220 6.800000-2 1.470800+3 7.000000-2 1.446600+3 7.200000-2 1.423500+36649 3102 221 7.400000-2 1.401300+3 7.600000-2 1.379900+3 7.800000-2 1.359300+36649 3102 222 8.000000-2 1.339500+3 8.200000-2 1.320400+3 8.400000-2 1.301900+36649 3102 223 8.600000-2 1.284100+3 8.800000-2 1.266800+3 9.000000-2 1.250200+36649 3102 224 9.200000-2 1.234000+3 9.400000-2 1.218300+3 9.600000-2 1.203200+36649 3102 225 9.800000-2 1.188400+3 9.805030-2 1.188100+3 1.000000-1 1.174100+36649 3102 226 1.086630-1 1.116600+3 1.198760-1 1.051300+3 1.200000-1 1.050600+36649 3102 227 1.320000-1 9.898600+2 1.400000-1 9.536000+2 1.453070-1 9.311500+26649 3102 228 1.600000-1 8.746900+2 1.600820-1 8.744000+2 1.766400-1 8.191200+26649 3102 229 1.800000-1 8.088100+2 1.953550-1 7.649800+2 2.000000-1 7.526900+26649 3102 230 2.166730-1 7.117500+2 2.200000-1 7.041300+2 2.400000-1 6.615500+26649 3102 231 2.411410-1 6.592800+2 2.600000-1 6.238300+2 2.694370-1 6.074700+26649 3102 232 2.800000-1 5.901100+2 3.000000-1 5.597400+2 3.024020-1 5.562900+26649 3102 233 3.200000-1 5.322000+2 3.400000-1 5.071000+2 3.412080-1 5.056500+26649 3102 234 3.600000-1 4.840900+2 3.800000-1 4.629200+2 3.871250-1 4.557700+26649 3102 235 4.000000-1 4.433500+2 4.200000-1 4.252100+2 4.400000-1 4.083400+26649 3102 236 4.419240-1 4.067700+2 4.600000-1 3.925900+2 4.800000-1 3.778700+26649 3102 237 5.000000-1 3.640700+2 5.079380-1 3.588300+2 5.200000-1 3.511000+26649 3102 238 5.400000-1 3.388900+2 5.600000-1 3.273800+2 5.800000-1 3.165000+26649 3102 239 5.882540-1 3.121800+2 6.000000-1 3.062000+2 6.200000-1 2.964400+26649 3102 240 6.400000-1 2.871800+2 6.600000-1 2.783800+2 6.800000-1 2.700100+26649 3102 241 6.870460-1 2.671500+2 7.000000-1 2.620300+2 7.200000-1 2.544200+26649 3102 242 7.400000-1 2.471600+2 7.600000-1 2.402200+2 7.800000-1 2.335800+26649 3102 243 8.000000-1 2.272300+2 8.100030-1 2.241500+2 8.200000-1 2.211400+26649 3102 244 8.400000-1 2.153100+2 8.600000-1 2.097100+2 8.800000-1 2.043300+26649 3102 245 9.000000-1 1.991600+2 9.200000-1 1.941900+2 9.400000-1 1.894100+26649 3102 246 9.600000-1 1.848100+2 9.650530-1 1.836700+2 9.800000-1 1.803800+26649 3102 247 1.000000+0 1.761000+2 1.078888+0 1.604440+2 1.164000+0 1.461800+26649 3102 248 1.200000+0 1.406300+2 1.296148+0 1.270990+2 1.400000+0 1.148700+26649 3102 249 1.422590+0 1.124000+2 1.508690+0 1.036030+2 1.600000+0 9.549400+16649 3102 250 1.680562+0 8.897070+1 1.765180+0 8.289300+1 1.800000+0 8.054700+16649 3102 251 1.897367+0 7.442380+1 2.000000+0 6.876600+1 2.097618+0 6.386750+16649 3102 252 2.200000+0 5.931800+1 2.229000+0 5.810000+1 2.229000+0 0.000000+06649 3102 253 1.000000+4 0.000000+0 1.000000+4 3.000000-1 1.189207+4 2.837220-16649 3102 254 1.354256+4 2.720970-1 1.645755+4 2.555450-1 2.000000+4 2.400000-16649 3102 255 2.449490+4 2.271560-1 3.000000+4 2.150000-1 3.464101+4 2.073640-16649 3102 256 4.000000+4 2.000000-1 5.000000+4 1.910000-1 6.000000+4 1.850000-16649 3102 257 7.000000+4 1.800000-1 8.000000+4 1.750000-1 9.000000+4 1.710000-16649 3102 258 1.000000+5 1.690000-1 1.100000+5 1.680000-1 1.200000+5 1.660000-16649 3102 259 1.400000+5 1.630000-1 1.500000+5 1.620000-1 1.600000+5 1.610000-16649 3102 260 1.800000+5 1.600000-1 2.000000+5 1.600000-1 2.500000+5 1.690000-16649 3102 261 3.000000+5 1.940000-1 3.500000+5 1.980000-1 3.741657+5 1.877340-16649 3102 262 4.000000+5 1.780000-1 4.229485+5 1.606150-1 4.410198+5 1.487000-16649 3102 263 4.695848+5 1.324630-1 5.000000+5 1.180000-1 5.477225+5 1.113100-16649 3102 264 6.000000+5 1.050000-1 7.000000+5 1.140000-1 8.000000+5 1.200000-16649 3102 265 9.000000+5 1.200000-1 1.000000+6 1.190000-1 1.100000+6 1.180000-16649 3102 266 1.200000+6 1.150000-1 1.300000+6 1.120000-1 1.400000+6 1.100000-16649 3102 267 1.500000+6 1.080000-1 1.600000+6 1.050000-1 1.700000+6 1.020000-16649 3102 268 1.800000+6 1.000000-1 1.900000+6 9.600000-2 2.000000+6 9.300000-26649 3102 269 2.236068+6 8.462270-2 2.500000+6 7.700000-2 2.738613+6 6.964910-26649 3102 270 3.000000+6 6.300000-2 3.240370+6 5.778410-2 3.500000+6 5.300000-26649 3102 271 3.741657+6 4.883650-2 4.000000+6 4.500000-2 4.242640+6 4.189270-26649 3102 272 4.500000+6 3.900000-2 4.743416+6 3.668110-2 5.000000+6 3.450000-26649 3102 273 5.244044+6 3.217140-2 5.500000+6 3.000000-2 6.000000+6 2.700000-26649 3102 274 6.500000+6 2.450000-2 7.000000+6 2.200000-2 7.500000+6 2.000000-26649 3102 275 8.000000+6 1.820000-2 8.500000+6 1.700000-2 9.000000+6 1.590000-26649 3102 276 9.500000+6 1.480000-2 1.000000+7 1.360000-2 1.048809+7 1.277500-26649 3102 277 1.100000+7 1.200000-2 1.148913+7 1.122500-2 1.200000+7 1.050000-26649 3102 278 1.300000+7 9.500000-3 1.400000+7 8.500000-3 1.500000+7 8.000000-36649 3102 279 1.600000+7 7.100000-3 1.700000+7 6.600000-3 1.800000+7 6.100000-36649 3102 280 1.900000+7 5.700000-3 2.000000+7 5.300000-3 0.000000+0 0.000000+06649 3102 281 6649 3 0 282 6649 0 0 283 0 0 0 284 7.318100+4 1.794000+2 1 0 0 07328 1451 1 0.000000+0 0.000000+0 0 0 0 67328 1451 2 1.000000+0 0.000000+0 0 0 10 67328 1451 3 0.000000+0 0.000000+0 0 0 254 57328 1451 4 73-TA-181 LLNL EVAL-JAN72 HOWERTON, PERKINS, MACGREGOR 7328 1451 5 DIST-FEB90 900201 7328 1451 6 ----ENDF/B-VI MATERIAL 7328 7328 1451 7 -----INCIDENT NEUTRON DATA 7328 1451 8 ------ENDF-6 FORMAT 7328 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************7328 1451 10 ACTIVATION II 7328 1451 11 ******************************************************************7328 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 7328 1451 13 * * * * * * *7328 1451 14 7328 1451 15 *** DNA 4179 MOD 3 WITH ENDF/B-III RESONANCE PARAMETERS ******* 7328 1451 16 *************************************************************** 7328 1451 17 7328 1451 18 TA-181 EVALUATED NEUTRON CROSS SECTIONS 7328 1451 19 R.J.HOWERTON, S.T.PERKINS, R.C.HAIGHT AND M.H. MACGREGOR 7328 1451 20 LAWRENCE LIVERMORE LABORATORY, LIVERMORE, CALIFORNIA 7328 1451 21 7328 1451 22 GENERAL COMMENTS 7328 1451 23 THE NEUTRON ENERGY RANGE EXTENDS FROM .00001 EV TO 20 MEV. IN7328 1451 24 ADDITION TO ELASTIC SCATTERING, WHICH OCCURS AT ALL ENERGIES, THE 7328 1451 25 FOLLOWING REACTIONS HAVE THRESHOLD (UCRL-50400, VOL. 9) ENERGIES 7328 1451 26 LESS THAN 20 MEV. 7328 1451 27 7328 1451 28 REACTION THRESHOLD (MEV) 7328 1451 29 N,N* 0.00623 7328 1451 30 N,2N 7.69 7328 1451 31 N,3N 14.30 7328 1451 32 N,P 0.24 7328 1451 33 N,NP 5.97 7328 1451 34 N,D 3.73 7328 1451 35 N,ND 11.16 7328 1451 36 N,T 4.87 7328 1451 37 N,NT 11.00 7328 1451 38 N,HE3 6.20 7328 1451 39 N,NHE3 13.24 7328 1451 40 N,ALPHA EXOERGIC (Q = 7.41) 7328 1451 41 N,N ALPHA EXOERGIC (Q = 1.53) 7328 1451 42 N,GAMMA EXOERGIC (Q = 6.06) 7328 1451 43 ALL CHARGED PARTICLE PRODUCING REACTIONS, EXCEPT THE (N,P) 7328 1451 44 PROCESS WILL BE NEGLECTED AS THERE ARE ESSENTIALLY NO MEASURE- 7328 1451 45 MENTS. THE CROSS SECTIONS FOR (N,N), (N,N*), (N,2N), (N,3N), 7328 1451 46 (N,P), (N,GAMMA), AND (N,X GAMMA) REACTIONS ARE DISCUSSED BELOW, 7328 1451 47 AS ARE THE SECONDARY NEUTRON ANGULAR AND ENERGY DISTRIBUTIONS FOR 7328 1451 48 THESE REACTIONS. DISCUSSIONS ARE ALSO INCLUDED FOR PHOTON AND 7328 1451 49 ELECTRON PRODUCTION CROSS SECTIONS, MULTIPLICITIES, ENERGY DIST- 7328 1451 50 RIBUTIONS, AND ANGULAR DISTRIBUTIONS. TO PROVIDE A MECHANISM FOR 7328 1451 51 ENTERING ELECTRON PRODUCTION DATA INTO THE ENDF/B FORMAT, FILES 7328 1451 52 32, 33, 34, AND 35 WERE DEFINED EXACTLY ANALAGOUS TO FILES 12, 13,7328 1451 53 14, AND 15. FOR DOCUMENTATION SEE LA-4549 (ENDF-102, REV., VOL. 7328 1451 54 II) AND READ ELECTRON FOR PHOTON IN THAT REFERENCE. 7328 1451 55 THE DATA BASE FOR THE EVALUATION IS GIVEN IN UCRL-50400, 7328 1451 56 VOL. 2 AND 3. REFERENCES NOT SPECIFICALLY CITED HERE ARE GIVEN IN 7328 1451 57 THESE TWO VOLUMES. 7328 1451 58 7328 1451 59 7328 1451 60 MF = 2 7328 1451 61 ENDF/B-III RESOLVED AND UNRESOLVED RESONANCE PARAMETERS HAVE BEEN7328 1451 62 MARRIED ONTO THIS EVALUATION BELOW 5KEV (MAT-1126). 7328 1451 63 7328 1451 64 NEUTRON CROSS SECTIONS 7328 1451 65 7328 1451 66 ELASTIC SCATTERING CROSS SECTION 7328 1451 67 MF = 3 MT = 2 7328 1451 68 THE ELASTIC SCATTERING CROSS SECTIONS IS EQUAL TO 6.25 BARNS 7328 1451 69 AT 0.0253 EV, THE DIFFERENCE BETWEEN THE TOTAL AND N,GAMMA CROSS 7328 1451 70 SECTIONS, AND IS ESSENTIALLY CONSTANT OVER THE THERMAL ENERGY 7328 1451 71 REGION. IN THE RESOLVED RESONANCE REGION, UP TO ABOUT 300 EV, THE 7328 1451 72 CROSS SECTION WAS DETERMINED FROM A SINGLE LEVEL ANALYSIS FOR 7328 1451 73 ZERO DEGREES KELVIN MATERIAL TEMPERATURE. THE PARAMETERS USED 7328 1451 74 WERE THE RECOMMENDED SET IN BNL-325, SUPPL. 2, VOL. IIC (1966). 7328 1451 75 AT HIGHER ENERGIES, THE ELASTIC SCATTERING CROSS SECTION WAS 7328 1451 76 TAKEN AS THE DIFFERENCE BETWEEN THE TOTAL AND THE NONELASTIC CROSS7328 1451 77 SECTION. THE NONELASTIC WAS DERIVED FROM THE SUM OF ITS PARTS 7328 1451 78 WHERE DATA WERE AVAILABLE, FROM MEASUREMENTS OF THE NONELASTIC C/S7328 1451 79 WHERE AVAILABLE AND OTHERWISE FROM SYSTEMATICS. 7328 1451 80 7328 1451 81 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS, 7328 1451 82 MF = 4 MT = 2 7328 1451 83 NORMALIZED PROBABILITIES 7328 1451 84 THE ELASTIC SCATTERING WAS ASSUMED TO BE ISOTROPIC IN THE 7328 1451 85 CENTER OF MASS SYSTEM FOR ENERGIES LESS THAN 50 KEV. FROM 50 KEV 7328 1451 86 TO 14.6 MEV THE EVALUATIONS WERE BASED ON EXPERIMENTAL DATA WHERE 7328 1451 87 SUCH DATA EXIST. FOR ENERGIES EQUAL TO OR GREATER THAN ONE MEV 7328 1451 88 OPTICAL MODEL CALCULATIONS WERE DONE TO OBTAIN AN ESTIMATE OF THE 7328 1451 89 INELASTIC SCATTERING TO LOW LYING LEVELS INCLUDED IN THE EXPERI- 7328 1451 90 MENTAL RESULTS. TO PROVIDE A REASONABLE NUMBER OF ANGULAR DISTRI-7328 1451 91 BUTIONS, OPTICAL MODEL CALCULATIONS WERE USED AT INTERMEDIATE 7328 1451 92 ENERGIES AND FOR ENERGIES GREATER THAN 14.6 MEV. THE OPTICAL 7328 1451 93 MODEL RESULTS AGREED VERY WELL WITH THE EXPERIMENTS EXCEPT AT THE 7328 1451 94 MINIMA WHERE ONE WOULD EXPECT THE LOW LYING LEVEL EXCITATIONS 7328 1451 95 TO CAUSE A FILLING OF THE MINIMA. THE WICK LIMIT WAS TESTED 7328 1451 96 AGAINST ALL DISTRIBUTIONS AND IT WAS FOUND THAT THE CRITERION WAS 7328 1451 97 MET. 7328 1451 98 7328 1451 99 INELASTIC SCATTERING CROSS SECTION 7328 1451 100 MF = 3 MT = 51-60 AND 91 7328 1451 101 THE EXCITATION FUNCTION FOR THE 6 KEV LEVEL WAS BASED ON 7328 1451 102 CALCULATIONS DONE BY DONALD GARDNER USING THE COMNUC CODE. 7328 1451 103 THE EXCITATION FUNCTIONS FOR THE NEXT 9 LEVELS WERE OBTAINED 7328 1451 104 FROM REF. 885 AND FROM RECENT ORNL DATA (DICKENS AND MORGAN 7328 1451 105 (1973)). THE RESULTS WERE SMOOTHLY EXTRAPOLATED TO 10 MB AT 7328 1451 106 2-4 MEV AND KEPT CONSTANT TO 20 MEV. 7328 1451 107 THE TOTAL INELASTIC CROSS SECTION WAS BASED ON INDIVIDUAL 7328 1451 108 LEVEL DATA AT ENERGIES OF THE ORDER OF ONE MEV. FROM 1 TO 20 7328 1451 109 MEV THERE ARE FEW MEASUREMENTS AND THE EXCITATION FUNCTION WAS 7328 1451 110 ESTIMATED FROM NUCLEAR SYSTEMATICS. THE DIFFERENCE BETWEEN THE 7328 1451 111 TOTAL INELASTIC AND THE LEVEL DATA WAS ASSIGNED TO THE INELASTIC 7328 1451 112 CONTINUUM CROSS SECTION. THE EXPERIMENT REPORTED IN REF. 885 7328 1451 113 COULD NOT RESOLVE CERTAIN DOUBLETS SO A MEAN ENERGY WAS ASSIGNED 7328 1451 114 WHICH, OF COURSE, DIFFERS FROM THE ENERGIES PRESENTED IN ALL 7328 1451 115 TABULATIONS OF LEVELS OR LEVEL DIAGRAMS FOR TA-181. 7328 1451 116 7328 1451 117 INELASTIC SCATTERING ANGULAR DISTRIBUTIONS, 7328 1451 118 MF = 4 MT = 51-60 AND 91 7328 1451 119 NORMALIZED PROBABILITIES 7328 1451 120 THE LEVEL DATA WERE ASSUMED ISOTROPIC IN THE CENTER OF MASS 7328 1451 121 SYSTEM AND THE CONTINUUM COMPONENT WAS ASSUMED ISOTROPIC IN THE 7328 1451 122 LABORATORY SYSTEM FOR ENERGIES LESS THAN 8.0 MEV. FOR HIGHER 7328 1451 123 ENERGIES THE DISTRIBUTIONS WERE PEAKED FORWARD. 7328 1451 124 7328 1451 125 INELASTIC SCATTERING ENERGY DISTRIBUTIONS 7328 1451 126 MF = 5 MT = 91 7328 1451 127 THE CONTINUUM INELASTIC SCATTERING ENERGY DISTRIBUTION IS 7328 1451 128 COMPOSED OF AN EVAPORATION COMPONENT PLUS A HIGH ENERGY PRE- 7328 1451 129 EQUILIBRIUM COMPONENT. THIS LATTER PORTION DECREASES WITH INCREAS-7328 1451 130 ING SECONDARY ENERGY AND ITS CONTRIBUTION INCREASES WITH THE 7328 1451 131 INCIDENT NEUTRON ENERGY. THE EVAPORATION TEMPERATURE WAS ASSUMED 7328 1451 132 TO VARY AS THE SQUARE ROOT OF THE INCIDENT NEUTRON ENERGY. 7328 1451 133 IN THE DETAILED EVALUATION, A SEPARATION WAS MADE INTO NEUTRONS 7328 1451 134 WITH INCIDENT ENERGIES ABOVE THE (N,2N) THRESHOLD, AND THOSE WITH 7328 1451 135 ENERGIES BELOW. THE FORMER WERE ASSUMED TO EMIT PRIMARILY HIGH 7328 1451 136 ENERGY NEUTRONS IN THE (N,N*) REACTION. 7328 1451 137 7328 1451 138 (N,2N) CROSS SECTION 7328 1451 139 MF = 3 MT = 16 7328 1451 140 THE (N,2N) CROSS SECTION NEAR THRESHOLD WAS DETERMINED FROM 7328 1451 141 THE OBSERVED DIP IN GAMMA RAY PRODUCTION (OAK RIDGE REPORT ORNL- 7328 1451 142 TM-3702,FEB,1972), USING THE FORMALISM OF HOWERTON AND PLECHATY 7328 1451 143 (NUCL.SCI.ENG.32,178(1968)). THE OVERALL SHAPE FOR THE EXCITATION 7328 1451 144 FUNCTION WAS SET EQUAL TO THAT OF U238, WITH SUITABLE ADJUSTMENTS 7328 1451 145 TO MATCH THE SYSTEMATICS OF TANTALUM. 7328 1451 146 (N,2N) ENERGY DISTRIBUTIONS 7328 1451 147 MF = 5 MT = 16 7328 1451 148 THE FORMALISM OF THE TEMPERATURE MODEL WAS USED FOR CONVENI- 7328 1451 149 ENCE IN THE ABSENCE OF MEASUREMENT. 7328 1451 150 7328 1451 151 (N,3N) CROSS SECTION 7328 1451 152 MF = 3 MT = 17 7328 1451 153 THE (N,3N) EXCITATION FUNCTION WAS BASED ON THE DIFFERENCE 7328 1451 154 BETWEEN A CONSTANT NONELASTIC CROSS SECTION OF 2.45 BARNS AND THE 7328 1451 155 SUM OF THE INELASTIC AND (N,2N) CROSS SECTIONS. 7328 1451 156 7328 1451 157 (N,3N) ENERGY DISTRIBUTIONS 7328 1451 158 MF = 5 MT = 17 7328 1451 159 THE FORMALISM OF THE TEMPERATURE MODEL WAS USED FOR CONVENI- 7328 1451 160 ENCE IN THE ABSENCE OF MEASUREMENT. 7328 1451 161 7328 1451 162 (N,P) CROSS SECTION 7328 1451 163 MF = 3 MT = 103 7328 1451 164 THE (N,P) CROSS SECTION WAS BASED ON THE DATA OF REF. 2887, 7328 1451 165 WITH SMOOTH EXTRAPOLATIONS TO THRESHOLD AND TO 20 MEV. 7328 1451 166 7328 1451 167 (N,GAMMA) CROSS SECTION 7328 1451 168 MF = 3 MT - 102 7328 1451 169 THE (N,GAMMA) CROSS SECTION IS EQUAL TO 21.9 BARNS AT 7328 1451 170 .0253 EV AND IS 1/V OVER THE THERMAL REGION. IN THE RESOLVED 7328 1451 171 RESONANCE REGION, THE CROSS SECTION (AT ZERO DEGREES KELVIN) WAS 7328 1451 172 OBTAINED FROM A SINGLE LEVEL ANALYSIS - SEE SECTION UNDER ELASTIC 7328 1451 173 SCATTERING CROSS SECTION. 7328 1451 174 FROM ABOUT 300 EV TO 10 KEV, THE LEAD SLOWING-DOWN-TIME 7328 1451 175 SPECTROMETER DATA OF REF. 1960 WAS USED. THIS WAS MERGED SMOOTH- 7328 1451 176 LY INTO THE RELATIVELY LARGE AMOUNT OF DATA AVAILABLE FOR ENERGIES7328 1451 177 BELOW 5 MEV, AND SMOOTHLY EXTRAPOLATED TO 20 MEV. 7328 1451 178 7328 1451 179 GAMMA RAY PRODUCTION CROSS SECTIONS 7328 1451 180 7328 1451 181 (N,X GAMMA) CROSS SECTION FROM THE 7328 1451 182 (N,GAMMA) REACTION 7328 1451 183 MF = 12 MT = 102 7328 1451 184 THE MULTIPLICITY FOR GAMMA RAYS, M(E), FROM THE (N,GAMMA) 7328 1451 185 REACTION WAS OBTAINED BELOW 35 KEV NEUTRON ENERGY BY NORMAL- 7328 1451 186 IZING THE SPECTRAL SHAPES TO THE BINDING ENERGY (BE) PLUS THE 7328 1451 187 NEUTRON ENERGY E MINUS THE ENERGY DIVERTED BY INTERNAL CONVER- 7328 1451 188 SION. ABOVE 35 KEV, THIS CROSS SECTION IS INCLUDED IN THE 7328 1451 189 (N,XGAMMA) CROSS SECTION. NOTE THAT THE ASSUMED ENERGY VARIATION 7328 1451 190 OF THE MULTIPLICITY CONSERVES ENERGY FOR THE REACTION WITH 7328 1451 191 THE ENERGY DISTRIBUTION DESCRIBED BELOW. 7328 1451 192 7328 1451 193 (N,X GAMMA) ENERGY DISTRIBUTION FROM 7328 1451 194 THE (N,GAMMA) REACTION 7328 1451 195 MF = 15 MT = 102 7328 1451 196 THE DISTRIBUTIONS ARE EXPRESSED AS NORMALIZED PROBA- 7328 1451 197 BILITY DISTRIBUTIONS. 7328 1451 198 AT (10**(-11)) MEV NEUTRON ENERGY, THIS ENERGY DISTRIBUTION 7328 1451 199 WAS TAKEN TO BE THAT OF REF. 2415 FOR PHOTONS BETWEEN 2.5 AND 7328 1451 200 5. MEV. ABOVE 5. MEV THE THERMAL CAPTURE DATA OF REF. 3211 7328 1451 201 WERE USED AFTER HAVING BEEN NORMALIZED TO REF. 2415. BELOW 7328 1451 202 0.5 MEV PHOTON ENERGY, THE DATA OF REF. 3211 WERE USED, NORMAL- 7328 1451 203 IZED AT 402 KEV TO REF. 2415. THE PRODUCTION OF K AND L X-RAYS 7328 1451 204 FOLLOWING INTERNAL CONVERSION WAS TAKEN FROM THE INTERNAL 7328 1451 205 CONVERSION CROSS SECTIONS DISCUSSED BELOW. A FLOURESCENCE YIELD 7328 1451 206 OF 100 WAS ASSUMED FOR EACH K AND L VACANCY. BETWEEN 0.5 AND 7328 1451 207 2.5 MEV, THE ENERGY DISTRIBUTION WAS TAKEN FROM A GAMMA 7328 1451 208 CASCADE CALCULATION. 7328 1451 209 AT 2 KEV NEUTRON ENERGY THE SAME PROCEDURE WAS FOLLOWED 7328 1451 210 EXCEPT THAT THE 2 KEV DATA OF REF. 3211 WAS USED FOR THE 7328 1451 211 PHOTON ENERGIES ABOVE 5. MEV. AT 35 KEV NEUTRON ENERGY THE 7328 1451 212 ENERGY DISTRIBUTION WAS ASSUMED TO BE THE SAME AS AT 2 KEV. 7328 1451 213 7328 1451 214 (N,X GAMMA) CROSS SECTION 7328 1451 215 MF = 13 MT = 3 7328 1451 216 THIS COMPONENT INCLUDES ALL GAMMA RAYS EXCEPT THOSE FROM THE 7328 1451 217 CAPTURE PROCESS DISCUSSED ABOVE. FOUR DISCRETE LINES WERE 7328 1451 218 ENTERED EXPLICITLY. THE MEASUREMENTS OF DICKENS AND MORGAN (1973),7328 1451 219 LARSEN (1973), AND OF ROGERS ET AL (1971) WERE USED AS GUIDES 7328 1451 220 FOR LINES AT 0.108, 0.1361, 0.152, 0.165, 0.179, 0.1937, 0.205 7328 1451 221 0.259, 0.288, 0.301, 0.331, 0.345, 0.3589, 0.482, 0.80, 0.99, 7328 1451 222 1.08, 1.150, 1.206, 1.245, 1.308, 1.382, AND 1.426 MEV. K AND L 7328 1451 223 X-RAYS FOLLOWING INTERNAL CONVERSION WERE ALSO INCLUDED. 7328 1451 224 GAMMA RAYS FROM THE OTHER DISCRETE (N,N*) LEVELS WERE 7328 1451 225 LUMPED INTO THE CONTINUUM. 7328 1451 226 CONTINUUM CONTRIBUTIONS WERE HANDLED BY USING THE HOWERTON AND 7328 1451 227 PLECHATY RECIPE WITH MEASURED GAMMA RAY TEMPERATURES (ORNL-TM- 7328 1451 228 3702)FOR EACH REACTION. THE AVERAGE PHOTON ENERGY IN THE SPECTRA 7328 1451 229 WERE CHOSEN TO GIVE OVERALL ENERGY CONSERVATION FOR THE COMBINED 7328 1451 230 NEUTRON-PLUS-GAMMA PRODUCTION PROCESSES. 7328 1451 231 7328 1451 232 (N,X GAMMA) ENERGY DISTRIBUTIONS 7328 1451 233 MF = 15 MT = 3 7328 1451 234 EXPERIMENTAL GAMMA RAY TEMPERATURES (ORNL-TM-3702) WERE USED 7328 1451 235 WITH THE HOWERTON AND PLECHATY RECIPE (LOC. CIT.) IN A CALCULA- 7328 1451 236 TION THAT WAS MATCHED TO GAMMA RAY PRODUCTION DATA (ORNL-TM-3702) 7328 1451 237 AND TO NEUTRON SYSTEMATICS, WITH ENERGY BEING CONSERVED ON THE 7328 1451 238 AVERAGE FOR ALL NEUTRON AND GAMMA RAY PRODUCTION PROCESSES. 7328 1451 239 7328 1451 240 REFERENCES 7328 1451 241 REFERENCE NUMBERS QUOTED HERE REFER TO DATA IN THE LLL 7328 1451 242 EXPERIMENTAL NEUTRON CROSS SECTION LIBRARY. SEE UCRL-50400, 7328 1451 243 VOL. 2 AND 3 FOR COMMENTS AND INDEXES TO THE DATA, AS WELL AS FOR 7328 1451 244 OTHER EXPERIMENTAL RESULTS THAT WERE USED IN THE EVALUATION. 7328 1451 245 7328 1451 246 885. PRIVATE COMMUNICATION (1966) A.B.SMITH (ANL) 7328 1451 247 1019 PRIVATE COMMUNICATION (1968) W.E.TUCKER (TEXAS NUCLEAR) 7328 1451 248 1497 NUCLEAR SCI. ENG. 40, 294 (1970) D.M.DRAKE ET AL. (LASL) 7328 1451 249 1960 J.EXPTL.THEORET.PHYS. (USSR) 46, 80 (1964) V.A.KONKS ET AL. 7328 1451 250 2402 INR-795/I/PL (1967) J.BRZOSKO ET AL. (POLAND) 7328 1451 251 2415 GA-10248 (DASA-2570) (1970) N.C.RASMUSSEN ET AL. (GGA) 7328 1451 252 2887 NUCLEAR PHYS. 123, 603 (1969) J.S.BRZOSKO ET AL. (POLAND) 7328 1451 253 3211 NUCLEAR PHYS. A168, 449 (1971) R.G. HELMER, R.C. GREENWOOD 7328 1451 254 AND C.W. REICH (MTR) 7328 1451 255 3212 P.F.A. GOUDSMIT, THESIS, UNIV. AMSTERDAM (1969) 7328 1451 256 3213 BULL. ACAD. SCI. (PHYS. SER.) 32, 1833 (1968) YA K. ALKENIS,7328 1451 257 M.K. BALODIS, AND P.T. PROKOFIEV 7328 1451 258 1 451 263 07328 1451 259 2 151 139 07328 1451 260 3 16 9 07328 1451 261 3 102 16 07328 1451 262 3 103 5 07328 1451 263 7328 1 0 264 7328 0 0 265 7.318100+4 1.794000+2 0 0 1 07328 2151 266 7.318100+4 1.000000+0 0 0 2 07328 2151 267 1.000000-5 3.300000+2 1 2 0 07328 2151 268 3.500000+0 8.127100-1 0 0 1 07328 2151 269 1.793940+2 0.000000+0 0 0 456 767328 2151 270 -1.440000+1 3.000000+0 9.350000-2 3.750000-2 5.600000-2 0.000000+07328 2151 271 4.280000+0 4.000000+0 5.690000-2 3.900000-3 5.300000-2 0.000000+07328 2151 272 1.034000+1 3.000000+0 5.966000-2 4.660000-3 5.500000-2 0.000000+07328 2151 273 1.395000+1 4.000000+0 5.301300-2 1.013000-3 5.200000-2 0.000000+07328 2151 274 2.030000+1 4.000000+0 6.102200-2 1.022200-3 6.000000-2 0.000000+07328 2151 275 2.270000+1 3.000000+0 5.225100-2 2.514300-4 5.200000-2 0.000000+07328 2151 276 2.390000+1 3.000000+0 6.042800-2 7.428000-3 5.300000-2 0.000000+07328 2151 277 3.000000+1 4.000000+0 5.519600-2 1.955600-4 5.500000-2 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1.970000+0 1.200000+7 2.170000+07328 3 16 412 1.250000+7 2.220000+0 1.430000+7 2.210000+0 1.460000+7 2.190000+07328 3 16 413 1.500000+7 2.080000+0 1.600000+7 1.680000+0 1.700000+7 1.270000+07328 3 16 414 1.750000+7 1.010000+0 2.000000+7 6.100000-1 0.000000+0 0.000000+07328 3 16 415 7328 3 0 416 7.318100+4 1.794000+2 0 0 0 07328 3102 417 6.070000+6 6.070000+6 0 0 1 377328 3102 418 37 2 0 0 0 07328 3102 419 1.000000-5 0.000000+0 3.300000+2 0.000000+0 3.300000+2-1.610000+07328 3102 420 6.000000+2 1.000000+0 1.000000+3 6.610000-1 2.000000+3 6.000000-37328 3102 421 5.000000+3-1.130000-1 5.000000+3 3.300000+0 7.000000+3 2.600000+07328 3102 422 1.000000+4 2.000000+0 1.300000+4 1.550000+0 1.500000+4 1.350000+07328 3102 423 2.000000+4 1.050000+0 2.500000+4 8.700000-1 3.000000+4 7.200000-17328 3102 424 4.000000+4 6.000000-1 5.000000+4 5.000000-1 6.000000+4 4.300000-17328 3102 425 7.000000+4 3.900000-1 8.000000+4 3.600000-1 9.000000+4 3.300000-17328 3102 426 1.000000+5 3.100000-1 1.500000+5 2.600000-1 2.000000+5 2.800000-17328 3102 427 2.500000+5 2.850000-1 3.000000+5 2.600000-1 4.000000+5 2.200000-17328 3102 428 5.000000+5 2.000000-1 7.000000+5 1.600000-1 1.000000+6 1.300000-17328 3102 429 1.500000+6 9.000000-2 2.000000+6 5.500000-2 3.000000+6 2.500000-27328 3102 430 4.000000+6 1.500000-2 6.000000+6 1.000000-2 1.200000+7 5.000000-37328 3102 431 2.000000+7 3.000000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+07328 3102 432 7328 3 0 433 7.318100+4 1.794000+2 0 0 0 07328 3103 434 -2.387000+5-2.387000+5 0 0 1 67328 3103 435 6 2 0 0 0 07328 3103 436 2.400000+5 1.000000-6 5.000000+6 2.000000-4 1.250000+7 1.000000-37328 3103 437 1.500000+7 5.500000-3 1.700000+7 7.500000-3 2.000000+7 7.500000-37328 3103 438 7328 3 0 439 7328 0 0 440 0 0 0 441 7.418200+4 1.803900+2 -1 0 0 07431 1451 1 0.000000+0 0.000000+0 0 0 0 67431 1451 2 1.000000+0 0.000000+0 0 0 10 67431 1451 3 0.000000+0 0.000000+0 0 0 264 27431 1451 4 74-W-182 LANL,ANL+ EVAL-DEC80 ARTHUR,YOUNG,SMITH,PHILIS 7431 1451 5 DIST-FEB90 900202 7431 1451 6 ----ENDF/B-VI MATERIAL 7431 7431 1451 7 -----INCIDENT NEUTRON DATA 7431 1451 8 ------ENDF-6 FORMAT 7431 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************7431 1451 10 ACTIVATION II 7431 1451 11 ******************************************************************7431 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 7431 1451 13 * * * * * * *7431 1451 14 7431 1451 15 SUMMARY OF CONTRIBUTIONS 7431 1451 16 7431 1451 17 1. MF=2,MT=151 AND MF=3,MT=103,107 TAKEN FROM ENDF/B-V. 7431 1451 18 2. TOTAL CROSS SECTION ABOVE 100 KEV EVALUATED BY SMITH. 7431 1451 19 3. ALL OTHER DATA OBTAINED FROM MODEL CALCULATIONS OPTIMIZED TO 7431 1451 20 EXPERIMENT BY ARTHUR, YOUNG, AND PHILIS. 7431 1451 21 7431 1451 22 **************************************************************** 7431 1451 23 7431 1451 24 MF=1 MT=451 DESCRIPTIVE INFORMATION 7431 1451 25 7431 1451 26 ATOMIC MASS AND Q VALUES A.H. WAPSTRA AND K. BOS 7431 1451 27 ATOMIC DATA AND NUCLEAR DATA TABLES 19, 177(1977) 7431 1451 28 7431 1451 29 MF=2 MT=151 RESONANCE PARAMETERS 7431 1451 30 7431 1451 31 RESOLVED RESONANCE EVALUATION 7431 1451 32 POTENTIAL SCATTERING XSEC = 8.0+-1.0 B AT E=0 7431 1451 33 2200 M/S CROSS SECTIONS (BARNS) 7431 1451 34 CALC MEAS (REF-1) 7431 1451 35 CAP 20.5 20.7+-0.5 7431 1451 36 SCAT 11.6 7431 1451 37 7431 1451 38 RESOLVED RESONANCE PARAMETERS 7431 1451 39 -100 EV FROM FIT TO CAPTURE 7431 1451 40 4.16 EV FROM REFERENCE 1 7431 1451 41 5 - 250 EV FROM EVALUATION, REFERENCE 1,2, AND 3 7431 1451 42 250 - 1250 EV FROM EVALUATION, REFERENCE 2 AND 3 7431 1451 43 1250 - 4500 EV FROM REFERENCE 3 EXCEPT BELOW 7431 1451 44 1920 , 2198 EV FROM REFERENCE 2 7431 1451 45 7431 1451 46 UNRESOLVED RESONANCE EVALUATION 7431 1451 47 POTENTIAL SCATTERING XSEC = 8.5+-1.0 B AT E=0 7431 1451 48 TOTAL XSEC = 8.85 B AT E=100 KEV (CALCULATED) 7431 1451 49 7431 1451 50 UNRESOLVED RESONANCE PARAMETERS FROM AUTOMATED OPTIMIZED FIT TO7431 1451 51 THE EVALUATED MEASURED CAPTURE CROSS SECTION. 7431 1451 52 AV L=0 LEVEL SPACING (E=0) = 57.45 EV, ENERGY DEP. FROM REF 4.7431 1451 53 AV CAPTURE LEVEL WIDTH = 0.0901 EV, ENERGY INDEPENDENT 7431 1451 54 L=0 STRENGTH FUNCTION = 1.8E-4 , ENERGY INDEPENDENT 7431 1451 55 L=1 STRENGTH FUNCTION = 0.272E-4 , ENERGY INDEPENDENT 7431 1451 56 L=2 STRENGTH FUNCTION = 0.0 7431 1451 57 7431 1451 58 AVERAGE CAPTURE CROSS SECTION UNCERTAINTY AT ENERGY E 7431 1451 59 E (KEV) UNC. (() 7431 1451 60 100 15 7431 1451 61 90 10 7431 1451 62 10 10 7431 1451 63 4.5 17 7431 1451 64 7431 1451 65 RESONANCE INTEGRAL(CAPT.) 596 B CALC., 590+-10 B MEAS. (REF-5) 7431 1451 66 REFERENCES 7431 1451 67 1. BNL-325,2ND EDITION, SUPPLEMENT 2, GOLDBERG ET AL (1966) 7431 1451 68 2. Z.M.BARTOLOME ET AL, NUCL.SCI.ENG. 37, P137 (1969) 7431 1451 69 3. F.J.RAHN AND H.CAMARDA, PERSONAL COMMUNICATION, COLUMBIA(1970)7431 1451 70 4. J.L.COOK ET AL AAEC/TM-392 (1967) 7431 1451 71 5. M.DRAKE, (1968) FOR AMERICAN INSTITUTE OF PHYS. HANDBOOK(1972)7431 1451 72 7431 1451 73 MF=3 MT=1 TOTAL CROSS SECTION 7431 1451 74 7431 1451 75 THE EVALUATED TOTAL CROSS SECTION RELIES UPON THE EXPERIMEN- 7431 1451 76 TAL RESULTS OF LISTER ET AL REF 1 FROM 0.1 TO 0.65 MEV. 7431 1451 77 (BELOW 0.1 MEV THE ENDF-B/V RESULTS IN THE UNRESOLVED RESONANCE 7431 1451 78 RANGE WERE USED DIRECTLY). FROM 0.65 TO 2.3 MEV THE NEWLY 7431 1451 79 MEASURED RESULTS OF GUENTHER ET AL REF 2 WERE USED SINCE 7431 1451 80 THESE DATA ARE CONSISTENT WITH BOTH HIGHER AND LOWER ENERGY 7431 1451 81 DATA REF 1,3,4. FROM 2.3 TO 5.0 MEV THE GUENTHER RESULTS AND 7431 1451 82 THOSE OF FOSTER AND GLASGOW REF 3 WERE AVERAGED TO PRODUCE 7431 1451 83 THE EVALUATED DATA. BETWEEN 5 AND 15 MEV THE EVALUATION 7431 1451 84 RELIED ON THE FOSTER RESULTS. NO EXPERIMENTAL DATA EXIST 7431 1451 85 ABOVE 15 MEV SO THAT RESULTS FROM CALCULATIONS USING THE 7431 1451 86 COUPLED CHANNELS CODE ECIS REF 5 WERE ADOPTED. THE OPTICAL 7431 1451 87 PARAMATERS USED SEE REF 6 GAVE GOOD AGREEMENT TO DATA IN 7431 1451 88 THE ENERGY RANGE FROM 0.1 TO 15 MEV. 7431 1451 89 7431 1451 90 MF=3 MT=2 ELASTIC CROSS SECTION 7431 1451 91 7431 1451 92 THE EVALUATED ELASTIC CROSS SECTION WAS OBTAINED BY SUBTRAC- 7431 1451 93 TING THE NONELASTIC CROSS SECTION FROM THE EVALUATED TOTAL 7431 1451 94 CROSS SECTION. 7431 1451 95 THE EVALUATED DATA ARE IN GOOD AGREEMENT WITH RECENT MEASURE- 7431 1451 96 MENTS AT ENERGIES BELOW 4 MEV REF 2. 7431 1451 97 7431 1451 98 MF=3 MT=4 TOTAL INELASTIC CROSS SECTION 7431 1451 99 7431 1451 100 EQUAL TO THE SUM OF THE INELASTIC LEVEL EXCITATION AND 7431 1451 101 CONTINUUM CROSS SECTIONS. 7431 1451 102 7431 1451 103 MF=3 MT=16 (N,2N) CROSS SECTIONS 7431 1451 104 7431 1451 105 MULTISTEP HAUSER-FESHBACH CALCULATIONS WITH PREEQUILIBRIUM 7431 1451 106 CORRECTIONS WERE MADE USING THE GNASH CODE REF 7 AND 7431 1451 107 DEFORMED OPTICAL MODEL TRANSMISSION COEFFICIENTS FROM THE ECIS 7431 1451 108 COUPLED-CHANNELS CODE. THE RESULTS AGREE WELL WITH THE ISO- 7431 1451 109 TOPIC DATA OF FREHAUT ET AL REF 8 MEASURED FROM THRESHOLD TO 7431 1451 110 15 MEV. 7431 1451 111 7431 1451 112 MF=3 MT=17 (N,3N) CROSS SECTIONS 7431 1451 113 7431 1451 114 OBTAINED FROM PREEQUILIBRIUM HAUSER-FESHBACH CALCULATIONS 7431 1451 115 MADE WITH THE GNASH CODE. 7431 1451 116 7431 1451 117 MF=3 MT=28 (N,PN) AND (N,NP) CROSS SECTIONS 7431 1451 118 7431 1451 119 ENDF-B/V VALUES MODIFIED TO FIT QAIM(1975) SYSTEMATICS 7431 1451 120 7431 1451 121 MF=3 MT=51,52 INELASTIC CROSS SECTIONS FOR EXCITATION OF 7431 1451 122 THE FIRST AND SECOND EXCITED STATES 7431 1451 123 7431 1451 124 CALCULATED VALUES WERE USED FOR THESE CROSS SECTIONS. THE 7431 1451 125 ECIS COUPLED CHANNELS CODE WAS USED FOR DIRECT-REACTION CONT- 7431 1451 126 RIBUTIONS WHILE COMPOUND NUCLEUS CONTRIBUTIONS WERE OBTAINED 7431 1451 127 USING THE COMNUC HAUSER-FESHBACH CODE REF 9 WITH WIDTH- 7431 1451 128 FLUCTUATION CORRECTIONS. BOTH CALCULATIONS EMPLOYED DEFORMED 7431 1451 129 NEUTRON OPTICAL MODEL PARAMETERS BASED ON A MODIFICATION 7431 1451 130 REF 6 OF THE SET DEVELOPED BY DELAROCHE ET AL REF 10. 7431 1451 131 THESE CALCULATED DATA AGREE WELL WITH THE MEASURED RESULTS 7431 1451 132 OF REF 2. 7431 1451 133 7431 1451 134 MF=3 MT=53,69 INELASTIC SCATTERING CROSS SECTIONS TO THE 7431 1451 135 THIRD THROUGH NINETEENTH EXCITED STATES IN W182 7431 1451 136 7431 1451 137 CROSS SECTIONS FOR INELASTIC SCATTERING FROM THE THIRD 7431 1451 138 THROUGH NINETEENTH EXCITED STATES IN W182 WERE CALCULATED 7431 1451 139 USING THE COMNUC HAUSER-FESHBACH CODE SO ONLY COMPOUND- 7431 1451 140 NUCLEUS CONTRIBUTIONS WERE INCLUDED. ABOVE 6 MEV SUCH CROSS 7431 1451 141 SECTIONS WERE SET TO ZERO AND WERE ADDED TO THE CONTINUUM 7431 1451 142 CROSS SECTION. 7431 1451 143 7431 1451 144 MF=3 MT=91 INELASTIC SCATTERING TO THE CONTINUUM 7431 1451 145 7431 1451 146 AT LOW ENERGIES THIS CROSS SECTION REPRESENTS CONTRIBUTIONS 7431 1451 147 FROM THE (N,GAMMA N) PROCESS CALCULATED USING THE COMNUC CODE. 7431 1451 148 AT HIGHER ENERGIES THIS CROSS SECTION IS DOMINATED BY 7431 1451 149 INELASTIC SCATTERING TO THE CONTINUUM WHICH WAS CALCULATED 7431 1451 150 USING THE COMNUC CODE AND, WHERE PREEQUILIBRIUM EFFECTS ARE 7431 1451 151 IMPORTANT, WITH THE GNASH CODE. 7431 1451 152 7431 1451 153 MF=3 MT=102 RADIATIVE CAPTURE CROSS SECTIONS 7431 1451 154 7431 1451 155 AT ENERGIES BELOW 0.1 MEV THE ENDF-B/V RESULTS WERE USED 7431 1451 156 DIRECTLY. FROM 0.1 TO 6 MEV COMNUC/GNASH CALCULATIONS WERE 7431 1451 157 MADE. AT ENERGIES GREATER THAN 1 MEV A FULL TREATMENT OF THE 7431 1451 158 GAMMA-RAY CASCADE WAS INCLUDED. ABOVE 6 MEV A SIMPLE MODEL 7431 1451 159 BASED ON THE PREEQUILIBRIUM EMISSION OF GAMMA RAYS WAS 7431 1451 160 USED TO ACCOUNT FOR DIRECT-SEMIDIRECT EFFECTS. RESULTS FROM 7431 1451 161 THIS MODEL WERE NORMALIZED TO DATA REF 11 AT 14 MEV. THE 7431 1451 162 CALCULATED CAPTURE CROSS SECTIONS BETWEEN 0.5 AND 3 MEV AGREE 7431 1451 163 WELL WITH THE RECENT MEASUREMENTS OF GRENIER REF 12. 7431 1451 164 7431 1451 165 MF=3 MT=103,107 N,P AND N,ALPHA CROSS SECTIONS 7431 1451 166 7431 1451 167 TAKEN DIRECTLY FROM ENDF-B/V. 7431 1451 168 7431 1451 169 MF=4 MT=2 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS 7431 1451 170 7431 1451 171 ANGULAR DISTRIBUTIONS OBTAINED FROM ECIS COUPLED-CHANNEL 7431 1451 172 CALCULATIONS ARE EXPRESSED IN TERMS OF LEGENDRE COEFFICIENTS 7431 1451 173 IN THE CENTER OF MASS SYSTEM. 7431 1451 174 7431 1451 175 MF=4 MT=16,17 ANGULAR DISTRIBUTIONS OF NEUTRONS 7431 1451 176 FROM (N,2N) AND (N,3N) REACTIONS 7431 1451 177 7431 1451 178 ANGULAR DISTRIBUTIONS WERE OBTAINED USING THE KALBACH-MANN 7431 1451 179 SYSTEMATICS REF 13 THAT REQUIRE KNOWLEDGE OF THE PRE- 7431 1451 180 EQUILIBRIUM EMISSION FRACTION AND THE AVERAGE ENERGY OF THE 7431 1451 181 EMITTED NEUTRON. THE RESULTS ARE EXPRESSED IN TERMS OF 7431 1451 182 LEGENDRE POLYNOMIAL COEFFICIENTS IN THE LABORATORY SYSTEM. 7431 1451 183 7431 1451 184 MF=4 MT=28 ANGULAR DISTRIBUTIONS OF NEUTRONS FROM 7431 1451 185 (N,NP) AND (N,PN) REACTIONS 7431 1451 186 7431 1451 187 THESE ARE ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM. 7431 1451 188 7431 1451 189 MF=4 MT=91 ANGULAR DISTRIBUTIONS OF NEUTRONS FROM 7431 1451 190 CONTINUUM INELASTIC SCATTERING 7431 1451 191 7431 1451 192 LEGENDRE COEFFICIENTS OBTAINED FROM THE KALBACH-MANN 7431 1451 193 SYSTEMATICS ARE GIVEN IN THE LABORATORY SYSTEM. 7431 1451 194 7431 1451 195 MF=5 MT=16,17 NEUTRON EMISSION SPECTRA FROM (N,2N) 7431 1451 196 AND (N,3N) REACTIONS 7431 1451 197 7431 1451 198 HISTOGRAMS ARE GIVEN OF EMISSION SPECTRA CALCULATED USING 7431 1451 199 THE GNASH PREEQUILIBRIUM STATISTICAL MODEL CODE. 7431 1451 200 7431 1451 201 MF=5 MT=28 NEUTRON SPECTRA FROM (N,NP) AND (N,PN) 7431 1451 202 REACTIONS 7431 1451 203 7431 1451 204 FOR THESE SPECTRA ENDF-B/V RESULTS WERE USED DIRECTLY. 7431 1451 205 7431 1451 206 MF=5 MT=91 NEUTRON SPECTRA FROM THE CONTINUUM EMISSION 7431 1451 207 OF INELASTICALLY SCATTERED NEUTRONS 7431 1451 208 7431 1451 209 HISTOGRAMS ARE GIVEN OF EMISSION SPECTRA THAT INCLUDE 7431 1451 210 PREEQUILBRIUM EFFECTS AS OBTAINED FROM GNASH CALCULATIONS. 7431 1451 211 7431 1451 212 MF=12 MT=102 MULTIPLICITIES FOR GAMMA-RAY PRODUCTION FROM 7431 1451 213 RADIATIVE CAPTURE 7431 1451 214 7431 1451 215 BELOW 0.1 MEV THE MULTIPLICITIES WERE TAKEN DIRECTLY 7431 1451 216 FROM ENDF-B/V. AT HIGHER ENERGIES MULTIPLICITIES WERE 7431 1451 217 OBTAINED DIRECTLY FROM COMNUC AND GNASH STATISTICAL MODEL 7431 1451 218 CALCULATIONS. 7431 1451 219 7431 1451 220 MF=13 MT=4,16,17 GAMMA-RAY PRODUCTION CROSS SECTIONS FROM 7431 1451 221 INELASTIC, (N,2N), AND (N,3N) REACTIONS 7431 1451 222 7431 1451 223 THE CROSS SECTION FOR DISCRETE PHOTONS OCCURING THROUGH 7431 1451 224 INELASTIC SCATTERING ARE BASED ON THE LEVEL EXCITATION CROSS 7431 1451 225 SECTION IN MF=3, MT=51-69. FOR GAMMA-RAY CROSS SECTIONS 7431 1451 226 FROM CONTINUUM INELASTIC, (N,2N), AND (N,3N) REACTIONS, 7431 1451 227 GNASH RESULTS WERE USED DIRECTLY. 7431 1451 228 7431 1451 229 MF=14 MT=4,16,17,102 ANGULAR DISTRIBUTIONS OF GAMMA-RAYS 7431 1451 230 FROM INELASTIC SCATTERING, (N,2N), 7431 1451 231 (N,3N), AND RADIATIVE CAPTURE REACTIONS 7431 1451 232 7431 1451 233 ALL GAMMA-RAYS ARE ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM. 7431 1451 234 7431 1451 235 MF=15 MT=16,17,91 ENERGY SPECTRA OF GAMMA-RAYS FROM 7431 1451 236 (N,2N), (N,3N) AND CONTINUUM INELASTIC 7431 1451 237 REACTIONS 7431 1451 238 7431 1451 239 THE SPECTRA AT ALL ENERGIES ARE BASED DIRECTLY ON PREEQUI- 7431 1451 240 LIBRIUM HAUSER-FESHBACH CALCULATIONS MADE USING THE GNASH 7431 1451 241 NUCLEAR MODEL CODE. 7431 1451 242 7431 1451 243 MF=15 MT=102 ENERGY SPECTRA OF GAMMA-RAYS FROM RADIATIVE 7431 1451 244 CAPTURE 7431 1451 245 7431 1451 246 BELOW 0.1 MEV THE SPECTRA ARE TAKEN FROM ENDF-B/V. 7431 1451 247 FROM 0.1 TO 10 MEV THE SPECTRA ARE TAKEN FROM GNASH STATISTI- 7431 1451 248 CAL MODEL CALCULATIONS. ABOVE 10 MEV A SIMPLE PREEQUILIBRIUM 7431 1451 249 -LIKE MODEL WAS USED TO CALCULATE THE SPECTRA. 7431 1451 250 7431 1451 251 7431 1451 252 REFERENCES FOR MF=3,4,12,13,15 7431 1451 253 7431 1451 254 1. D.LISTER ET AL, PHYS. REV. 162,1077 (1967) 7431 1451 255 2. P.GUENTHER, A.B.SMITH, TO BE PUBLISHED (1981) 7431 1451 256 3. D.FOSTER AND D.GLASGOW, PHYS. REV. C3,576 (1971) 7431 1451 257 4. R.C.MARTIN ET AL, BULL. AM. PHYS. SOC. 12,106 (1967) 7431 1451 258 5. J.RAYNAL,IAEA-SMR-9/8 (1972) 7431 1451 259 6. E.D.ARTHUR ET AL, LOS ALAMOS REPORT LA 8630 PR, P.2 (1980) 7431 1451 260 7. P.G.YOUNG AND E.D.ARTHUR, LOS ALAMOS REPORT LA 6947 (1977) 7431 1451 261 8. J.FREHAUT ET AL, BNL-NCS-51245, VOL.1,P.399 (1980) 7431 1451 262 9. C.DUNFORD, ATOMICS INTERNATIONAL REPORT AI-AEC-12931 (1970) 7431 1451 263 10. J.P.DELAROCHE ET AL, NBS SPECIAL PUBLICATION 594,P.336 (1980) 7431 1451 264 11. M.BUDNAR ET AL, INDC(YUG)-6/2 (1979) 7431 1451 265 12. G.GRENIER ET AL, NBS SPECIAL PUBLICATION 594,P.323 (1980) 7431 1451 266 13. C.KALBACH AND F.MANN, BNL-NCS-5/245,P.689 (1980) 7431 1451 267 7431 1451 268 1 451 270 07431 1451 269 3 16 12 07431 1451 270 7431 1 0 271 7431 0 0 272 7.418200+4 1.803900+2 0 0 0 07431 3 16 273 -8.062400+6-8.062400+6 0 0 1 257431 3 16 274 25 2 0 0 0 07431 3 16 275 8.107100+6 0.000000+0 8.500000+6 9.598000-2 9.000000+6 4.417000-17431 3 16 276 9.500000+6 8.247000-1 1.000000+7 1.141000+0 1.050000+7 1.355000+07431 3 16 277 1.100000+7 1.515000+0 1.150000+7 1.643000+0 1.200000+7 1.754000+07431 3 16 278 1.250000+7 1.839500+0 1.300000+7 1.903000+0 1.350000+7 1.953500+07431 3 16 279 1.400000+7 1.992000+0 1.450000+7 2.020000+0 1.500000+7 2.044000+07431 3 16 280 1.550000+7 2.061900+0 1.600000+7 2.054000+0 1.650000+7 2.008600+07431 3 16 281 1.700000+7 1.936700+0 1.750000+7 1.848100+0 1.800000+7 1.753000+07431 3 16 282 1.850000+7 1.657600+0 1.900000+7 1.559800+0 1.950000+7 1.457100+07431 3 16 283 2.000000+7 1.347000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+07431 3 16 284 7431 3 0 285 7431 0 0 286 0 0 0 287 7.418400+4 1.823700+2 1 0 0 07437 1451 1 0.000000+0 0.000000+0 0 0 0 67437 1451 2 1.000000+0 0.000000+0 0 0 10 67437 1451 3 0.000000+0 0.000000+0 0 0 266 47437 1451 4 74-W-184 LANL,ANL+ EVAL-DEC80 ARTHUR,YOUNG,SMITH,PHILIS 7437 1451 5 DIST-FEB90 900202 7437 1451 6 ----ENDF/B-VI MATERIAL 7437 7437 1451 7 -----INCIDENT NEUTRON DATA 7437 1451 8 ------ENDF-6 FORMAT 7437 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************7437 1451 10 ACTIVATION II 7437 1451 11 ******************************************************************7437 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 7437 1451 13 * * * * * * *7437 1451 14 7437 1451 15 SUMMARY OF CONTRIBUTIONS 7437 1451 16 7437 1451 17 1. MF=2,MT=151 AND MF=3,MT=103,107 TAKEN FROM ENDF/B-V. 7437 1451 18 2. TOTAL CROSS SECTION ABOVE 100 KEV EVALUATED BY SMITH. 7437 1451 19 3. ALL OTHER DATA OBTAINED FROM MODEL CALCULATIONS OPTIMIZED TO 7437 1451 20 EXPERIMENT BY ARTHUR, YOUNG, AND PHILIS. 7437 1451 21 7437 1451 22 **************************************************************** 7437 1451 23 7437 1451 24 MF=1 MT=451 DESCRIPTIVE INFORMATION 7437 1451 25 7437 1451 26 ATOMIC MASS AND Q VALUES A.H. WAPSTRA AND K. BOS 7437 1451 27 ATOMIC DATA AND NUCLEAR DATA TABLES 19, 177(1977) 7437 1451 28 7437 1451 29 MF=2 MT=151 RESONANCE PARAMETERS 7437 1451 30 7437 1451 31 RESOLVED RESONANCE EVALUATION 7437 1451 32 7437 1451 33 POTENTIAL SCATTERING XSEC = 8.0+-1.0 B AT E=0 7437 1451 34 2200 M/S CROSS SECTION (BARNS) 7437 1451 35 CALC MEAS (REF-1) 7437 1451 36 CAP 1.8 1.8+-0.2 7437 1451 37 SCAT 3.9 7437 1451 38 7437 1451 39 RESOLVED RESONANCE PARAMETERS 7437 1451 40 -11.76 EV FROM FIT TO CAPTURE 7437 1451 41 102 EV FROM EVALUATION, REFERENCE 1 AND 2 7437 1451 42 150 - 2060 EV FROM EVALUATION, REFERENCE 1,2, AND 3 7437 1451 43 2080 - 2110 EV FROM REFERENCE 2 7437 1451 44 2200 - 2650 EV FROM REFERENCE 3 7437 1451 45 7437 1451 46 UNRESOLVED RESONANCE EVALUATION 7437 1451 47 7437 1451 48 POTENTIAL SCATTERING XSEC = 8.5+-1.0 B AT E=0 7437 1451 49 TOTAL XSEC = 9.1 B AT E=100 KEV (CALCULATED) 7437 1451 50 7437 1451 51 UNRESOLVED RESONANCE PARAMETERS FROM AUTOMATED OPTIMIZED FIT TO7437 1451 52 THE EVALUATED MEASURED CAPTURE CROSS SECTION. 7437 1451 53 AV L=0 LEVEL SPACING (E=0) = 80.3 EV, ENERGY DEP. FROM REF 4 7437 1451 54 AV CAPTURE LEVEL WIDTH = 0.0731 EV, ENERGY INDEPENDENT 7437 1451 55 L=0 STRENGTH FUNCTION = 2.3E-4 , ENERGY INDEPENDENT 7437 1451 56 L=1 STRENGTH FUNCTION = 0.18E-4 , ENERGY INDEPENDENT 7437 1451 57 L=2 STRENGTH FUNCTION = 1.45E-4 , ENERGY INDEPENDENT 7437 1451 58 7437 1451 59 AVERAGE CAPTURE CROSS SECTION UNCERTAINTY AT ENERGY E 7437 1451 60 E (KEV) UNC. (() 7437 1451 61 100 15 7437 1451 62 90 10 7437 1451 63 10 10 7437 1451 64 4.5 20 7437 1451 65 7437 1451 66 RESONANCE INTEGRAL(CAPTURE) 16.2B CALC., 13+-2B MEASURED (REF-5)7437 1451 67 7437 1451 68 REFERENCES 7437 1451 69 1. BNL-325,2ND EDITION, SUPPLEMENT 2, GOLDBERG ET AL (1966) 7437 1451 70 2. Z.M.BARTOLOME ET AL, NUCL.SCI.ENG. 37, P137 (1969) 7437 1451 71 3. F.J.RAHN AND H.CAMARDA, PERSONAL COMMUNICATION, COLUMBIA(1970)7437 1451 72 4. J.L.COOK ET AL AAEC/TM-392 (1967) 7437 1451 73 5. M.DRAKE, (1968) FOR AMERICAN INSTITUTE OF PHYS. HANDBOOK(1972)7437 1451 74 7437 1451 75 MF=3 MT=1 TOTAL CROSS SECTION 7437 1451 76 7437 1451 77 THE EVALUATED TOTAL CROSS SECTION RELIES UPON THE EXPERIMEN- 7437 1451 78 TAL RESULTS OF LISTER ET AL REF 1 FROM 0.1 TO 0.65 MEV. 7437 1451 79 (BELOW 0.1 MEV THE ENDF-B/V RESULTS IN THE UNRESOLVED RESONANCE 7437 1451 80 RANGE WERE USED DIRECTLY). FROM 0.65 TO 2.3 MEV THE NEWLY 7437 1451 81 MEASURED RESULTS OF GUENTHER ET AL REF 2 WERE USED SINCE 7437 1451 82 THESE DATA ARE CONSISTENT WITH BOTH HIGHER AND LOWER ENERGY 7437 1451 83 DATA REF 1,3,4. FROM 2.3 TO 5.0 MEV THE GUENTHER RESULTS AND 7437 1451 84 THOSE OF FOSTER AND GLASGOW REF 3 WERE AVERAGED TO PRODUCE 7437 1451 85 THE EVALUATED DATA. BETWEEN 5 AND 15 MEV THE EVALUATION 7437 1451 86 RELIED ON THE FOSTER RESULTS. NO EXPERIMENTAL DATA EXIST 7437 1451 87 ABOVE 15 MEV SO THAT RESULTS FROM CALCULATIONS USING THE 7437 1451 88 COUPLED CHANNELS CODE ECIS REF 5 WERE ADOPTED. THE OPTICAL 7437 1451 89 PARAMATERS USED SEE REF 6 GAVE GOOD AGREEMENT TO DATA IN 7437 1451 90 THE ENERGY RANGE FROM 0.1 TO 15 MEV. 7437 1451 91 7437 1451 92 MF=3 MT=2 ELASTIC CROSS SECTION 7437 1451 93 7437 1451 94 THE EVALUATED ELASTIC CROSS SECTION WAS OBTAINED BY SUBTRAC- 7437 1451 95 TING THE NONELASTIC CROSS SECTION FROM THE EVALUATED TOTAL 7437 1451 96 CROSS SECTION. 7437 1451 97 THE EVALUATED DATA ARE IN GOOD AGREEMENT WITH RECENT MEASURE- 7437 1451 98 MENTS AT ENERGIES BELOW 4 MEV REF 2. 7437 1451 99 7437 1451 100 MF=3 MT=4 TOTAL INELASTIC CROSS SECTION 7437 1451 101 7437 1451 102 EQUAL TO THE SUM OF THE INELASTIC LEVEL EXCITATION AND 7437 1451 103 CONTINUUM CROSS SECTIONS. 7437 1451 104 7437 1451 105 MF=3 MT=16 (N,2N) CROSS SECTIONS 7437 1451 106 7437 1451 107 MULTISTEP HAUSER-FESHBACH CALCULATIONS WITH PREEQUILIBRIUM 7437 1451 108 CORRECTIONS WERE MADE USING THE GNASH CODE REF 7 AND 7437 1451 109 DEFORMED OPTICAL MODEL TRANSMISSION COEFFICIENTS FROM THE ECIS 7437 1451 110 COUPLED-CHANNELS CODE. THE RESULTS AGREE WELL WITH THE ISO- 7437 1451 111 TOPIC DATA OF FREHAUT ET AL REF 8 MEASURED FROM THRESHOLD TO 7437 1451 112 15 MEV. 7437 1451 113 7437 1451 114 MF=3 MT=17 (N,3N) CROSS SECTIONS 7437 1451 115 7437 1451 116 OBTAINED FROM PREEQUILIBRIUM HAUSER-FESHBACH CALCULATIONS 7437 1451 117 MADE WITH THE GNASH CODE. 7437 1451 118 7437 1451 119 MF=3 MT=28 (N,PN) AND (N,NP) CROSS SECTIONS 7437 1451 120 7437 1451 121 THESE VALUES WERE TAKEN DIRECTLY FROM ENDF-B/V. 7437 1451 122 7437 1451 123 MF=3 MT=51,52 INELASTIC CROSS SECTIONS FOR EXCITATION OF 7437 1451 124 THE FIRST AND SECOND EXCITED STATES 7437 1451 125 7437 1451 126 CALCULATED VALUES WERE USED FOR THESE CROSS SECTIONS. THE 7437 1451 127 ECIS COUPLED CHANNELS CODE WAS USED FOR DIRECT-REACTION CONT- 7437 1451 128 RIBUTIONS WHILE COMPOUND NUCLEUS CONTRIBUTIONS WERE OBTAINED 7437 1451 129 USING THE COMNUC HAUSER-FESHBACH CODE REF 9 WITH WIDTH- 7437 1451 130 FLUCTUATION CORRECTIONS. BOTH CALCULATIONS EMPLOYED DEFORMED 7437 1451 131 NEUTRON OPTICAL MODEL PARAMETERS BASED ON A MODIFICATION 7437 1451 132 REF 6 OF THE SET DEVELOPED BY DELAROCHE ET AL REF 10. 7437 1451 133 THESE CALCULATED DATA AGREE WELL WITH THE MEASURED RESULTS 7437 1451 134 OF REF 2. 7437 1451 135 7437 1451 136 MF=3 MT=53,68 INELASTIC SCATTERING CROSS SECTIONS TO THE 7437 1451 137 THIRD THROUGH EIGHTEENTH EXCITED STATES IN W184 7437 1451 138 7437 1451 139 CROSS SECTIONS FOR INELASTIC SCATTERING FROM THE THIRD 7437 1451 140 THROUGH EIGHTEENTH EXCITED STATES IN W182 WERE CALCULATED 7437 1451 141 USING THE COMNUC HAUSER-FESHBACH CODE SO ONLY COMPOUND- 7437 1451 142 NUCLEUS CONTRIBUTIONS WERE INCLUDED. ABOVE 6 MEV SUCH CROSS 7437 1451 143 SECTIONS WERE SET TO ZERO AND WERE ADDED TO THE CONTINUUM 7437 1451 144 CROSS SECTION. 7437 1451 145 7437 1451 146 MF=3 MT=91 INELASTIC SCATTERING TO THE CONTINUUM 7437 1451 147 7437 1451 148 AT LOW ENERGIES THIS CROSS SECTION REPRESENTS CONTRIBUTIONS 7437 1451 149 FROM THE (N,GAMMA N) PROCESS CALCULATED USING THE COMNUC CODE. 7437 1451 150 AT HIGHER ENERGIES THIS CROSS SECTION IS DOMINATED BY 7437 1451 151 INELASTIC SCATTERING TO THE CONTINUUM WHICH WAS CALCULATED 7437 1451 152 USING THE COMNUC CODE AND, WHERE PREEQUILIBRIUM EFFECTS ARE 7437 1451 153 IMPORTANT, WITH THE GNASH CODE. 7437 1451 154 7437 1451 155 MF=3 MT=102 RADIATIVE CAPTURE CROSS SECTIONS 7437 1451 156 7437 1451 157 AT ENERGIES BELOW 0.1 MEV THE ENDF-B/V RESULTS WERE USED 7437 1451 158 DIRECTLY. FROM 0.1 TO 6 MEV COMNUC/GNASH CALCULATIONS WERE 7437 1451 159 MADE. AT ENERGIES GREATER THAN 1 MEV A FULL TREATMENT OF THE 7437 1451 160 GAMMA-RAY CASCADE WAS INCLUDED. ABOVE 6 MEV A SIMPLE MODEL 7437 1451 161 BASED ON THE PREEQUILIBRIUM EMISSION OF GAMMA RAYS WAS 7437 1451 162 USED TO ACCOUNT FOR DIRECT-SEMIDIRECT EFFECTS. RESULTS FROM 7437 1451 163 THIS MODEL WERE NORMALIZED TO DATA REF 11 AT 14 MEV. THE 7437 1451 164 CALCULATED CAPTURE CROSS SECTIONS BETWEEN 0.5 AND 3 MEV AGREE 7437 1451 165 WELL WITH THE RECENT MEASUREMENTS OF GRENIER REF 12. 7437 1451 166 7437 1451 167 MF=3 MT=103,107 N,P AND N,ALPHA CROSS SECTIONS 7437 1451 168 7437 1451 169 ENDF-B/V NORMALIZED TO FIT QAIM(1975) VALUES 7437 1451 170 7437 1451 171 MF=4 MT=2 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS 7437 1451 172 7437 1451 173 ANGULAR DISTRIBUTIONS OBTAINED FROM ECIS COUPLED-CHANNEL 7437 1451 174 CALCULATIONS ARE EXPRESSED IN TERMS OF LEGENDRE COEFFICIENTS 7437 1451 175 IN THE CENTER OF MASS SYSTEM. 7437 1451 176 7437 1451 177 MF=4 MT=16,17 ANGULAR DISTRIBUTIONS OF NEUTRONS 7437 1451 178 FROM (N,2N) AND (N,3N) REACTIONS 7437 1451 179 7437 1451 180 ANGULAR DISTRIBUTIONS WERE OBTAINED USING THE KALBACH-MANN 7437 1451 181 SYSTEMATICS REF 13 THAT REQUIRE KNOWLEDGE OF THE PRE- 7437 1451 182 EQUILIBRIUM EMISSION FRACTION AND THE AVERAGE ENERGY OF THE 7437 1451 183 EMITTED NEUTRON. THE RESULTS ARE EXPRESSED IN TERMS OF 7437 1451 184 LEGENDRE POLYNOMIAL COEFFICIENTS IN THE LABORATORY SYSTEM. 7437 1451 185 7437 1451 186 MF=4 MT=28 ANGULAR DISTRIBUTIONS OF NEUTRONS FROM 7437 1451 187 (N,NP) AND (N,PN) REACTIONS 7437 1451 188 7437 1451 189 THESE ARE ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM. 7437 1451 190 7437 1451 191 MF=4 MT=91 ANGULAR DISTRIBUTIONS OF NEUTRONS FROM 7437 1451 192 CONTINUUM INELASTIC SCATTERING 7437 1451 193 7437 1451 194 LEGENDRE COEFFICIENTS OBTAINED FROM THE KALBACH-MANN 7437 1451 195 SYSTEMATICS ARE GIVEN IN THE LABORATORY SYSTEM. 7437 1451 196 7437 1451 197 MF=5 MT=16,17 NEUTRON EMISSION SPECTRA FROM (N,2N) 7437 1451 198 AND (N,3N) REACTIONS 7437 1451 199 7437 1451 200 HISTOGRAMS ARE GIVEN OF EMISSION SPECTRA CALCULATED USING 7437 1451 201 THE GNASH PREEQUILIBRIUM STATISTICAL MODEL CODE. 7437 1451 202 7437 1451 203 MF=5 MT=28 NEUTRON SPECTRA FROM (N,NP) AND (N,PN) 7437 1451 204 REACTIONS 7437 1451 205 7437 1451 206 FOR THESE SPECTRA ENDF-B/V RESULTS WERE USED DIRECTLY. 7437 1451 207 7437 1451 208 MF=5 MT=91 NEUTRON SPECTRA FROM THE CONTINUUM EMISSION 7437 1451 209 OF INELASTICALLY SCATTERED NEUTRONS 7437 1451 210 7437 1451 211 HISTOGRAMS ARE GIVEN OF EMISSION SPECTRA THAT INCLUDE 7437 1451 212 PREEQUILBRIUM EFFECTS AS OBTAINED FROM GNASH CALCULATIONS. 7437 1451 213 7437 1451 214 MF=12 MT=102 MULTIPLICITIES FOR GAMMA-RAY PRODUCTION FROM 7437 1451 215 RADIATIVE CAPTURE 7437 1451 216 7437 1451 217 BELOW 0.1 MEV THE MULTIPLICITIES WERE TAKEN DIRECTLY 7437 1451 218 FROM ENDF-B/V. AT HIGHER ENERGIES MULTIPLICITIES WERE 7437 1451 219 OBTAINED DIRECTLY FROM COMNUC AND GNASH STATISTICAL MODEL 7437 1451 220 CALCULATIONS. 7437 1451 221 7437 1451 222 MF=13 MT=4,16,17 GAMMA-RAY PRODUCTION CROSS SECTIONS FROM 7437 1451 223 INELASTIC, (N,2N), AND (N,3N) REACTIONS 7437 1451 224 7437 1451 225 THE CROSS SECTION FOR DISCRETE PHOTONS OCCURING THROUGH 7437 1451 226 INELASTIC SCATTERING ARE BASED ON THE LEVEL EXCITATION CROSS 7437 1451 227 SECTION IN MF=3, MT=51-68. FOR GAMMA-RAY CROSS SECTIONS 7437 1451 228 FROM CONTINUUM INELASTIC, (N,2N), AND (N,3N) REACTIONS, 7437 1451 229 GNASH RESULTS WERE USED DIRECTLY. 7437 1451 230 7437 1451 231 MF=14 MT=4,16,17,102 ANGULAR DISTRIBUTIONS OF GAMMA-RAYS 7437 1451 232 FROM INELASTIC SCATTERING, (N,2N), 7437 1451 233 (N,3N), AND RADIATIVE CAPTURE REACTIONS 7437 1451 234 7437 1451 235 ALL GAMMA-RAYS ARE ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM. 7437 1451 236 7437 1451 237 MF=15 MT=16,17,91 ENERGY SPECTRA OF GAMMA-RAYS FROM 7437 1451 238 (N,2N), (N,3N) AND CONTINUUM INELASTIC 7437 1451 239 REACTIONS 7437 1451 240 7437 1451 241 THE SPECTRA AT ALL ENERGIES ARE BASED DIRECTLY ON PREEQUI- 7437 1451 242 LIBRIUM HAUSER-FESHBACH CALCULATIONS MADE USING THE GNASH 7437 1451 243 NUCLEAR MODEL CODE. 7437 1451 244 7437 1451 245 MF=15 MT=102 ENERGY SPECTRA OF GAMMA-RAYS FROM RADIATIVE 7437 1451 246 CAPTURE 7437 1451 247 7437 1451 248 BELOW 0.1 MEV THE SPECTRA ARE TAKEN FROM ENDF-B/V. 7437 1451 249 FROM 0.1 TO 10 MEV THE SPECTRA ARE TAKEN FROM GNASH STATISTI- 7437 1451 250 CAL MODEL CALCULATIONS. ABOVE 10 MEV A SIMPLE PREEQUILIBRIUM 7437 1451 251 -LIKE MODEL WAS USED TO CALCULATE THE SPECTRA. 7437 1451 252 7437 1451 253 7437 1451 254 REFERENCES FOR MF=3,4,12,13,15 7437 1451 255 7437 1451 256 1. D.LISTER ET AL, PHYS. REV. 162,1077 (1967) 7437 1451 257 2. P.GUENTHER, A.B.SMITH, TO BE PUBLISHED (1981) 7437 1451 258 3. D.FOSTER AND D.GLASGOW, PHYS. REV. C3,576 (1971) 7437 1451 259 4. R.C.MARTIN ET AL, BULL. AM. PHYS. SOC. 12,106 (1967) 7437 1451 260 5. J.RAYNAL,IAEA-SMR-9/8 (1972) 7437 1451 261 6. E.D.ARTHUR ET AL, LOS ALAMOS REPORT LA 8630 PR, P.2 (1980) 7437 1451 262 7. P.G.YOUNG AND E.D.ARTHUR, LOS ALAMOS REPORT LA 6947 (1977) 7437 1451 263 8. J.FREHAUT ET AL, BNL-NCS-51245, VOL.1,P.399 (1980) 7437 1451 264 9. C.DUNFORD, ATOMICS INTERNATIONAL REPORT AI-AEC-12931 (1970) 7437 1451 265 10. J.P.DELAROCHE ET AL, NBS SPECIAL PUBLICATION 594,P.336 (1980) 7437 1451 266 11. M.BUDNAR ET AL, INDC(YUG)-6/2 (1979) 7437 1451 267 12. G.GRENIER ET AL, NBS SPECIAL PUBLICATION 594,P.323 (1980) 7437 1451 268 13. C.KALBACH AND F.MANN, BNL-NCS-5/245,P.689 (1980) 7437 1451 269 7437 1451 270 1 451 274 07437 1451 271 2 151 88 07437 1451 272 3 102 32 07437 1451 273 3 107 10 07437 1451 274 7437 1 0 275 7437 0 0 276 7.418400+4 1.823700+2 0 0 1 07437 2151 277 7.418400+4 1.000000+0 0 0 2 07437 2151 278 1.000000-5 2.650000+3 1 2 0 07437 2151 279 0.000000+0 7.978900-1 0 0 1 07437 2151 280 1.823700+2 0.000000+0 0 0 228 387437 2151 281 -1.176000+1 5.000000-1 6.963000-2 1.630000-3 6.800000-2 0.000000+07437 2151 282 1.020000+2 5.000000-1 7.120000-2 3.200000-3 6.800000-2 0.000000+07437 2151 283 1.845000+2 5.000000-1 1.163000+0 1.100000+0 6.300000-2 0.000000+07437 2151 284 3.110000+2 5.000000-1 1.290000-1 7.799990-2 5.100000-2 0.000000+07437 2151 285 4.235000+2 5.000000-1 1.210000-1 5.200000-2 6.899990-2 0.000000+07437 2151 286 6.815000+2 5.000000-1 7.880000-1 7.100000-1 7.799990-2 0.000000+07437 2151 287 7.030000+2 5.000000-1 7.450000-2 6.500000-3 6.800000-2 0.000000+07437 2151 288 7.835000+2 5.000000-1 8.900000-2 2.100000-2 6.800000-2 0.000000+07437 2151 289 7.990000+2 5.000000-1 1.827000+0 1.770000+0 5.700000-2 0.000000+07437 2151 290 9.590000+2 5.000000-1 1.610000+0 1.500000+0 1.100000-1 0.000000+07437 2151 291 9.980000+2 5.000000-1 1.650000-1 1.100000-1 5.500000-2 0.000000+07437 2151 292 1.078000+3 5.000000-1 1.030000-1 3.500000-2 6.800000-2 0.000000+07437 2151 293 1.090000+3 5.000000-1 3.465000+0 3.370000+0 9.500000-2 0.000000+07437 2151 294 1.133000+3 5.000000-1 3.900000-1 3.300000-1 6.000000-2 0.000000+07437 2151 295 1.149000+3 5.000000-1 8.299990-2 1.500000-2 6.800000-2 0.000000+07437 2151 296 1.187000+3 5.000000-1 8.600000-2 1.800000-2 6.800000-2 0.000000+07437 2151 297 1.261000+3 5.000000-1 1.263000+0 1.200000+0 6.300000-2 0.000000+07437 2151 298 1.333500+3 5.000000-1 8.600000-2 1.800000-2 6.800000-2 0.000000+07437 2151 299 1.400000+3 5.000000-1 3.476000+0 3.400000+0 7.600000-2 0.000000+07437 2151 300 1.422000+3 5.000000-1 5.800000-1 5.000000-1 8.000000-2 0.000000+07437 2151 301 1.515000+3 5.000000-1 1.658000+0 1.600000+0 5.800000-2 0.000000+07437 2151 302 1.551000+3 5.000000-1 1.440000-1 7.600000-2 6.800000-2 0.000000+07437 2151 303 1.612000+3 5.000000-1 9.300000-2 2.500000-2 6.800000-2 0.000000+07437 2151 304 1.652000+3 5.000000-1 4.200000-1 3.400000-1 8.000000-2 0.000000+07437 2151 305 1.676000+3 5.000000-1 1.030000-1 3.500000-2 6.800000-2 0.000000+07437 2151 306 1.721000+3 5.000000-1 8.400000-2 1.600000-2 6.800000-2 0.000000+07437 2151 307 1.790000+3 5.000000-1 1.405000+0 1.340000+0 6.500000-2 0.000000+07437 2151 308 1.870000+3 5.000000-1 9.800000-2 3.000000-2 6.800000-2 0.000000+07437 2151 309 1.918000+3 5.000000-1 3.200000-1 2.450000-1 7.500000-2 0.000000+07437 2151 310 2.045000+3 5.000000-1 1.460000+0 1.400000+0 6.000000-2 0.000000+07437 2151 311 2.080000+3 5.000000-1 1.545000+0 1.490000+0 5.500000-2 0.000000+07437 2151 312 2.110000+3 5.000000-1 9.700000-1 9.000000-1 7.000000-2 0.000000+07437 2151 313 2.211000+3 5.000000-1 3.430000-1 2.750000-1 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5.000000+4 7.396570+1 0.000000+0 1.701210-2 7.306000-2 0.000000+07437 2151 329 1.000000+5 6.816860+1 0.000000+0 1.567880-2 7.306000-2 0.000000+07437 2151 330 1.823710+2 0.000000+0 1 0 2 07437 2151 331 5.000000-1 0.000000+0 5 0 42 67437 2151 332 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07437 2151 333 2.650000+3 7.993150+1 0.000000+0 1.438770-3 7.306000-2 0.000000+07437 2151 334 5.000000+3 7.962340+1 0.000000+0 1.433220-3 7.306000-2 0.000000+07437 2151 335 1.000000+4 7.897350+1 0.000000+0 1.421520-3 7.306000-2 0.000000+07437 2151 336 2.000000+4 7.768900+1 0.000000+0 1.398400-3 7.306000-2 0.000000+07437 2151 337 5.000000+4 7.396570+1 0.000000+0 1.331380-3 7.306000-2 0.000000+07437 2151 338 1.000000+5 6.816860+1 0.000000+0 1.227030-3 7.306000-2 0.000000+07437 2151 339 1.500000+0 0.000000+0 5 0 42 67437 2151 340 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07437 2151 341 2.650000+3 4.206880+1 0.000000+0 7.572390-4 7.306000-2 0.000000+07437 2151 342 5.000000+3 4.190620+1 0.000000+0 7.543110-4 7.306000-2 0.000000+07437 2151 343 1.000000+4 4.156300+1 0.000000+0 7.481340-4 7.306000-2 0.000000+07437 2151 344 2.000000+4 4.088490+1 0.000000+0 7.359280-4 7.306000-2 0.000000+07437 2151 345 5.000000+4 3.891960+1 0.000000+0 7.005520-4 7.306000-2 0.000000+07437 2151 346 1.000000+5 3.586020+1 0.000000+0 6.454840-4 7.306000-2 0.000000+07437 2151 347 1.823710+2 0.000000+0 2 0 2 07437 2151 348 1.500000+0 0.000000+0 5 0 42 67437 2151 349 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07437 2151 350 2.650000+3 4.206900+1 0.000000+0 6.100000-3 7.306000-2 0.000000+07437 2151 351 5.000000+3 4.190620+1 0.000000+0 6.076390-3 7.306000-2 0.000000+07437 2151 352 1.000000+4 4.156300+1 0.000000+0 6.026640-3 7.306000-2 0.000000+07437 2151 353 2.000000+4 4.088490+1 0.000000+0 5.928310-3 7.306000-2 0.000000+07437 2151 354 5.000000+4 3.891960+1 0.000000+0 5.643330-3 7.306000-2 0.000000+07437 2151 355 1.000000+5 3.586020+1 0.000000+0 5.199730-3 7.306000-2 0.000000+07437 2151 356 2.500000+0 0.000000+0 5 0 42 67437 2151 357 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07437 2151 358 2.650000+3 3.052300+1 0.000000+0 4.426000-3 7.306000-2 0.000000+07437 2151 359 5.000000+3 3.042980+1 0.000000+0 4.412310-3 7.306000-2 0.000000+07437 2151 360 1.000000+4 3.017930+1 0.000000+0 4.375990-3 7.306000-2 0.000000+07437 2151 361 2.000000+4 2.968440+1 0.000000+0 4.304230-3 7.306000-2 0.000000+07437 2151 362 5.000000+4 2.825030+1 0.000000+0 4.096280-3 7.306000-2 0.000000+07437 2151 363 1.000000+5 2.601870+1 0.000000+0 3.772710-3 7.306000-2 0.000000+07437 2151 364 7437 2 0 365 7437 0 0 366 7.418400+4 1.823700+2 0 0 0 07437 3102 367 5.754400+6 5.754400+6 0 0 2 857437 3102 368 6 5 85 2 0 07437 3102 369 1.000000-5 2.040000-6 2.530000-2 1.025000-4 5.000000+2 1.440000-27437 3102 370 1.000000+3 2.030000-2 2.000000+3 2.840000-2 2.650000+3 3.250000-27437 3102 371 2.650000+3 0.000000+0 1.000000+4 0.000000+0 1.000000+5 0.000000+07437 3102 372 1.000000+5 1.640000-1 1.100000+5 1.380600-1 1.200000+5 1.187400-17437 3102 373 1.400000+5 9.297200-2 1.600000+5 7.766900-2 1.800000+5 6.843200-27437 3102 374 2.000000+5 6.300000-2 2.200000+5 5.952100-2 2.400000+5 5.686800-27437 3102 375 2.600000+5 5.482200-2 2.800000+5 5.323400-2 3.000000+5 5.200000-27437 3102 376 3.200000+5 5.093300-2 3.400000+5 4.995200-2 3.600000+5 4.911700-27437 3102 377 3.800000+5 4.846000-2 4.000000+5 4.800000-2 4.200000+5 4.769200-27437 3102 378 4.400000+5 4.746600-2 4.600000+5 4.730300-2 4.800000+5 4.718500-27437 3102 379 5.000000+5 4.710000-2 5.200000+5 4.703400-2 5.400000+5 4.699300-27437 3102 380 5.600000+5 4.699800-2 5.800000+5 4.706300-2 6.000000+5 4.720000-27437 3102 381 6.200000+5 4.742200-2 6.400000+5 4.771500-2 6.600000+5 4.805500-27437 3102 382 6.800000+5 4.842300-2 7.000000+5 4.880000-2 7.200000+5 4.915900-27437 3102 383 7.400000+5 4.951300-2 7.600000+5 4.989800-2 7.800000+5 5.035100-27437 3102 384 8.000000+5 5.090000-2 8.500000+5 5.241600-2 9.000000+5 5.390000-27437 3102 385 9.500000+5 5.533400-2 1.000000+6 5.670000-2 1.100000+6 5.648700-27437 3102 386 1.200000+6 5.266100-2 1.300000+6 4.766200-2 1.400000+6 4.287100-27437 3102 387 1.500000+6 3.890000-2 1.600000+6 3.565100-2 1.700000+6 3.278400-27437 3102 388 1.800000+6 3.022100-2 1.900000+6 2.790700-2 2.000000+6 2.580000-27437 3102 389 2.200000+6 2.213000-2 2.400000+6 1.909900-2 2.600000+6 1.659600-27437 3102 390 2.800000+6 1.452300-2 3.000000+6 1.280000-2 3.500000+6 9.192500-37437 3102 391 4.000000+6 6.500000-3 4.500000+6 4.395700-3 5.000000+6 2.840000-37437 3102 392 5.500000+6 1.741900-3 6.000000+6 1.090000-3 7.000000+6 5.153700-47437 3102 393 8.000000+6 3.840000-4 9.000000+6 5.759600-4 1.000000+7 9.470000-47437 3102 394 1.100000+7 1.239300-3 1.200000+7 1.460000-3 1.300000+7 1.377900-37437 3102 395 1.400000+7 1.060000-3 1.500000+7 7.446000-4 1.600000+7 4.500000-47437 3102 396 1.700000+7 2.476200-4 1.800000+7 1.410000-4 1.900000+7 8.281900-57437 3102 397 2.000000+7 5.000000-5 0.000000+0 0.000000+0 0.000000+0 0.000000+07437 3102 398 7437 3 0 399 7.418400+4 1.823700+2 0 0 0 07437 3107 400 7.362000+6 7.362000+6 0 0 1 217437 3107 401 21 2 0 0 0 07437 3107 402 1.000000-5 0.000000+0 2.530000-2 0.000000+0 1.100000+7 0.000000+07437 3107 403 1.150000+7 1.978500-5 1.200000+7 5.465500-5 1.250000+7 1.197000-47437 3107 404 1.300000+7 2.300000-4 1.350000+7 3.991900-4 1.400000+7 6.325000-47437 3107 405 1.450000+7 9.474300-4 1.500000+7 1.408800-3 1.550000+7 2.070000-37437 3107 406 1.600000+7 2.846300-3 1.650000+7 3.507500-3 1.700000+7 4.025000-37437 3107 407 1.750000+7 4.506600-3 1.800000+7 4.997200-3 1.850000+7 5.519100-37437 3107 408 1.900000+7 6.095000-3 1.950000+7 6.737300-3 2.000000+7 7.417500-37437 3107 409 7437 3 0 410 7437 0 0 411 0 0 0 412 7.418600+4 1.843600+2 1 0 0 07443 1451 1 0.000000+0 0.000000+0 0 0 0 67443 1451 2 1.000000+0 0.000000+0 0 0 10 67443 1451 3 0.000000+0 0.000000+0 0 0 260 57443 1451 4 74-W-186 LANL,ANL+ EVAL-DEC80 ARTHUR,YOUNG,SMITH,PHILIS 7443 1451 5 DIST-FEB90 900202 7443 1451 6 ----ENDF/B-VI MATERIAL 7443 7443 1451 7 -----INCIDENT NEUTRON DATA 7443 1451 8 ------ENDF-6 FORMAT 7443 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************7443 1451 10 ACTIVATION II 7443 1451 11 ******************************************************************7443 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 7443 1451 13 * * * * * * *7443 1451 14 7443 1451 15 SUMMARY OF CONTRIBUTIONS 7443 1451 16 7443 1451 17 1. MF=2,MT=151 AND MF=3,MT=103,107 TAKEN FROM ENDF/B-V. 7443 1451 18 2. TOTAL CROSS SECTION ABOVE 100 KEV EVALUATED BY SMITH. 7443 1451 19 3. ALL OTHER DATA OBTAINED FROM MODEL CALCULATIONS OPTIMIZED TO 7443 1451 20 EXPERIMENT BY ARTHUR, YOUNG, AND PHILIS. 7443 1451 21 7443 1451 22 **************************************************************** 7443 1451 23 7443 1451 24 MF=1 MT=451 DESCRIPTIVE INFORMATION 7443 1451 25 7443 1451 26 ATOMIC MASS AND Q VALUES A.H. WAPSTRA AND K. BOS 7443 1451 27 ATOMIC DATA AND NUCLEAR DATA TABLES 19, 177(1977) 7443 1451 28 7443 1451 29 MF=2 MT=151 RESONANCE PARAMETERS 7443 1451 30 7443 1451 31 RESOLVED RESONANCE EVALUATION 7443 1451 32 POTENTIAL SCATTERING XSEC = 8.0+-1.0 B AT E=0 7443 1451 33 2200 M/S CROSS SECTION (BARNS) 7443 1451 34 CALC MEAS (REF-1) 7443 1451 35 CAP 37.5 38+-2 7443 1451 36 SCAT 0.39 7443 1451 37 RESOLVED RESONANCE PARAMETERS 7443 1451 38 18.81 EV FROM EVALUATION OF REF 1 AND 3 PLUS 7443 1451 39 ADJUSTMENT FROM FIT TO CAPTURE XSEC7443 1451 40 100 - 250 EV FROM EVALUATION OF REFERENCES 1-3. 7443 1451 41 250 - 3200 EV FROM EVALUATION OF REFERENCES 2-3. 7443 1451 42 UNRESOLVED RESONANCE EVALUATION 7443 1451 43 POTENTIAL SCATTERING XSEC = 8.5+-1.0 B AT E=0 7443 1451 44 TOTAL XSEC = 9.1 B AT E=100KEV (CALCULATED) 7443 1451 45 UNRESOLVED RESONANCE PARAMETERS FROM AUTOMATED OPTIMIZED FIT TO7443 1451 46 THE EVALUATED MEASURED CAPTURE CROSS SECTION. 7443 1451 47 AV L=0 LEVEL SPACING (E=0) = 99.1 EV, ENERGY DEP. FROM REF 4 7443 1451 48 AV CAPTURE LEVEL WIDTH = 0.0530 EV, ENERGY INDEPENDENT 7443 1451 49 L=0 STRENGTH FUNCTION = 2.2E-4 , ENERGY INDEPENDENT 7443 1451 50 L=1 STRENGTH FUNCTION = 0.252E-4 , ENERGY INDEPENDENT 7443 1451 51 L=2 STRENGTH FUNCTION = 1.45E-4 , ENERGY INDEPENDENT 7443 1451 52 AVERAGE CAPTURE CROSS SECTION UNCERTAINTY AT ENERGY E 7443 1451 53 E (KEV) UNC. (() 7443 1451 54 100 11 7443 1451 55 90 8 7443 1451 56 45 8 7443 1451 57 22.5 14 7443 1451 58 10 11 7443 1451 59 4.5 17 7443 1451 60 RESONANCE INTEGRAL(CAPT.) 522 B CALC., 490+-50 B MEAS. (REF-5) 7443 1451 61 7443 1451 62 REFERENCES 7443 1451 63 1. BNL-325,2ND EDITION, SUPPLEMENT 2, GOLDBERG ET AL (1966) 7443 1451 64 2. Z.M.BARTOLOME ET AL, NUCL.SCI.ENG. 37, P137 (1969) 7443 1451 65 3. F.J.RAHN AND H.CAMARDA, PERSONAL COMMUNICATION, COLUMBIA(1970)7443 1451 66 4. J.L.COOK ET AL AAEC/TM-392 (1967) 7443 1451 67 5. M.DRAKE, (1968) FOR AMERICAN INSTITUTE OF PHYS. HANDBOOK(1972)7443 1451 68 7443 1451 69 MF=3 MT=1 TOTAL CROSS SECTION 7443 1451 70 7443 1451 71 THE EVALUATED TOTAL CROSS SECTION RELIES UPON THE EXPERIMEN- 7443 1451 72 TAL RESULTS OF LISTER ET AL REF 1 FROM 0.1 TO 0.65 MEV. 7443 1451 73 (BELOW 0.1 MEV THE ENDF-B/V RESULTS IN THE UNRESOLVED RESONANCE 7443 1451 74 RANGE WERE USED DIRECTLY). FROM 0.65 TO 2.3 MEV THE NEWLY 7443 1451 75 MEASURED RESULTS OF GUENTHER ET AL REF 2 WERE USED SINCE 7443 1451 76 THESE DATA ARE CONSISTENT WITH BOTH HIGHER AND LOWER ENERGY 7443 1451 77 DATA REF 1,3,4. FROM 2.3 TO 5.0 MEV THE GUENTHER RESULTS AND 7443 1451 78 THOSE OF FOSTER AND GLASGOW REF 3 WERE AVERAGED TO PRODUCE 7443 1451 79 THE EVALUATED DATA. BETWEEN 5 AND 15 MEV THE EVALUATION 7443 1451 80 RELIED ON THE FOSTER RESULTS. NO EXPERIMENTAL DATA EXIST 7443 1451 81 ABOVE 15 MEV SO THAT RESULTS FROM CALCULATIONS USING THE 7443 1451 82 COUPLED CHANNELS CODE ECIS REF 5 WERE ADOPTED. THE OPTICAL 7443 1451 83 PARAMATERS USED SEE REF 6 GAVE GOOD AGREEMENT TO DATA IN 7443 1451 84 THE ENERGY RANGE FROM 0.1 TO 15 MEV. 7443 1451 85 7443 1451 86 MF=3 MT=2 ELASTIC CROSS SECTION 7443 1451 87 7443 1451 88 THE EVALUATED ELASTIC CROSS SECTION WAS OBTAINED BY SUBTRAC- 7443 1451 89 TING THE NONELASTIC CROSS SECTION FROM THE EVALUATED TOTAL 7443 1451 90 CROSS SECTION. 7443 1451 91 THE EVALUATED DATA ARE IN GOOD AGREEMENT WITH RECENT MEASURE- 7443 1451 92 MENTS AT ENERGIES BELOW 4 MEV REF 2. 7443 1451 93 7443 1451 94 MF=3 MT=4 TOTAL INELASTIC CROSS SECTION 7443 1451 95 7443 1451 96 EQUAL TO THE SUM OF THE INELASTIC LEVEL EXCITATION AND 7443 1451 97 CONTINUUM CROSS SECTIONS. 7443 1451 98 7443 1451 99 MF=3 MT=16 (N,2N) CROSS SECTIONS 7443 1451 100 7443 1451 101 MULTISTEP HAUSER-FESHBACH CALCULATIONS WITH PREEQUILIBRIUM 7443 1451 102 CORRECTIONS WERE MADE USING THE GNASH CODE REF 7 AND 7443 1451 103 DEFORMED OPTICAL MODEL TRANSMISSION COEFFICIENTS FROM THE ECIS 7443 1451 104 COUPLED-CHANNELS CODE. THE RESULTS AGREE WELL WITH THE ISO- 7443 1451 105 TOPIC DATA OF FREHAUT ET AL REF 8 MEASURED FROM THRESHOLD TO 7443 1451 106 15 MEV. 7443 1451 107 7443 1451 108 MF=3 MT=17 (N,3N) CROSS SECTIONS 7443 1451 109 7443 1451 110 OBTAINED FROM PREEQUILIBRIUM HAUSER-FESHBACH CALCULATIONS 7443 1451 111 MADE WITH THE GNASH CODE. 7443 1451 112 7443 1451 113 MF=3 MT=28 (N,PN) AND (N,NP) CROSS SECTIONS 7443 1451 114 7443 1451 115 THESE VALUES WERE TAKEN DIRECTLY FROM ENDF-B/V. 7443 1451 116 7443 1451 117 MF=3 MT=51,52 INELASTIC CROSS SECTIONS FOR EXCITATION OF 7443 1451 118 THE FIRST AND SECOND EXCITED STATES 7443 1451 119 7443 1451 120 CALCULATED VALUES WERE USED FOR THESE CROSS SECTIONS. THE 7443 1451 121 ECIS COUPLED CHANNELS CODE WAS USED FOR DIRECT-REACTION CONT- 7443 1451 122 RIBUTIONS WHILE COMPOUND NUCLEUS CONTRIBUTIONS WERE OBTAINED 7443 1451 123 USING THE COMNUC HAUSER-FESHBACH CODE REF 9 WITH WIDTH- 7443 1451 124 FLUCTUATION CORRECTIONS. BOTH CALCULATIONS EMPLOYED DEFORMED 7443 1451 125 NEUTRON OPTICAL MODEL PARAMETERS BASED ON A MODIFICATION 7443 1451 126 REF 6 OF THE SET DEVELOPED BY DELAROCHE ET AL REF 10. 7443 1451 127 THESE CALCULATED DATA AGREE WELL WITH THE MEASURED RESULTS 7443 1451 128 OF REF 2. 7443 1451 129 7443 1451 130 MF=3 MT=53,68 INELASTIC SCATTERING CROSS SECTIONS TO THE 7443 1451 131 THIRD THROUGH EIGHTEENTH EXCITED STATES IN W186 7443 1451 132 7443 1451 133 CROSS SECTIONS FOR INELASTIC SCATTERING FROM THE THIRD 7443 1451 134 THROUGH EIGHTEENTH EXCITED STATES IN W182 WERE CALCULATED 7443 1451 135 USING THE COMNUC HAUSER-FESHBACH CODE SO ONLY COMPOUND- 7443 1451 136 NUCLEUS CONTRIBUTIONS WERE INCLUDED. ABOVE 6 MEV SUCH CROSS 7443 1451 137 SECTIONS WERE SET TO ZERO AND WERE ADDED TO THE CONTINUUM 7443 1451 138 CROSS SECTION. 7443 1451 139 7443 1451 140 MF=3 MT=91 INELASTIC SCATTERING TO THE CONTINUUM 7443 1451 141 7443 1451 142 AT LOW ENERGIES THIS CROSS SECTION REPRESENTS CONTRIBUTIONS 7443 1451 143 FROM THE (N,GAMMA N) PROCESS CALCULATED USING THE COMNUC CODE. 7443 1451 144 AT HIGHER ENERGIES THIS CROSS SECTION IS DOMINATED BY 7443 1451 145 INELASTIC SCATTERING TO THE CONTINUUM WHICH WAS CALCULATED 7443 1451 146 USING THE COMNUC CODE AND, WHERE PREEQUILIBRIUM EFFECTS ARE 7443 1451 147 IMPORTANT, WITH THE GNASH CODE. 7443 1451 148 7443 1451 149 MF=3 MT=102 RADIATIVE CAPTURE CROSS SECTIONS 7443 1451 150 7443 1451 151 AT ENERGIES BELOW 0.1 MEV THE ENDF-B/V RESULTS WERE USED 7443 1451 152 DIRECTLY. FROM 0.1 TO 6 MEV COMNUC/GNASH CALCULATIONS WERE 7443 1451 153 MADE. AT ENERGIES GREATER THAN 1 MEV A FULL TREATMENT OF THE 7443 1451 154 GAMMA-RAY CASCADE WAS INCLUDED. ABOVE 6 MEV A SIMPLE MODEL 7443 1451 155 BASED ON THE PREEQUILIBRIUM EMISSION OF GAMMA RAYS WAS 7443 1451 156 USED TO ACCOUNT FOR DIRECT-SEMIDIRECT EFFECTS. RESULTS FROM 7443 1451 157 THIS MODEL WERE NORMALIZED TO DATA REF 11 AT 14 MEV. THE 7443 1451 158 CALCULATED CAPTURE CROSS SECTIONS BETWEEN 0.5 AND 3 MEV AGREE 7443 1451 159 WELL WITH THE RECENT MEASUREMENTS OF GRENIER REF 12. 7443 1451 160 7443 1451 161 MF=3 MT=103,107 N,P AND N,ALPHA CROSS SECTIONS 7443 1451 162 7443 1451 163 ENDF-B/V NORMALIZED TO FIT QAIM(1975) VALUES 7443 1451 164 7443 1451 165 MF=4 MT=2 ELASTIC SCATTERING ANGULAR DISTRIBUTIONS 7443 1451 166 7443 1451 167 ANGULAR DISTRIBUTIONS OBTAINED FROM ECIS COUPLED-CHANNEL 7443 1451 168 CALCULATIONS ARE EXPRESSED IN TERMS OF LEGENDRE COEFFICIENTS 7443 1451 169 IN THE CENTER OF MASS SYSTEM. 7443 1451 170 7443 1451 171 MF=4 MT=16,17 ANGULAR DISTRIBUTIONS OF NEUTRONS 7443 1451 172 FROM (N,2N) AND (N,3N) REACTIONS 7443 1451 173 7443 1451 174 ANGULAR DISTRIBUTIONS WERE OBTAINED USING THE KALBACH-MANN 7443 1451 175 SYSTEMATICS REF 13 THAT REQUIRE KNOWLEDGE OF THE PRE- 7443 1451 176 EQUILIBRIUM EMISSION FRACTION AND THE AVERAGE ENERGY OF THE 7443 1451 177 EMITTED NEUTRON. THE RESULTS ARE EXPRESSED IN TERMS OF 7443 1451 178 LEGENDRE POLYNOMIAL COEFFICIENTS IN THE LABORATORY SYSTEM. 7443 1451 179 7443 1451 180 MF=4 MT=28 ANGULAR DISTRIBUTIONS OF NEUTRONS FROM 7443 1451 181 (N,NP) AND (N,PN) REACTIONS 7443 1451 182 7443 1451 183 THESE ARE ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM. 7443 1451 184 7443 1451 185 MF=4 MT=91 ANGULAR DISTRIBUTIONS OF NEUTRONS FROM 7443 1451 186 CONTINUUM INELASTIC SCATTERING 7443 1451 187 7443 1451 188 LEGENDRE COEFFICIENTS OBTAINED FROM THE KALBACH-MANN 7443 1451 189 SYSTEMATICS ARE GIVEN IN THE LABORATORY SYSTEM. 7443 1451 190 7443 1451 191 MF=5 MT=16,17 NEUTRON EMISSION SPECTRA FROM (N,2N) 7443 1451 192 AND (N,3N) REACTIONS 7443 1451 193 7443 1451 194 HISTOGRAMS ARE GIVEN OF EMISSION SPECTRA CALCULATED USING 7443 1451 195 THE GNASH PREEQUILIBRIUM STATISTICAL MODEL CODE. 7443 1451 196 7443 1451 197 MF=5 MT=28 NEUTRON SPECTRA FROM (N,NP) AND (N,PN) 7443 1451 198 REACTIONS 7443 1451 199 7443 1451 200 FOR THESE SPECTRA ENDF-B/V RESULTS WERE USED DIRECTLY. 7443 1451 201 7443 1451 202 MF=5 MT=91 NEUTRON SPECTRA FROM THE CONTINUUM EMISSION 7443 1451 203 OF INELASTICALLY SCATTERED NEUTRONS 7443 1451 204 7443 1451 205 HISTOGRAMS ARE GIVEN OF EMISSION SPECTRA THAT INCLUDE 7443 1451 206 PREEQUILBRIUM EFFECTS AS OBTAINED FROM GNASH CALCULATIONS. 7443 1451 207 7443 1451 208 MF=12 MT=102 MULTIPLICITIES FOR GAMMA-RAY PRODUCTION FROM 7443 1451 209 RADIATIVE CAPTURE 7443 1451 210 7443 1451 211 BELOW 0.1 MEV THE MULTIPLICITIES WERE TAKEN DIRECTLY 7443 1451 212 FROM ENDF-B/V. AT HIGHER ENERGIES MULTIPLICITIES WERE 7443 1451 213 OBTAINED DIRECTLY FROM COMNUC AND GNASH STATISTICAL MODEL 7443 1451 214 CALCULATIONS. 7443 1451 215 7443 1451 216 MF=13 MT=4,16,17 GAMMA-RAY PRODUCTION CROSS SECTIONS FROM 7443 1451 217 INELASTIC, (N,2N), AND (N,3N) REACTIONS 7443 1451 218 7443 1451 219 THE CROSS SECTION FOR DISCRETE PHOTONS OCCURING THROUGH 7443 1451 220 INELASTIC SCATTERING ARE BASED ON THE LEVEL EXCITATION CROSS 7443 1451 221 SECTION IN MF=3, MT=51-68. FOR GAMMA-RAY CROSS SECTIONS 7443 1451 222 FROM CONTINUUM INELASTIC, (N,2N), AND (N,3N) REACTIONS, 7443 1451 223 GNASH RESULTS WERE USED DIRECTLY. 7443 1451 224 7443 1451 225 MF=14 MT=4,16,17,102 ANGULAR DISTRIBUTIONS OF GAMMA-RAYS 7443 1451 226 FROM INELASTIC SCATTERING, (N,2N), 7443 1451 227 (N,3N), AND RADIATIVE CAPTURE REACTIONS 7443 1451 228 7443 1451 229 ALL GAMMA-RAYS ARE ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM. 7443 1451 230 7443 1451 231 MF=15 MT=16,17,91 ENERGY SPECTRA OF GAMMA-RAYS FROM 7443 1451 232 (N,2N), (N,3N) AND CONTINUUM INELASTIC 7443 1451 233 REACTIONS 7443 1451 234 7443 1451 235 THE SPECTRA AT ALL ENERGIES ARE BASED DIRECTLY ON PREEQUI- 7443 1451 236 LIBRIUM HAUSER-FESHBACH CALCULATIONS MADE USING THE GNASH 7443 1451 237 NUCLEAR MODEL CODE. 7443 1451 238 7443 1451 239 MF=15 MT=102 ENERGY SPECTRA OF GAMMA-RAYS FROM RADIATIVE 7443 1451 240 CAPTURE 7443 1451 241 7443 1451 242 BELOW 0.1 MEV THE SPECTRA ARE TAKEN FROM ENDF-B/V. 7443 1451 243 FROM 0.1 TO 10 MEV THE SPECTRA ARE TAKEN FROM GNASH STATISTI- 7443 1451 244 CAL MODEL CALCULATIONS. ABOVE 10 MEV A SIMPLE PREEQUILIBRIUM 7443 1451 245 -LIKE MODEL WAS USED TO CALCULATE THE SPECTRA. 7443 1451 246 7443 1451 247 7443 1451 248 REFERENCES FOR MF=3,4,12,13,15 7443 1451 249 7443 1451 250 1. D.LISTER ET AL, PHYS. REV. 162,1077 (1967) 7443 1451 251 2. P.GUENTHER, A.B.SMITH, TO BE PUBLISHED (1981) 7443 1451 252 3. D.FOSTER AND D.GLASGOW, PHYS. REV. C3,576 (1971) 7443 1451 253 4. R.C.MARTIN ET AL, BULL. AM. PHYS. SOC. 12,106 (1967) 7443 1451 254 5. J.RAYNAL,IAEA-SMR-9/8 (1972) 7443 1451 255 6. E.D.ARTHUR ET AL, LOS ALAMOS REPORT LA 8630 PR, P.2 (1980) 7443 1451 256 7. P.G.YOUNG AND E.D.ARTHUR, LOS ALAMOS REPORT LA 6947 (1977) 7443 1451 257 8. J.FREHAUT ET AL, BNL-NCS-51245, VOL.1,P.399 (1980) 7443 1451 258 9. C.DUNFORD, ATOMICS INTERNATIONAL REPORT AI-AEC-12931 (1970) 7443 1451 259 10. J.P.DELAROCHE ET AL, NBS SPECIAL PUBLICATION 594,P.336 (1980) 7443 1451 260 11. M.BUDNAR ET AL, INDC(YUG)-6/2 (1979) 7443 1451 261 12. G.GRENIER ET AL, NBS SPECIAL PUBLICATION 594,P.323 (1980) 7443 1451 262 13. C.KALBACH AND F.MANN, BNL-NCS-5/245,P.689 (1980) 7443 1451 263 7443 1451 264 1 451 269 07443 1451 265 2 151 90 07443 1451 266 3 16 13 07443 1451 267 3 102 32 07443 1451 268 3 107 12 07443 1451 269 7443 1 0 270 7443 0 0 271 7.418600+4 1.843600+2 0 0 1 07443 2151 272 7.418600+4 1.000000+0 0 0 2 07443 2151 273 1.000000-5 3.200000+3 1 2 0 07443 2151 274 0.000000+0 7.978900-1 0 0 1 07443 2151 275 1.843600+2 0.000000+0 0 0 240 407443 2151 276 1.881000+1 5.000000-1 3.290000-1 2.800000-1 4.900000-2 0.000000+07443 2151 277 1.704000+2 5.000000-1 8.900000-2 2.500000-2 6.400000-2 0.000000+07443 2151 278 2.040000+2 5.000000-1 7.250000-2 7.500000-3 6.500000-2 0.000000+07443 2151 279 2.190000+2 5.000000-1 5.820000-1 5.200000-1 6.200000-2 0.000000+07443 2151 280 2.865000+2 5.000000-1 9.400000-2 2.900000-2 6.500000-2 0.000000+07443 2151 281 4.055000+2 5.000000-1 1.380000-1 8.200000-2 5.600000-2 0.000000+07443 2151 282 5.095000+2 5.000000-1 1.220000-1 7.799990-2 4.400000-2 0.000000+07443 2151 283 5.405000+2 5.000000-1 5.600000-1 4.950000-1 6.500000-2 0.000000+07443 2151 284 6.625000+2 5.000000-1 7.650000-1 6.800000-1 8.500000-2 0.000000+07443 2151 285 7.140000+2 5.000000-1 9.000000-2 2.500000-2 6.500000-2 0.000000+07443 2151 286 7.235000+2 5.000000-1 2.172000+0 2.080000+0 9.199990-2 0.000000+07443 2151 287 7.690000+2 5.000000-1 7.100000-2 6.000000-3 6.500000-2 0.000000+07443 2151 288 8.300000+2 5.000000-1 9.100000-2 2.600000-2 6.500000-2 0.000000+07443 2151 289 9.625000+2 5.000000-1 1.132000+0 1.060000+0 7.200000-2 0.000000+07443 2151 290 1.070000+3 5.000000-1 6.310000-1 5.700000-1 6.100000-2 0.000000+07443 2151 291 1.120000+3 5.000000-1 4.820000-1 4.200000-1 6.200000-2 0.000000+07443 2151 292 1.185500+3 5.000000-1 8.800000-1 8.250000-1 5.500000-2 0.000000+07443 2151 293 1.417000+3 5.000000-1 2.600000-1 1.700000-1 9.000000-2 0.000000+07443 2151 294 1.470000+3 5.000000-1 7.350000-2 8.500000-3 6.500000-2 0.000000+07443 2151 295 1.498000+3 5.000000-1 1.298000+0 1.230000+0 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1.500000+0 0.000000+0 5 0 42 67443 2151 337 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07443 2151 338 3.200000+3 5.193550+1 0.000000+0 1.308770-3 5.301000-2 0.000000+07443 2151 339 5.000000+3 5.177810+1 0.000000+0 1.304810-3 5.301000-2 0.000000+07443 2151 340 1.000000+4 5.134190+1 0.000000+0 1.293820-3 5.301000-2 0.000000+07443 2151 341 2.000000+4 5.048190+1 0.000000+0 1.272140-3 5.301000-2 0.000000+07443 2151 342 5.000000+4 4.799120+1 0.000000+0 1.209380-3 5.301000-2 0.000000+07443 2151 343 1.000000+5 4.412150+1 0.000000+0 1.111860-3 5.301000-2 0.000000+07443 2151 344 1.843570+2 0.000000+0 2 0 2 07443 2151 345 1.500000+0 0.000000+0 5 0 42 67443 2151 346 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07443 2151 347 3.200000+3 5.193550+1 0.000000+0 7.530640-3 5.301000-2 0.000000+07443 2151 348 5.000000+3 5.177810+1 0.000000+0 7.507820-3 5.301000-2 0.000000+07443 2151 349 1.000000+4 5.134190+1 0.000000+0 7.444570-3 5.301000-2 0.000000+07443 2151 350 2.000000+4 5.048190+1 0.000000+0 7.319870-3 5.301000-2 0.000000+07443 2151 351 5.000000+4 4.799120+1 0.000000+0 6.958720-3 5.301000-2 0.000000+07443 2151 352 1.000000+5 4.412150+1 0.000000+0 6.397620-3 5.301000-2 0.000000+07443 2151 353 2.500000+0 0.000000+0 5 0 42 67443 2151 354 0.000000+0 0.000000+0 0.000000+0 1.000000+0 0.000000+0 0.000000+07443 2151 355 3.200000+3 3.779710+1 0.000000+0 5.480580-3 5.301000-2 0.000000+07443 2151 356 5.000000+3 3.768190+1 0.000000+0 5.463880-3 5.301000-2 0.000000+07443 2151 357 1.000000+4 3.736270+1 0.000000+0 5.417590-3 5.301000-2 0.000000+07443 2151 358 2.000000+4 3.673340+1 0.000000+0 5.326350-3 5.301000-2 0.000000+07443 2151 359 5.000000+4 3.491130+1 0.000000+0 5.062140-3 5.301000-2 0.000000+07443 2151 360 1.000000+5 3.208160+1 0.000000+0 4.651830-3 5.301000-2 0.000000+07443 2151 361 7443 2 0 362 7443 0 0 363 7.418600+4 1.843600+2 0 0 0 07443 3 16 364 -7.199500+6-7.199500+6 0 0 1 287443 3 16 365 28 2 0 0 0 07443 3 16 366 7.238600+6 0.000000+0 7.500000+6 7.027000-2 8.000000+6 5.136000-17443 3 16 367 8.500000+6 9.314000-1 9.000000+6 1.214000+0 9.500000+6 1.411000+07443 3 16 368 1.000000+7 1.556000+0 1.050000+7 1.655000+0 1.100000+7 1.735000+07443 3 16 369 1.150000+7 1.799000+0 1.200000+7 1.854000+0 1.250000+7 1.900300+07443 3 16 370 1.300000+7 1.940000+0 1.302000+7 1.941500+0 1.350000+7 1.965400+07443 3 16 371 1.400000+7 1.962000+0 1.450000+7 1.883000+0 1.500000+7 1.738000+07443 3 16 372 1.550000+7 1.552600+0 1.600000+7 1.367000+0 1.650000+7 1.203500+07443 3 16 373 1.700000+7 1.053500+0 1.750000+7 9.166700-1 1.800000+7 7.930000-17443 3 16 374 1.850000+7 6.886400-1 1.900000+7 6.076100-1 1.950000+7 5.465300-17443 3 16 375 2.000000+7 5.020000-1 0.000000+0 0.000000+0 0.000000+0 0.000000+07443 3 16 376 7443 3 0 377 7.418600+4 1.843600+2 0 0 0 07443 3102 378 5.466100+6 5.466100+6 0 0 2 857443 3102 379 6 5 85 2 0 07443 3102 380 1.000000-5 2.860000-6 2.530000-2 1.440000-4 5.000000+2 2.020000-27443 3102 381 1.000000+3 2.840000-2 2.000000+3 3.950000-2 3.200000+3 4.880000-27443 3102 382 3.200000+3 0.000000+0 1.000000+4 0.000000+0 1.000000+5 0.000000+07443 3102 383 1.000000+5 1.663000-1 1.100000+5 1.530600-1 1.200000+5 1.398800-17443 3102 384 1.400000+5 1.165800-1 1.600000+5 9.848200-2 1.800000+5 8.503500-27443 3102 385 2.000000+5 7.523500-2 2.200000+5 6.819500-2 2.400000+5 6.324600-27443 3102 386 2.600000+5 5.978000-2 2.800000+5 5.711700-2 3.000000+5 5.570000-27443 3102 387 3.200000+5 5.507300-2 3.400000+5 5.451800-2 3.600000+5 5.402600-27443 3102 388 3.800000+5 5.358900-2 4.000000+5 5.320000-2 4.200000+5 5.284300-27443 3102 389 4.400000+5 5.251000-2 4.600000+5 5.220600-2 4.800000+5 5.193600-27443 3102 390 5.000000+5 5.170000-2 5.200000+5 5.158400-2 5.400000+5 5.162100-27443 3102 391 5.600000+5 5.175100-2 5.800000+5 5.192500-2 6.000000+5 5.210000-27443 3102 392 6.200000+5 5.245100-2 6.400000+5 5.301800-2 6.600000+5 5.359500-27443 3102 393 6.800000+5 5.400700-2 7.000000+5 5.410000-2 7.200000+5 5.391000-27443 3102 394 7.400000+5 5.359600-2 7.600000+5 5.321100-2 7.800000+5 5.280000-27443 3102 395 8.000000+5 5.240000-2 8.500000+5 5.158000-2 9.000000+5 5.030000-27443 3102 396 9.500000+5 4.824700-2 1.000000+6 4.610000-2 1.100000+6 4.238300-27443 3102 397 1.200000+6 3.916600-2 1.300000+6 3.618600-2 1.400000+6 3.358000-27443 3102 398 1.500000+6 3.160000-2 1.600000+6 3.068700-2 1.700000+6 3.095500-27443 3102 399 1.800000+6 3.132900-2 1.900000+6 3.134800-2 2.000000+6 3.095000-27443 3102 400 2.200000+6 2.781000-2 2.400000+6 2.398300-2 2.600000+6 2.002100-27443 3102 401 2.800000+6 1.647600-2 3.000000+6 1.390000-2 3.500000+6 9.432700-37443 3102 402 4.000000+6 6.230000-3 4.500000+6 4.061800-3 5.000000+6 2.480000-37443 3102 403 5.500000+6 1.485300-3 6.000000+6 8.800000-4 7.000000+6 3.811300-47443 3102 404 8.000000+6 2.800000-4 9.000000+6 4.635400-4 1.000000+7 8.470000-47443 3102 405 1.100000+7 1.150600-3 1.200000+7 1.370000-3 1.300000+7 1.299300-37443 3102 406 1.400000+7 1.010000-3 1.500000+7 7.071800-4 1.600000+7 4.300000-47443 3102 407 1.700000+7 2.337000-4 1.800000+7 1.320000-4 1.900000+7 7.942200-57443 3102 408 2.000000+7 4.970000-5 0.000000+0 0.000000+0 0.000000+0 0.000000+07443 3102 409 7443 3 0 410 7.418600+4 1.843600+2 0 0 0 07443 3107 411 6.417500+6 6.417500+6 0 0 1 257443 3107 412 25 2 0 0 0 07443 3107 413 1.000000-5 0.000000+0 2.530000-2 0.000000+0 3.200000+3 0.000000+07443 3107 414 3.200000+3 0.000000+0 1.000000+5 0.000000+0 1.000000+5 0.000000+07443 3107 415 1.100000+7 0.000000+0 1.150000+7 1.135500-5 1.200000+7 3.136700-57443 3107 416 1.250000+7 6.870300-5 1.300000+7 1.320200-4 1.350000+7 2.289000-47443 3107 417 1.400000+7 3.630000-4 1.450000+7 5.437400-4 1.500000+7 8.085000-47443 3107 418 1.550000+7 1.188000-3 1.600000+7 1.633500-3 1.650000+7 2.013000-37443 3107 419 1.700000+7 2.310000-3 1.750000+7 2.586400-3 1.800000+7 2.867900-37443 3107 420 1.850000+7 3.167500-3 1.900000+7 3.498000-3 1.950000+7 3.866600-37443 3107 421 2.000000+7 4.257000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+07443 3107 422 7443 3 0 423 7443 0 0 424 0 0 0 425 7.919700+4 1.952740+2 1 0 0 17925 1451 1 0.000000+0 0.000000+0 0 0 0 67925 1451 2 1.000000+0 0.000000+0 0 0 10 67925 1451 3 0.000000+0 0.000000+0 0 0 222 57925 1451 4 79-AU-197 LANL EVAL-JAN84 P.G.YOUNG 7925 1451 5 DIST-FEB90 900205 7925 1451 6 ----ENDF/B-VI MATERIAL 7925 7925 1451 7 -----INCIDENT NEUTRON DATA 7925 1451 8 ------ENDF-6 FORMAT 7925 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************7925 1451 10 ACTIVATION II 7925 1451 11 ******************************************************************7925 1451 12 7925 1451 13 *************** summary ******************************************7925 1451 14 7925 1451 15 A new evaluation of all neutron and gamma-ray data above the 7925 1451 16 resonance region is joined with the endf/b-v resolved resonance 7925 1451 17 region evaluation and with the Version VI standard cross section 7925 1451 18 for the (n,gamma) reaction below a neutron energy of 2.5 MeV. 7925 1451 19 7925 1451 20 *************** general description ******************************7925 1451 21 7925 1451 22 P.G.Young and E.D.Arthur 7925 1451 23 7925 1451 24 the new evaluation for files 3,4,5,12,13,14,15 is based on 7925 1451 25 statistical theory, hauser-feshbach, preequilibrium calculations 7925 1451 26 with the comnuc and gnash codes (ref1,2). deformed optical poten-7925 1451 27 tial of delaroche and ecis coupled-channel code were used to cal-7925 1451 28 culate neutron transmission coefficients and total and elastic 7925 1451 29 elastic cross sections (ref3,4). gamma-ray strength functions 7925 1451 30 were obtained by fitting morgan n,xg data (ref5) at 0.4 and 6.5 7925 1451 31 mev. calculated results were used for all major reactions except 7925 1451 32 total cross section. for total, the theoretical cross section 7925 1451 33 was used as prior in covariance analysis of experimental data 7925 1451 34 using glucs code (ref6). more details on experimental data used 7925 1451 35 are given below and in main reference for evaluation (ref 7). 7925 1451 36 7925 1451 37 *************** mf=2 resonance parameters ************************7925 1451 38 7925 1451 39 mt=151 resolved resonance parameters given from 1.0e-05ev 7925 1451 40 to 2 kev based on ref8 and references therein 7925 1451 41 and a bound level. some of the reson. spin assignments 7925 1451 42 from ref9. from 2 to 4.827 kev the parameters are based7925 1451 43 on macklin et al and hoffman et al normalized data. 7925 1451 44 see refs 10 and 11. 7925 1451 45 thermal cross sections are as follows: 7925 1451 46 capture = 98.71 b 7925 1451 47 scattering = 6.84 b 7925 1451 48 total = 105.55 b 7925 1451 49 the absorption resonance integral is 1559 b 7925 1451 50 7925 1451 51 *************** mf=3 smooth neutron cross sections ***************7925 1451 52 7925 1451 53 mt= 1 total cross section. based on glucs covariance analysis 7925 1451 54 using deformed optical model calculation as the prior and 7925 1451 55 experimental data from refs 12-22, 29 for fitting. 7925 1451 56 mt= 2 elastic cross section. difference of mt=1 and sum of 7925 1451 57 all nonelastic cross sections. closely approximates theore- 7925 1451 58 tical results. 7925 1451 59 mt= 4 inelastic cross section. sum of mt=51-63, 91. 7925 1451 60 mt= 16 (n,2n) cross section. theoretical calculation used. 7925 1451 61 in good agreement with exp. below 23 mev. see refs 23-25. 7925 1451 62 mt= 17 (n,3n) cross section. theoretical calculation used. 7925 1451 63 in good agreement with exp. at all energies (refs 24,25). 7925 1451 64 mt= 37 (n,4n) cross section. theoretical calculation used. 7925 1451 65 in reasonable agreement with data of ref 25. 7925 1451 66 mt=51-63 (n,nprime) cross sections to levels. except for mt=53 7925 1451 67 and 56, all are from compound-nucleus calculations with the 7925 1451 68 comnuc code. mt=53 and 56 also include direct reaction com- 7925 1451 69 ponents from ecis calculations (mt53 and 56 are the 5/2+ 7925 1451 70 and 7/2+ members of the ground state rotational band) and 7925 1451 71 extend to 30 mev. mt=51,52,54,55,57-63 are zeroed above 6 mev.7925 1451 72 mt= 91 inelastic continuum cross section. from gnash theoreti- 7925 1451 73 cal calculations. includes (n,gn) component from 0.1 to 7925 1451 74 2.0 mev. conventional (n,ng) continuum starts at 1.2236 7925 1451 75 mev. q-value has no significance except corresponds to thres.7925 1451 76 mt=102 (n,gamma) cross section. below 2.5 MeV, adopted the 7925 1451 77 ENDF/B-VI standard cross section (Ref.30,31) down to the 7925 1451 78 resonance region. At higher energies, the theoretical cal- 7925 1451 79 culations were adjusted to agree with experimental data. A 7925 1451 80 semi-direct component normalized to an average of experimental7925 1451 81 data at 14 MeV was included above En = 6 MeV. 7925 1451 82 at higher energies, use theoretical calculations, which agree 7925 1451 83 reasonably with available exp. data. above 5 mev, calculation7925 1451 84 includes semi-direct component normalized to average of 7925 1451 85 14 mev data. 7925 1451 86 mt=103 (n,p) cross section. adopted endf/b-v with smooth 7925 1451 87 extrapolation to 30 mev. based on exp data of ref 26. 7925 1451 88 mt=107 (n,alpha) cross section. adopted endf/b-v with smooth 7925 1451 89 extrapolation to 30 mev. based on data of ref 26. 7925 1451 90 7925 1451 91 *************** mf=4 neutron angular distributions ***************7925 1451 92 7925 1451 93 mt= 2 elastic scattering. legendre coefficients obtained by 7925 1451 94 combining ecis direct reaction calculations with comnuc com- 7925 1451 95 pound nucleus results. 7925 1451 96 mt= 16 (n,2n) angular distribution. used kalbach-mann (ref 27) 7925 1451 97 semi-empirical shape averaged over the emitted neutron 7925 1451 98 spectrum at each incident neutron energy. 7925 1451 99 mt= 17 (n,3n) angular distribution. same comment as mt=16. 7925 1451 100 mt= 37 (n,4n) angular distribution. same comment as mt=16. 7925 1451 101 mt=51-63 (n,nprime) level angular distributions. legendre coef 7925 1451 102 -ficients obtained from comnuc compound nucleus calculations. 7925 1451 103 for mt=53 and 56, ecis direct reaction results were combined 7925 1451 104 with the compound nucleus calculations, 7925 1451 105 mt= 91 (n,nprime) continuum. same comment as for mt=16. 7925 1451 106 7925 1451 107 *************** mf=5 neutron energy distributions ****************7925 1451 108 7925 1451 109 mt= 16 (n,2n) tabulated distribution from gnash calculations. 7925 1451 110 mt= 17 (n,3n) tabulated distribution from gnash calculations. 7925 1451 111 mt= 37 (n,4n) tabulated distribution from gnash calculations. 7925 1451 112 mt= 91 (n,nprime) continuum tabulated distribution obtained from7925 1451 113 gnash calculation. 7925 1451 114 7925 1451 115 *************** mf=8 radioactive decay data **********************7925 1451 116 7925 1451 117 mt= 16 decay data for the 10 hour metastable sixth excited state7925 1451 118 in au-196. endf/b-v data adopted without change. 7925 1451 119 7925 1451 120 *************** mf=10 radioactive nuclide cross sections *********7925 1451 121 7925 1451 122 mt= 16 production cross section for the 10-hour metastable sixth7925 1451 123 excited state of au-196 through (n,2n) reactions. endf/b-v 7925 1451 124 data adopted, with smooth extrapolation to 30 mev. 7925 1451 125 7925 1451 126 *************** mf=12 photon multiplicities **********************7925 1451 127 7925 1451 128 mt=102 (n,gamma) yield at low energies obtained by requiring 7925 1451 129 energy conservation with mf=15,mt=102 results. beginning 7925 1451 130 near 10 kev, gnash results used. 7925 1451 131 7925 1451 132 *************** mf=13 photon cross sections **********************7925 1451 133 7925 1451 134 mt= 4 gamma-ray production cross sections obtained from gnash 7925 1451 135 calculations for continua regions and from comnuc for 7925 1451 136 discrete levels. ecis was used to calculate direct react- 7925 1451 137 tion contributions for 3rd and 6th levels of au-197. 7925 1451 138 mt= 16 gamma-ray production cross sections obtained from gnash 7925 1451 139 calculations at all incident neutron energies. 7925 1451 140 mt= 17 gamma-ray production cross sections obtained from gnash 7925 1451 141 calculations at all incident neutron energies. 7925 1451 142 mt= 37 gamma-ray production cross sections obtained from gnash 7925 1451 143 calculations at all incident neutron energies. 7925 1451 144 7925 1451 145 *************** mf=14 photon angular distributions ***************7925 1451 146 7925 1451 147 mt= 4 photons from inelastic scattering assumed isotropic. 7925 1451 148 mt= 16 photons from (n,2n) reactions assumed isotropic. 7925 1451 149 mt= 17 photons from (n,3n) reactions assumed isotropic. 7925 1451 150 mt= 37 photons from (n,4n) reactions assumed isotropic. 7925 1451 151 mt=102 photons from (n,gamma) reactions assumed isotropic. 7925 1451 152 7925 1451 153 *************** mf=15 photon energy distributions ****************7925 1451 154 7925 1451 155 mt= 4 inelastic scattering photon tabulated distributions 7925 1451 156 obtained from gnash calculations for continua regions and 7925 1451 157 from comnuc for discrete levels. direct contributions for 7925 1451 158 mt=53 and mt=56 obtained from ecis calculations. 7925 1451 159 mt= 16 (n,2n) photon tabulated distributions obtained from 7925 1451 160 gnash calculations. 7925 1451 161 mt= 17 (n,3n) photon tabulated distributions obtained from 7925 1451 162 gnash calculations. 7925 1451 163 mt= 37 (n,4n) photon tabulated distributions obtained from 7925 1451 164 gnash calculations. 7925 1451 165 mt=102 (n,gamma) tabulated thermal distribution obtained from 7925 1451 166 experimental data of ref 28. thermal spectrum linearly inter-7925 1451 167 polated to gnash calculation at 10 kev. gnash results used 7925 1451 168 at higher energies. 7925 1451 169 7925 1451 170 *************** mf=33 neutron cross section covariances **********7925 1451 171 7925 1451 172 mt= 1 total cross section covariance from glucs analysis. 7925 1451 173 7925 1451 174 *************** references ***************************************7925 1451 175 7925 1451 176 1. c.l.dunford. ai-aec-12931(1970) 7925 1451 177 2. p.g.young, e.d.arthur, la-6947 (1977). 7925 1451 178 3. j.p.delaroche, harwell conference (1978)p.366. 7925 1451 179 4. j.raynal, iaea smr-9/8 (1970). 7925 1451 180 5. g.l.morgan, e.newman, ornl-tm-4973 (1975). 7925 1451 181 6. d.m.hetrick, c.y.fu, ornl/tm-7341 (1980). 7925 1451 182 7. p.g.young, e.d.arthur, in la- -pr (1984)p.12. 7925 1451 183 8. s.f.mughabghab and d.i.garber bnl-325,3rd edn,vol i(1973). 7925 1451 184 9. a.lottin and a.jain conf on nuclear structure study with 7925 1451 185 neutrons,budapest,1972 p34 and private communication. 7925 1451 186 10. r.macklin et al. phys. rev/c 11,1270(1975) and private 7925 1451 187 communication. 7925 1451 188 11. m.m. hoffman et al. 75washington conf., 2, 868(1971) knox. 7925 1451 189 12. w.poenitz et al., nuc.sci.eng. 78, 333(1981). 7925 1451 190 13. d.g.foster jr., d.glasgow, phys.rev. c3, 576(1971). 7925 1451 191 14. k.k.seth,phys.letters,16,306(1965). 7925 1451 192 15. s.c.snowdon, phys.rev. 90, 615(1953). 7925 1451 193 16. j.f.whalen,anl-7210,16(1966). 7925 1451 194 17. n.nereson, phys.rev. 94, 1678(1954). 7925 1451 195 18. a.bratenahl et al., phys.rev. 110, 927(1958). 7925 1451 196 19. j.p.conner,phys.rev.109,1268(1958). 7925 1451 197 20. j.h.coon,phys.rev.88,562(1952). 7925 1451 198 21. j.m.peterson,phys.rev.120,521(1960). 7925 1451 199 22. e.g.bilpuch,private communication(1959). 7925 1451 200 23. j.frehaut et al, proc. 10-50 mev conf, bnl-ncs-51245 (1980) 7925 1451 201 page 399. 7925 1451 202 24. l.r.veeser et al, phys.rev. c16, 1792(1977). 7925 1451 203 25. b.p.bayhurst et al, phys.rev. c12, 451(1975). 7925 1451 204 26. r.j.prestwood and b.p.bayhurst,phys.rev.121,1438(1961). 7925 1451 205 27. c.kalbach and f.mann, bnl-ncs-5/245,p.689 (1980). 7925 1451 206 28. v.j.orphan et al, ga-10248 (1970). 7925 1451 207 29. d.c.larson, proc. 10-50 mev conf, bnl-ncs-51245 (1980) p.277.7925 1451 208 30. A.Carlson et al., Nuc.Data for Basic & Applied Science, 7925 1451 209 Santa Fe, NM (1985) p.1429. 7925 1451 210 31. W.Poenitz, ANL-West, personnal communication (1989). 7925 1451 211 7925 1451 212 ******************************************************************7925 1451 213 ***************** PROGRAM FIXUP (VERSION 86-2) ******************7925 1451 214 *RECONSTRUCTED MT NUMBERS 7925 1451 215 4 =+( 51, 91) 7925 1451 216 103 =+(700,718) 7925 1451 217 104 =+(720,738) 7925 1451 218 105 =+(740,758) 7925 1451 219 106 =+(760,778) 7925 1451 220 107 =+(780,798) 7925 1451 221 101 =+(102,114) 7925 1451 222 27 =+( 18, 18)+(101,101) 7925 1451 223 3 =+( 4, 4)+( 6, 9)+( 16, 17)+( 22, 37) 7925 1451 224 19 =+( 18, 18)-( 20, 21)-( 38, 38) 7925 1451 225 1 =+( 2, 3) 7925 1451 226 1 451 231 17925 1451 227 2 151 268 07925 1451 228 3 16 25 17925 1451 229 3 17 16 17925 1451 230 3 102 44 17925 1451 231 7925 1 0 232 7925 0 0 233 7.919700+4 1.952740+2 0 0 1 07925 2151 234 7.919700+4 1.000000+0 0 0 1 07925 2151 235 1.000000-5 5.000000+3 1 2 0 07925 2151 236 1.500000+0 9.800000-1 0 0 1 07925 2151 237 1.952740+2 0.000000+0 0 0 1578 2637925 2151 238 -3.380000+1 2.000000+0 2.562000-1 1.562000-1 1.000000-1 0.000000+07925 2151 239 4.906000+0 2.000000+0 1.377000-1 1.520000-2 1.225000-1 0.000000+07925 2151 240 4.645000+1 1.000000+0 1.241300-1 1.300000-4 1.240000-1 0.000000+07925 2151 241 5.810000+1 1.000000+0 1.164000-1 4.400000-3 1.120000-1 0.000000+07925 2151 242 6.030000+1 2.000000+0 1.980000-1 6.800000-2 1.300000-1 0.000000+07925 2151 243 7.840000+1 1.000000+0 1.467000-1 1.670000-2 1.300000-1 0.000000+07925 2151 244 1.070000+2 2.000000+0 1.278000-1 7.800000-3 1.200000-1 0.000000+07925 2151 245 1.223000+2 2.000000+0 1.248000-1 8.000000-4 1.240000-1 0.000000+07925 2151 246 1.442000+2 1.000000+0 1.289000-1 8.900000-3 1.200000-1 0.000000+07925 2151 247 1.513000+2 2.000000+0 1.420000-1 2.200000-2 1.200000-1 0.000000+07925 2151 248 1.629000+2 1.000000+0 1.800000-1 5.000000-2 1.300000-1 0.000000+07925 2151 249 1.649000+2 2.000000+0 1.153000-1 9.300000-3 1.060000-1 0.000000+07925 2151 250 1.903000+2 1.000000+0 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2.500000+6 3.340000-2 2.750000+6 2.904190-27925 3102 574 3.000000+6 2.480330-2 3.250000+6 2.068920-2 3.500000+6 1.711460-27925 3102 575 3.750000+6 1.433960-2 4.000000+6 1.205200-2 4.250000+6 1.091040-27925 3102 576 4.500000+6 9.576000-3 4.750000+6 8.393720-3 5.000000+6 7.314300-37925 3102 577 5.500000+6 6.202050-3 6.000000+6 4.719000-3 6.500000+6 3.574800-37925 3102 578 7.000000+6 2.415000-3 7.500000+6 9.986730-4 8.000000+6 8.180000-47925 3102 579 8.500000+6 9.384900-4 9.000000+6 1.080000-3 9.500000+6 1.240300-37925 3102 580 1.000000+7 1.400000-3 1.050000+7 1.549700-3 1.100000+7 1.690000-37925 3102 581 1.150000+7 1.787400-3 1.200000+7 1.830000-3 1.250000+7 1.829400-37925 3102 582 1.300000+7 1.720000-3 1.350000+7 1.521100-3 1.400000+7 1.320000-37925 3102 583 1.450000+7 1.124200-3 1.500000+7 9.289400-4 1.550000+7 7.382300-47925 3102 584 1.600000+7 5.560000-4 1.650000+7 4.099100-4 1.700000+7 3.145000-47925 3102 585 1.750000+7 2.540900-4 1.800000+7 2.130000-4 1.900000+7 1.439300-47925 3102 586 2.000000+7 9.830000-5 2.100000+7 7.171000-5 2.200000+7 5.210000-57925 3102 587 2.300000+7 3.975500-5 2.400000+7 3.070000-5 2.500000+7 2.494600-57925 3102 588 2.600000+7 1.986900-5 2.700000+7 1.600000-5 2.800000+7 1.307500-57925 3102 589 2.900000+7 1.069900-5 3.000000+7 9.200000-6 0.000000+0 0.000000+07925 3102 590 7925 3 0 591 7925 0 0 592 0 0 0 593 8.220600+4 2.042000+2 -1 0 0 18231 1451 1 0.000000+0 0.000000+0 0 0 0 68231 1451 2 1.000000+0 0.000000+0 0 0 10 68231 1451 3 0.000000+0 0.000000+0 0 0 136 58231 1451 4 82-PB-206 ORNL EVAL-MAR89 C.Y.FU,N.M.LARSON,D.C.LARSON 8231 1451 5 ADNDT,16(1975)409. DIST-JUN90 900102 8231 1451 6 ----ENDF/B-VI MATERIAL 8231 8231 1451 7 -----INCIDENT NEUTRON DATA 8231 1451 8 ------ENDF-6 FORMAT 8231 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************8231 1451 10 ACTIVATION II 8231 1451 11 ******************************************************************8231 1451 12 8231 1451 13 FU75 DECRIBES ENDF/B-3. MINOR REVISIONS WERE MADE FOR 8231 1451 14 ENDF/B-4 AND -5, SEE FU82. THE PRESENT EVALUATION 8231 1451 15 WAS BASED ON AN IMPROVED MODEL CODE ANALYSIS UTILIZING MOST OF 8231 1451 16 THE OLD PARAMETERS DETERMINED PREVIOUSLY IN FU75. MORE 8231 1451 17 SPECIFICALLY: 8231 1451 18 8231 1451 19 1. ISOTOPIC EVALUATION IS NOW GIVEN FOR PB-206, -207, AND -208. 8231 1451 20 2. RESONANCE PARAMETERS WERE INTRODUCED (LA89,HO81). 8231 1451 21 3. ENERGY-ANGLE CORRELATED SPECTRA OF SECONDARY NEUTRONS ARE 8231 1451 22 GIVEN FOR THE FIRST TIME, BASED ON THE NEWEST VERSION OF THE 8231 1451 23 TNG CODE AND CONSIDERED DATA FOR BOTH PB AND BI-209 (FU88). 8231 1451 24 4. GAMMA-RAY PRODUCTION SPECTRA ARE NOW GIVEN FOR EACH REACTION 8231 1451 25 AND EACH ISOTOPE. THE NATURAL LEAD DATA (CH75) WAS CHECKED. 8231 1451 26 5. RECOIL SPECTRA ARE GIVEN TO ENABLE PRECISE ENERGY BALANCE 8231 1451 27 CHECKS. 8231 1451 28 6. GAMMA-RAY TRANSITION PROBABILITIES ARE GIVEN FOR THE 8231 1451 29 DISCRETE INELASTIC LEVELS FOR PERFECT ENERGY BALANCE. 8231 1451 30 7. GAMMA-RAY SPECTRA FROM CAPTURE ARE BASED ON CALCULATIONS 8231 1451 31 USING EXPERIMENTAL PRIMARY TRANSITION PROBABILITIES AND 8231 1451 32 BRANCHING RATIOS. THIS REMOVES ENERGY-BALANCE PROBLEMS IN 8231 1451 33 THE NATURAL EVALUATION AS THE Q VALUES FOR THE VARIOUS 8231 1451 34 ISOTOPES DIFFER SIGNIFICANTLY. 8231 1451 35 8. THE PRECOMPOUND-STRENGTH, COLLECTIVE-STRENGTH, AND LEVEL- 8231 1451 36 DENSITY PARAMETERS WERE FINE-TUNED TO ACCOMODATE NEW DATA 8231 1451 37 FOR (N,2N) CROSS SECTIONS (FR80, IW88, TA86) AND NEUTRON 8231 1451 38 EMISSION SPECTRA (PA88,TA86). 8231 1451 39 8231 1451 40 REFERENCES 8231 1451 41 CH75 G. T. CHAPMAN AND G. L. MORGAN, ORNL-TM-4822 (1975). 8231 1451 42 FR80 J. FREHAUT, BNL-NCS-51245 (1980). 8231 1451 43 FU75 C. Y. FU AND F. G. PEREY, ATOMIC DATA AND NUCLEAR DATA 8231 1451 44 TABLES 16, 409 (1975) OR ORNL-4765 (1972). 8231 1451 45 FU82 C. Y. FU, ORNL/TM-8283 (1982). 8231 1451 46 FU88 C. Y. FU, NUCL. SCI. ENG. 100, 61 (1988). 8231 1451 47 HO81 D. J. HOREN, J. A. HARVEY, N. W. HILL, PHYS. REV. C24, 8231 1451 48 1961 (1981), AND C20, 478 (1979). 8231 1451 49 IW88 S. IWASAKI ET AL., MITO CONF., MITO, JAPAN (1988). 8231 1451 50 LA81 N. M. LARSON, THE SAMMY CODE, OAK RIDGE NAT. LAB. (1988). 8231 1451 51 MC88 VICTORIA MCLANE ET AL., NEUTRON CROSS SECTION CURVES, 8231 1451 52 ACADEMIC PRESS, 1988. 8231 1451 53 MU81 S. F. MUGHABGHAB ET AL., NEUTRON RESONANCE PARAMETERS AND 8231 1451 54 THERMAL CROSS SECTIONS, ACADEMIC PRESS, 1981. 8231 1451 55 PA88 A. PAVLIK AND H. VONACH, UNIVERSITAT WIEN (1988). 8231 1451 56 QA76 S. M. QAIM AND G. STOCKLIN, NUCL. PHYS. A257, 233 (1976). 8231 1451 57 TA83 A. TAKAHASHI ET AL.,OKTAVIAN REPORT A-83-01 (1983). 8231 1451 58 TA86 A. TAKAHASHI, JAERI-M 86-080 (1986); ALSO RAD. EFF. 92, 8231 1451 59 59 (1986). 8231 1451 60 8231 1451 61 FILE 1 GENERAL INFORMATION 8231 1451 62 SECTION 451 DISCRIPTIVE DATA AND DICTIONARY 8231 1451 63 FILE 2 RESONANCE PARAMETERS 8231 1451 64 SECTION 151 GENERAL DESIGNATION FOR RESONANCE INFORMATION 8231 1451 65 BASED ON LA89 AND HO81 (>70 KEV), AND MU81 (<70 KEV) 8231 1451 66 FILE 3 NEUTRON CROSS SECTIONS 8231 1451 67 SECTION 1 TOTAL INTERACTION 8231 1451 68 HO81 BETWEEN RESONANCE RANGE (>900 KEV) AND 2 MEV. NATURAL 8231 1451 69 LEAD DATA USED BETWEEN 2 AND 3.7 MEV. ABOVE 3.7 MEV, THE 8231 1451 70 NATURAL LEAD DATA WAS MULTIPLIED BY 0.975 TO AGREE WITH 8231 1451 71 SEVERAL OLDER MEASUREMENTS (MC88) 8231 1451 72 SECTION 2 ELASTIC SCATTERING 8231 1451 73 DERIVED BY SUBTRACTING THE NON-ELASTIC CROSS SECTION FROM THE 8231 1451 74 TOTAL CROSS SECTION 8231 1451 75 SECTION 3 NON-ELASTIC INTERACTION 8231 1451 76 SUM OF ALL PARTIAL REACTION CROSS SECTIONS 8231 1451 77 SECTION 4 TOTAL INELASTIC SCATTERING 8231 1451 78 SUM OF SECTIONS 51 TO 91 8231 1451 79 SECTION 16 (N,2N) REACTION 8231 1451 80 CALCULATION ADJUSTED TO UPPER ERRORS OF FR80 8231 1451 81 AND LOWER ERRORS OF IW88 AND TA86 8231 1451 82 SECTION 17 (N,3N) REACTION 8231 1451 83 CALCULATED, NO DATA AVAILABLE 8231 1451 84 SECTION 51 THROUGH 89 INELASTIC SCATTERING EXCITING LEVELS 8231 1451 85 CALCULATED FOR 39 EXCITED LEVELS 8231 1451 86 COMPARED FAVORABLY WITH EXPERIMENTAL DATA 8231 1451 87 SECTION 91 INELASTIC SCATTERING EXCITING CONTINUUM 8231 1451 88 CALCULATED 8231 1451 89 SECTION 102 RADIATIVE CAPTURE 8231 1451 90 MEASURED DATA (FU75) USED BETWEEN RESONANCES AND 8231 1451 91 1 MEV. PB-208 DATA (MC88) USED FOR HIGHER ENERGIES. 8231 1451 92 SECTION 103 (N,P) 8231 1451 93 CALCULATION NORMALIZED TO DATA (MC88) 8231 1451 94 SECTION 105 (N,T) 8231 1451 95 BASED ON SYSTEMATICS (QA76) 8231 1451 96 SECTION 107 (N,A) 8231 1451 97 CALCULATION NORMALIZED TO DATA (MC88) 8231 1451 98 SECTION 251 MU BAR 8231 1451 99 DERIVED FROM ELASTIC ANGULAR DISTRIBUTIONS AND KINEMATICS 8231 1451 100 SECTION 252 XI 8231 1451 101 SEE SECTION 251. 8231 1451 102 SECTION 253 GAMMA 8231 1451 103 SEE SECTION 251. 8231 1451 104 FILE 4 ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS 8231 1451 105 ALL DISTRIBUTIONS ARE GIVEN IN THE LEGENDRE POLYNOMIAL 8231 1451 106 REPRESENTATIONS. 8231 1451 107 SECTION 2 ELASTIC SCATTERING 8231 1451 108 0.00001 EV TO 5 MEV--COEFFICIENTS OBTAINED BY FITTING DATA 8231 1451 109 5 MEV TO 20 MEV--OPTICAL MODEL CALCULATION. OPTICAL MODEL 8231 1451 110 PARAMETERS BEST FIT DATA AT 7 AND 14 MEV. 8231 1451 111 REPRESENTATION IS IN CENTER OF MASS SYSTEM. 8231 1451 112 TRANSFORMATION MATRIX IS GIVEN 8231 1451 113 NATURAL LEAD DATA ARE USED 8231 1451 114 SECTION 51 THROUGH 89 INELASTIC SCATTERING EXCITING LEVELS 8231 1451 115 CALCULATED AND COMPARED FAVORABLY WITH DATA. 8231 1451 116 REPRESENTATION IS IN CENTER OF MASS SYSTEM. 8231 1451 117 FILE 6 ENERGY-ANGLE DISTRIBUTION OF SECONDARY NEUTRONS, RECOILS, 8231 1451 118 AND GAMMA RAYS 8231 1451 119 SECTION 16 (N,2N) REACTION 8231 1451 120 CALCULATED, CHECKED WITH NATURAL DATA 8231 1451 121 SECTION 17 (N,3N) REACTION 8231 1451 122 CALCULATED 8231 1451 123 SECTION 91 INELASTIC SCATTERING EXCITING THE CONTINUUM 8231 1451 124 CALCULATED, CHECKED WITH NATURAL DATA 8231 1451 125 FILE 12 MULTIPLICITIES OF GAMMA RAYS PRODUCED BY NEUTRON REACTION 8231 1451 126 SECTION 51-89 8231 1451 127 TRANSITION PROBABILITIES USED IN THE MODEL ANALYSIS GIVEN 8231 1451 128 CHECKED WITH CH76 DATA FOR NATURAL LEAD 8231 1451 129 SECTION 102 CAPTURE 8231 1451 130 CALCULATED FOR THE ISOTOPE TO CONSERVE ENERGY 8231 1451 131 FILE 14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA RAYS 8231 1451 132 SECTION 51-89 AND 102 8231 1451 133 ASSUMED ISOTROPIC 8231 1451 134 FILE 15 ENERGY DISTRIBUTION OF SECONDARY GAMMA RAYS 8231 1451 135 SECTION 102 CAPTURE 8231 1451 136 CALCULATED FOR THE ISOTOPE TO CONSERVE ENERGY 8231 1451 137 FILE 33 COVARIANCE DATA 8231 1451 138 GIVEN FOR THE LARGER CROSS SECTIONS 8231 1451 139 8231 1451 140 1 451 145 18231 1451 141 3 16 11 18231 1451 142 3 105 6 18231 1451 143 3 107 7 18231 1451 144 33 16 9 18231 1451 145 8231 1 0 146 8231 0 0 147 8.220600+4 2.042000+2 0 99 0 08231 3 16 148 -8.085700+6-8.085700+6 0 0 1 238231 3 16 149 23 2 0 0 0 08231 3 16 150 8.125300+6 0.000000+0 8.200000+6 2.327800-3 8.400000+6 3.142500-28231 3 16 151 8.600000+6 8.830200-2 8.800000+6 1.672000-1 9.000000+6 2.605100-18231 3 16 152 9.500000+6 5.498400-1 9.930000+6 8.080000-1 1.042000+7 1.111800+08231 3 16 153 1.091000+7 1.353000+0 1.140000+7 1.549000+0 1.188000+7 1.751000+08231 3 16 154 1.236000+7 1.888000+0 1.285000+7 1.962000+0 1.333000+7 2.013000+08231 3 16 155 1.400000+7 2.080800+0 1.450000+7 2.137300+0 1.500000+7 2.134500+08231 3 16 156 1.600000+7 2.152600+0 1.700000+7 2.148600+0 1.800000+7 2.069200+08231 3 16 157 1.900000+7 1.848500+0 2.000000+7 1.538800+0 0.000000+0 0.000000+08231 3 16 158 8231 3 0 159 8.220600+4 2.042000+2 0 99 0 08231 3105 160 -6.321000+6-6.321000+6 0 0 2 98231 3105 161 2 2 9 5 0 08231 3105 162 6.352000+6 0.000000+0 8.000000+6 7.009000-7 1.000000+7 1.825600-68231 3105 163 1.200000+7 4.482500-5 1.400000+7 3.586000-4 1.500000+7 7.009000-48231 3105 164 1.600000+7 1.157300-3 1.800000+7 2.477600-3 2.000000+7 6.357000-38231 3105 165 8231 3 0 166 8.220600+4 2.042000+2 0 99 0 08231 3107 167 7.122000+6 7.122000+6 0 0 2 118231 3107 168 3 2 11 5 0 08231 3107 169 1.000000-5 0.000000+0 1.000000+6 0.000000+0 6.000000+6 2.053900-68231 3107 170 8.000000+6 1.159500-5 1.000000+7 6.294300-5 1.200000+7 3.511600-48231 3107 171 1.400000+7 1.755800-3 1.500000+7 3.644100-3 1.600000+7 8.282000-38231 3107 172 1.800000+7 2.981500-2 2.000000+7 4.306600-2 0.000000+0 0.000000+08231 3107 173 8231 3 0 174 8231 0 0 175 8.220600+4 2.042000+2 0 0 0 1823133 16 176 0.000000+0 0.000000+0 0 16 0 2823133 16 177 0.000000+0 0.000000+0 0 0 8 4823133 16 178 1.000000-5 0.000000+0 8.125600+6 1.000000-2 9.000000+6 0.000000+0823133 16 179 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0823133 16 180 0.000000+0 0.000000+0 0 1 14 7823133 16 181 1.000000-5 0.000000+0 8.125600+6 2.250000-2 9.000000+6 2.250000-2823133 16 182 1.200000+7 1.000000-2 1.500000+7 2.250000-2 1.700000+7 9.000000-2823133 16 183 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0823133 16 184 823133 0 185 8231 0 0 186 0 0 0 187 8.220800+4 2.061900+2 1 0 0 18237 1451 1 0.000000+0 0.000000+0 0 0 0 68237 1451 2 1.000000+0 0.000000+0 0 0 10 68237 1451 3 0.000000+0 0.000000+0 0 0 131 48237 1451 4 82-PB-208 ORNL EVAL-MAR89 C.Y.FU, D.C.LARSON 8237 1451 5 ADNDT,16(1975)409. DIST-JUN90 900102 8237 1451 6 ----ENDF/B-VI MATERIAL 8237 8237 1451 7 -----INCIDENT NEUTRON DATA 8237 1451 8 ------ENDF-6 FORMAT 8237 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************8237 1451 10 ACTIVATION II 8237 1451 11 ******************************************************************8237 1451 12 8237 1451 13 FU75 DECRIBES ENDF/B-3. MINOR REVISIONS WERE MADE FOR 8237 1451 14 ENDF/B-4 AND -5, SEE FU82. THE PRESENT EVALUATION 8237 1451 15 WAS BASED ON AN IMPROVED MODEL CODE ANALYSIS UTILIZING MOST OF 8237 1451 16 THE OLD PARAMETERS DETERMINED PREVIOUSLY IN FU75. MORE 8237 1451 17 SPECIFICALLY: 8237 1451 18 8237 1451 19 1. ISOTOPIC EVALUATION IS NOW GIVEN FOR PB-206, - 207, AND -208.8237 1451 20 2. RESONANCE PARAMETERS WERE INTRODUCED (LA89,HO86). 8237 1451 21 3. ENERGY-ANGLE CORRELATED SPECTRA OF SECONDARY NEUTRONS ARE 8237 1451 22 GIVEN FOR THE FIRST TIME, BASED ON THE NEWEST VERSION OF THE 8237 1451 23 TNG CODE AND CONSIDERED DATA FOR BOTH PB AND BI-209 (FU88). 8237 1451 24 4. GAMMA-RAY PRODUCTION SPECTRA ARE NOW GIVEN FOR EACH REACTION 8237 1451 25 AND EACH ISOTOPE. THE NATURAL LEAD DATA (CH75) WAS CHECKED. 8237 1451 26 5. RECOIL SPECTRA ARE GIVEN TO ENABLE PRECISE ENERGY BALANCE 8237 1451 27 CHECKS. 8237 1451 28 6. GAMMA-RAY TRANSITION PROBABILITIES ARE GIVEN FOR THE 8237 1451 29 DISCRETE INELASTIC LEVELS FOR PERFECT ENERGY BALANCE. 8237 1451 30 7. GAMMA-RAY SPECTRA FROM CAPTURE ARE BASED ON CALCULATIONS 8237 1451 31 USING EXPERIMENTAL PRIMARY TRANSITION PROBABILITIES AND 8237 1451 32 BRANCHING RATIOS. THIS REMOVES ENERGY-BALANCE PROBLEMS IN 8237 1451 33 THE NATURAL EVALUATION AS THE Q VALUES FOR THE VARIOUS 8237 1451 34 ISOTOPES DIFFER SIGNIFICANTLY. 8237 1451 35 8. THE PRECOMPOUND-STRENGTH, COLLECTIVE-STRENGTH, AND LEVEL- 8237 1451 36 DENSITY PARAMETERS WERE FINE-TUNED TO ACCOMODATE NEW DATA 8237 1451 37 FOR (N,2N) CROSS SECTIONS (FR80, IW88, TA86) AND NEUTRON 8237 1451 38 EMISSION SPECTRA (PA88,TA86). 8237 1451 39 8237 1451 40 REFERENCES 8237 1451 41 CH75 G. T. CHAPMAN AND G. L. MORGAN, ORNL-TM-4822 (1975). 8237 1451 42 FR80 J. FREHAUT, BNL-NCS-51245 (1980). 8237 1451 43 FU75 C. Y. FU AND F. G. PEREY, ATOMIC DATA AND NUCLEAR DATA 8237 1451 44 TABLES 16, 409 (1975) OR ORNL-4765 (1972). 8237 1451 45 FU82 C. Y. FU, ORNL/TM-8283 (1982). 8237 1451 46 FU88 C. Y. FU, NUCL. SCI. ENG. 100, 61 (1988). 8237 1451 47 HO86 D. J. HOREN ET AL., PHYS. REV. C34, 429 (1986). 8237 1451 48 IW88 S. IWASAKI ET AL., MITO CONF., MITO, JAPAN (1988). 8237 1451 49 LA89 N. M. LARSON, THE SAMMY CODE, OAK RIDGE NAT. LAB. (1988). 8237 1451 50 MC88 VICTORIA MCLANE ET AL., NEUTRON CROSS SECTION CURVES, 8237 1451 51 ACADEMIC PRESS, 1988. 8237 1451 52 MU81 S. F. MUGHABGHAB ET AL., NEUTRON RESONANCE PARAMETERS AND 8237 1451 53 THERMAL CROSS SECTIONS, ACADEMIC PRESS, 1981. 8237 1451 54 PA88 A. PAVLIK AND H. VONACH, UNIVERSITAT WIEN (1988). 8237 1451 55 QA76 S. M. QAIM AND G. STOCKLIN, NUCL. PHYS. A257, 233 (1976). 8237 1451 56 TA83 A. TAKAHASHI ET AL.,OKTAVIAN REPORT A-83-01 (1983). 8237 1451 57 TA86 A. TAKAHASHI, JAERI-M 86-080 (1986); ALSO RAD. EFF. 92, 8237 1451 58 59 (1986). 8237 1451 59 8237 1451 60 FILE 1 GENERAL INFORMATION 8237 1451 61 SECTION 451 DISCRIPTIVE DATA AND DICTIONARY 8237 1451 62 FILE 2 RESONANCE PARAMETERS 8237 1451 63 SECTION 151 GENERAL DESIGNATION FOR RESONANCE INFORMATION 8237 1451 64 BASED ON LA89 AND HO86 (>70 KEV), AND MU81 (<70 KEV) 8237 1451 65 FILE 3 NEUTRON CROSS SECTIONS 8237 1451 66 SECTION 1 TOTAL INTERACTION 8237 1451 67 HO86 ABOVE RESONANCE RANGE (> 1 MEV) 8237 1451 68 SECTION 2 ELASTIC SCATTERING 8237 1451 69 DERIVED BY SUBTRACTING THE NON-ELASTIC CROSS SECTION FROM THE 8237 1451 70 TOTAL CROSS SECTION 8237 1451 71 SECTION 3 NON-ELASTIC INTERACTION 8237 1451 72 SUM OF ALL PARTIAL REACTION CROSS SECTIONS 8237 1451 73 SECTION 4 TOTAL INELASTIC SCATTERING 8237 1451 74 SUM OF SECTIONS 51 TO 91 8237 1451 75 SECTION 16 (N,2N) REACTION 8237 1451 76 CALCULATION ADJUSTED TO UPPER ERRORS OF FR80 8237 1451 77 AND LOWER ERRORS OF IW88 AND TA86 8237 1451 78 SECTION 17 (N,3N) REACTION 8237 1451 79 CALCULATED, NO DATA AVAILABLE 8237 1451 80 SECTION 51 THROUGH 61 INELASTIC SCATTERING EXCITING LEVELS 8237 1451 81 CALCULATED FOR 21 EXCITED LEVELS 8237 1451 82 COMPARED FAVORABLY WITH EXPERIMENTAL DATA 8237 1451 83 SECTION 91 INELASTIC SCATTERING EXCITING CONTINUUM 8237 1451 84 CALCULATED 8237 1451 85 SECTION 102 RADIATIVE CAPTURE 8237 1451 86 PB-208 DATA (MC88) USED ABOVE 1 MEV. 8237 1451 87 SECTION 103 (N,P) 8237 1451 88 CALCULATION NORMALIZED TO DATA (MC88) 8237 1451 89 SECTION 105 (N,T) 8237 1451 90 BASED ON SYSTEMATICS (QA76) 8237 1451 91 SECTION 107 (N,A) 8237 1451 92 CALCULATION NORMALIZED TO DATA (MC88) 8237 1451 93 SECTION 251 MU BAR 8237 1451 94 DERIVED FROM ELASTIC ANGULAR DISTRIBUTIONS AND KINEMATICS 8237 1451 95 SECTION 252 XI 8237 1451 96 SEE SECTION 251. 8237 1451 97 SECTION 253 GAMMA 8237 1451 98 SEE SECTION 251. 8237 1451 99 FILE 4 ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS 8237 1451 100 ALL DISTRIBUTIONS ARE GIVEN IN THE LEGENDRE POLYNOMIAL 8237 1451 101 REPRESENTATIONS. 8237 1451 102 SECTION 2 ELASTIC SCATTERING 8237 1451 103 0.00001 EV TO 5 MEV--COEFFICIENTS OBTAINED BY FITTING DATA 8237 1451 104 5 MEV TO 20 MEV--OPTICAL MODEL CALCULATION. OPTICAL MODEL 8237 1451 105 PARAMETERS BEST FIT DATA AT 7 AND 14 MEV. 8237 1451 106 REPRESENTATION IS IN CENTER OF MASS SYSTEM. 8237 1451 107 TRANSFORMATION MATRIX IS GIVEN 8237 1451 108 NATURAL LEAD DATA ARE USED 8237 1451 109 SECTION 51 THROUGH 61 INELASTIC SCATTERING EXCITING LEVELS 8237 1451 110 CALCULATED AND COMPARED FAVORABLY WITH DATA. 8237 1451 111 REPRESENTATION IS IN CENTER OF MASS SYSTEM. 8237 1451 112 FILE 6 ENERGY-ANGLE DISTRIBUTION OF SECONDARY NEUTRONS, RECOILS, 8237 1451 113 AND GAMMA RAYS 8237 1451 114 SECTION 16 (N,2N) REACTION 8237 1451 115 CALCULATED, CHECKED WITH NATURAL DATA 8237 1451 116 SECTION 17 (N,3N) REACTION 8237 1451 117 CALCULATED 8237 1451 118 SECTION 91 INELASTIC SCATTERING EXCITING THE CONTINUUM 8237 1451 119 CALCULATED, CHECKED WITH NATURAL DATA 8237 1451 120 FILE 12 MULTIPLICITIES OF GAMMA RAYS PRODUCED BY NEUTRON REACTION 8237 1451 121 SECTION 51-61 8237 1451 122 TRANSITION PROBABILITIES USED IN THE MODEL ANALYSIS GIVEN 8237 1451 123 CHECKED WITH CH76 DATA FOR NATURAL LEAD 8237 1451 124 SECTION 102 CAPTURE 8237 1451 125 CALCULATED FOR THE ISOTOPE TO CONSERVE ENERGY 8237 1451 126 FILE 14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA RAYS 8237 1451 127 SECTION 51-61 AND 102 8237 1451 128 ASSUMED ISOTROPIC 8237 1451 129 FILE 15 ENERGY DISTRIBUTION OF SECONDARY GAMMA RAYS 8237 1451 130 SECTION 102 CAPTURE 8237 1451 131 CALCULATED FOR THE ISOTOPE TO CONSERVE ENERGY 8237 1451 132 FILE 33 COVARIANCE DATA 8237 1451 133 GIVEN FOR THE LARGER CROSS SECTIONS 8237 1451 134 8237 1451 135 1 451 139 18237 1451 136 2 151 88 18237 1451 137 3 102 10 18237 1451 138 33 102 6 18237 1451 139 8237 1 0 140 8237 0 0 141 8.220800+4 2.061900+2 0 0 1 08237 2151 142 8.220800+4 1.000000+0 0 0 1 08237 2151 143 1.000000-5 1.000000+6 1 3 0 18237 2151 144 0.000000+0 9.690000-1 1 0 4 48237 2151 145 2.061900+2 0.000000+0 0 0 36 68237 2151 146 -1.910000+6 5.000000-1 2.730700+5 9.140000-2 0.000000+0 0.000000+08237 2151 147 5.060000+5 5.000000-1 5.359000+4 3.700000-1 0.000000+0 0.000000+08237 2151 148 8.882000+5 5.000000-1 5.490000+3 3.700000-1 0.000000+0 0.000000+08237 2151 149 9.977000+5 5.000000-1 3.889000+3 3.700000-1 0.000000+0 0.000000+08237 2151 150 1.010000+6 5.000000-1 1.710000+2 3.700000-1 0.000000+0 0.000000+08237 2151 151 8.000000+6 5.000000-1 4.857700+5 3.700000-1 0.000000+0 0.000000+08237 2151 152 2.061900+2 0.000000+0 1 0 174 298237 2151 153 -4.000000+6 5.000000-1 5.009300+6 2.860000-1 0.000000+0 0.000000+08237 2151 154 -4.000000+6 1.500000+0 6.681200+6 2.860000-1 0.000000+0 0.000000+08237 2151 155 7.121000+4 1.500000+0 1.010000+2 3.500000-2 0.000000+0 0.000000+08237 2151 156 7.825000+4 1.500000+0 9.580000+2 5.380000-1 0.000000+0 0.000000+08237 2151 157 8.656000+4 5.000000-1 7.540000+1 2.500000-2 0.000000+0 0.000000+08237 2151 158 1.172200+5 1.500000+0 3.170000+2 1.370000-1 0.000000+0 0.000000+08237 2151 159 1.532500+5 1.500000+0 1.050000+2 2.860000-1 0.000000+0 0.000000+08237 2151 160 1.635000+5 1.500000+0 8.200000+0 2.860000-1 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6.450000-4 2.000000+7 1.370000-4 0.000000+0 0.000000+08237 3102 241 8237 3 0 242 8237 0 0 243 8.220800+4 2.061900+2 0 0 0 1823733102 244 0.000000+0 0.000000+0 0 102 0 1823733102 245 0.000000+0 0.000000+0 0 1 16 8823733102 246 1.000000-5 2.500000-3 1.000000+3 1.000000-2 1.000000+4 1.000000-2823733102 247 1.000000+5 1.000000-2 1.000000+6 2.250000-2 5.000000+6 4.000000-2823733102 248 1.000000+7 9.000000-2 2.000000+7 0.000000+0 0.000000+0 0.000000+0823733102 249 823733 0 250 8237 0 0 251 0 0 0 252 8.320900+4 2.071850+2 1 0 0 18325 1451 1 0.000000+0 0.000000+0 0 0 0 68325 1451 2 1.000000+0 0.000000+0 0 0 10 68325 1451 3 0.000000+0 0.000000+0 0 0 9 68325 1451 4 82-BI-209 ANL EVAL-AUG89 A.SMITH,D.SMITH,P.GUENTHER, 8325 1451 5 ANL/NDM-109 DIST-FEB90 891211 8325 1451 6 ----ENDF/B-VI MATERIAL 8325 8325 1451 7 -----INCIDENT NEUTRON DATA 8325 1451 8 ------ENDF-6 FORMAT 8325 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************8325 1451 10 ACTIVATION II 8325 1451 11 ******************************************************************8325 1451 12 J.MEADOWS,R.LAWSON (ANL), R.HOWERTON (LLNL), M.SUGIMOTO (JAERI) 8325 1451 13 1 451 19 18325 1451 14 2 151 108 18325 1451 15 3 16 11 18325 1451 16 3 102 20 18325 1451 17 33 16 6 18325 1451 18 33 102 6 18325 1451 19 8325 1 0 20 8325 0 0 21 8.320900+4 2.071850+2 0 0 1 08325 2151 22 8.320900+4 1.000000+0 0 0 1 08325 2151 23 1.000000-5 1.000000+5 1 2 0 08325 2151 24 4.500000+0 9.679200-1 0 0 2 08325 2151 25 2.071800+2 0.000000+0 0 0 342 578325 2151 26 8.000000+2 5.000000+0 4.675100+0 4.636400+0 3.870000-2 0.000000+08325 2151 27 2.310000+3 4.000000+0 1.793500+1 1.788900+1 4.600000-2 0.000000+08325 2151 28 5.112000+3 5.000000+0 5.696400+0 5.636400+0 6.000000-2 0.000000+08325 2151 29 1.209800+4 4.000000+0 2.590100+2 2.588900+2 1.170000-1 0.000000+08325 2151 30 1.551000+4 4.000000+0 1.145500+2 1.144400+2 1.100000-1 0.000000+08325 2151 31 1.782000+4 5.000000+0 5.130400-1 4.636400-1 4.940000-2 0.000000+08325 2151 32 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5.000000+0 2.370200+1 2.363600+1 6.520000-2 0.000000+08325 2151 97 2.877000+4 3.000000+0 2.452700+0 2.428600+0 2.410000-2 0.000000+08325 2151 98 2.901000+4 6.000000+0 2.018500+0 2.000000+0 1.850000-2 0.000000+08325 2151 99 2.919000+4 4.000000+0 4.470800+0 4.444400+0 2.640000-2 0.000000+08325 2151 100 2.951000+4 5.000000+0 3.294200+0 3.272700+0 2.150000-2 0.000000+08325 2151 101 3.272000+4 6.000000+0 2.009600+0 2.000000+0 9.600000-3 0.000000+08325 2151 102 3.467000+4 3.000000+0 3.775700+0 3.714300+0 6.140000-2 0.000000+08325 2151 103 3.724000+4 4.000000+0 1.413500+1 1.411100+1 2.360000-2 0.000000+08325 2151 104 3.915000+4 5.000000+0 2.411000+0 2.363600+0 4.740000-2 0.000000+08325 2151 105 4.238000+4 6.000000+0 1.696400+1 1.692300+1 4.050000-2 0.000000+08325 2151 106 4.649000+4 6.000000+0 5.883200+0 5.846200+0 3.700000-2 0.000000+08325 2151 107 4.841000+4 5.000000+0 2.585100+0 2.545500+0 3.964600-2 0.000000+08325 2151 108 4.967000+4 4.000000+0 2.484100+0 2.444400+0 3.964600-2 0.000000+08325 2151 109 5.076000+4 3.000000+0 1.575400+1 1.571400+1 3.964600-2 0.000000+08325 2151 110 5.420000+4 6.000000+0 1.166400+1 1.161500+1 4.840000-2 0.000000+08325 2151 111 5.541000+4 5.000000+0 9.394900+0 9.363600+0 3.130000-2 0.000000+08325 2151 112 5.827000+4 4.000000+0 3.484100+0 3.444400+0 3.964600-2 0.000000+08325 2151 113 6.058000+4 6.000000+0 2.655000+0 2.615400+0 3.964600-2 0.000000+08325 2151 114 6.299000+4 3.000000+0 1.132500+1 1.128600+1 3.964600-2 0.000000+08325 2151 115 6.372000+4 5.000000+0 3.948700+0 3.909100+0 3.964600-2 0.000000+08325 2151 116 6.716000+4 6.000000+0 1.080900+1 1.076900+1 3.964600-2 0.000000+08325 2151 117 6.839000+4 4.000000+0 7.817400+0 7.777800+0 3.964600-2 0.000000+08325 2151 118 6.858000+4 5.000000+0 4.221500+0 4.181800+0 3.964600-2 0.000000+08325 2151 119 7.067000+4 6.000000+0 1.619300+1 1.615400+1 3.964600-2 0.000000+08325 2151 120 7.168000+4 3.000000+0 1.132500+1 1.128600+1 3.964600-2 0.000000+08325 2151 121 7.970000+4 4.000000+0 1.559500+1 1.555600+1 3.964600-2 0.000000+08325 2151 122 8.426000+4 5.000000+0 1.887400+1 1.872700+1 1.470000-1 0.000000+08325 2151 123 8.462000+4 6.000000+0 1.419300+1 1.415400+1 3.964600-2 0.000000+08325 2151 124 8.951000+4 6.000000+0 8.270400+0 8.230800+0 3.964600-2 0.000000+08325 2151 125 9.107000+4 5.000000+0 8.403300+0 8.363600+0 3.964600-2 0.000000+08325 2151 126 9.149000+4 4.000000+0 1.492900+1 1.488900+1 3.964600-2 0.000000+08325 2151 127 9.294000+4 3.000000+0 1.575400+1 1.571400+1 3.964600-2 0.000000+08325 2151 128 9.481000+4 6.000000+0 1.188600+1 1.184600+1 3.964600-2 0.000000+08325 2151 129 8325 2 0 130 8325 0 0 131 8.320900+4 2.071850+2 0 0 0 08325 3 16 132 -7.460000+6-7.460000+6 0 0 1 238325 3 16 133 23 2 0 0 0 08325 3 16 134 7.496000+6 0.000000+0 7.750000+6 5.000000-2 8.000000+6 1.400000-18325 3 16 135 8.500000+6 4.000000-1 9.000000+6 7.250000-1 9.500000+6 1.090000+08325 3 16 136 1.000000+7 1.400000+0 1.050000+7 1.600000+0 1.100000+7 1.740000+08325 3 16 137 1.150000+7 1.850000+0 1.200000+7 1.940000+0 1.300000+7 2.070000+08325 3 16 138 1.400000+7 2.140000+0 1.500000+7 2.185000+0 1.600000+7 2.200000+08325 3 16 139 1.650000+7 2.175000+0 1.700000+7 2.100000+0 1.750000+7 1.920000+08325 3 16 140 1.800000+7 1.675000+0 1.850000+7 1.450000+0 1.900000+7 1.280000+08325 3 16 141 1.950000+7 1.140000+0 2.000000+7 1.040000+0 0.000000+0 0.000000+08325 3 16 142 8325 3 0 143 8.320900+4 2.071850+2 0 0 0 08325 3102 144 4.600000+6 4.600000+6 0 0 1 498325 3102 145 49 2 0 0 0 08325 3102 146 1.000000-5 0.000000+0 9.946279+4 0.000000+0 9.946360+4 5.599000-48325 3102 147 1.000000+5 5.981800-3 1.000000+5 6.010000-3 1.200000+5 5.350000-38325 3102 148 1.400000+5 4.870000-3 1.600000+5 4.510000-3 1.800000+5 4.220000-38325 3102 149 2.000000+5 3.990000-3 2.500000+5 3.570000-3 3.000000+5 3.280000-38325 3102 150 3.500000+5 3.080000-3 4.500000+5 2.880000-3 5.000000+5 2.810000-38325 3102 151 5.500000+5 2.770000-3 7.000000+5 2.720000-3 8.000000+5 2.750000-38325 3102 152 9.000000+5 2.850000-3 1.000000+6 2.780000-3 1.200000+6 2.830000-38325 3102 153 1.400000+6 2.970000-3 1.600000+6 3.190000-3 1.800000+6 3.090000-38325 3102 154 2.000000+6 3.120000-3 2.400000+6 3.270000-3 2.600000+6 3.310000-38325 3102 155 3.000000+6 2.860000-3 3.200000+6 2.510000-3 3.400000+6 2.050000-38325 3102 156 4.000000+6 1.200000-3 4.500000+6 7.000000-4 5.000000+6 5.500000-48325 3102 157 6.000000+6 4.000000-4 7.000000+6 3.000000-4 9.000000+6 2.000000-48325 3102 158 1.000000+7 2.000000-4 1.100000+7 2.400000-4 1.200000+7 3.500000-48325 3102 159 1.300000+7 7.000000-4 1.400000+7 1.000000-3 1.450000+7 1.100000-38325 3102 160 1.500000+7 1.100000-3 1.550000+7 1.000000-3 1.600000+7 8.200000-48325 3102 161 1.700000+7 4.000000-4 1.800000+7 1.500000-4 1.900000+7 3.000000-58325 3102 162 2.000000+7 1.000000-5 0.000000+0 0.000000+0 0.000000+0 0.000000+08325 3102 163 8325 3 0 164 8325 0 0 165 8.320900+4 2.071850+2 0 0 0 1832533 16 166 0.000000+0 0.000000+0 0 16 0 1832533 16 167 0.000000+0 0.000000+0 0 1 18 9832533 16 168 1.000000-5 0.000000+0 7.496000+6 2.250000-2 9.000000+6 3.600000-3832533 16 169 1.000000+7 2.500000-3 1.200000+7 2.500000-3 1.400000+7 2.500000-3832533 16 170 1.600000+7 3.600000-3 1.800000+7 8.100000-3 2.000000+7 0.000000+0832533 16 171 832533 0 172 8.320900+4 2.071850+2 0 0 0 1832533102 173 0.000000+0 0.000000+0 0 102 0 1832533102 174 0.000000+0 0.000000+0 0 1 16 8832533102 175 1.000000-5 4.000000-2 1.000000+5 2.250000-2 5.000000+5 1.000000-2832533102 176 8.000000+5 1.440000-2 1.000000+6 2.250000-2 1.200000+6 4.000000-2832533102 177 3.000000+6 2.500000-1 2.000000+7 0.000000+0 0.000000+0 0.000000+0832533102 178 832533 0 179 8325 0 0 180 0 0 0 181 9.023200+4 2.300400+2 1 1 0 19040 1451 1 0.000000+0 1.000000+0 0 0 0 69040 1451 2 1.000000+0 0.000000+0 0 0 10 69040 1451 3 0.000000+0 0.000000+0 0 0 244 49040 1451 4 90-TH-232 BNL,ANL+ EVAL-DEC77 BHAT,SMITH,LEONARD,DESAUSSURE+ 9040 1451 5 DIST-FEB90 900205 9040 1451 6 ----ENDF/B-VI MATERIAL 9040 9040 1451 7 -----INCIDENT NEUTRON DATA 9040 1451 8 ------ENDF-6 FORMAT 9040 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9040 1451 10 ACTIVATION II 9040 1451 11 ******************************************************************9040 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 9040 1451 13 * * * * * * *9040 1451 14 9040 1451 15 PRINCIPAL EVALUATORS- J.W.MEADOWS,W.P.POENITZ,A.B.SMITH,D.L.SMITH9040 1451 16 AND J.F.WHALEN(ANL) 9040 1451 17 R.J.HOWERTON(LLL) 9040 1451 18 B.R.LEONARD ET.AL.(BNW) 9040 1451 19 G.DE SAUSSURE,R.L.MACKLIN AND R.GWIN(ORNL) 9040 1451 20 D.K. OLSEN (ORNL) 9040 1451 21 THIS EVALUATION ASSEMBLED BY M.R.BHAT(BNL) USING THE FOLLOWING 9040 1451 22 EVALUATIONS 9040 1451 23 9040 1451 24 NU-BAR(PROMPT) - R.GWIN(ORNL)(REF 4) 9040 1451 25 DELAYED NEUTRONS -M.BRADY AND T.ENGLAND (REF 5) 9040 1451 26 ENERGY RELEASE IN FISSION - R.SHER ET.AL.(STANFORD)(REF 6) 9040 1451 27 THERMAL RANGE - B.R.LEONARD JR.ET.AL.(REF 2) WITH CHANGES BY9040 1451 28 M.R.BHAT(REF 31) 9040 1451 29 RESOLVED RESONANCE REGION - D.K. OLSEN (REF 37) 9040 1451 30 9040 1451 31 UNRESOLVED RESONANCE REGION - G.DE SAUSSURE AND R.L.MACKLIN 9040 1451 32 (REF 3)WITH CHANGES BY M.R.BHAT(REF 31) 9040 1451 33 SMOOTH CROSS-SECTIONS 50KEV TO 20MEV - 9040 1451 34 TOTAL - A.B.SMITH(ANL)(REF1) 9040 1451 35 FISSION - W.P.POENITZ(ANL)(REF1) 9040 1451 36 CAPTURE - W.P.POENITZ(ANL)(REF1) 9040 1451 37 INELASTIC AND OTHER CROSS-SECTIONS - J.W.MEADOWS ET.AL.(ANL)9040 1451 38 (REF1)9040 1451 39 FISSION NEUTRON SPECTRUM - M.R.BHAT(BNL) (REF 31) 9040 1451 40 GAMMA-RAY PRODUCTION - R.J.HOWERTON(LLL) 9040 1451 41 9040 1451 42 MF = 1 9040 1451 43 9040 1451 44 MT=452(NU-BAR TOTAL) CONSISTENT WITH MT=455 AND MT=456 9040 1451 45 MT=455(DELAYED NEUTRON YIELDS) (REF 5) 9040 1451 46 MT=456(PROMPT NU-BAR) BASED ON CF-252 NU-BAR(PROMPT)=3.757 9040 1451 47 EVALUATION BY GWIN(ORNL) BASED ON A STRAIGHT LINE LEAST- 9040 1451 48 SQUARES FIT TO THE AVAILABLE DATA LISTED IN REF.4. 9040 1451 49 MT=458(ENERGY RELEASE IN FISSION)EVALUATION BY R.SHER ET.AL(STAN-9040 1451 50 FORD)(REF 6) 9040 1451 51 9040 1451 52 MF = 2 9040 1451 53 9040 1451 54 RESOLVED RESONANCE REGION - D.K. OLSEN (REF 37) RESONANCE 9040 1451 55 PARAMETERS ARE UNCERTAINTY WEIGHTED AVERAGE OF AVAILABLE 9040 1451 56 DATA AND THE TWO BOUND RESONANCES OF REF 2 WITH MF=3 FILES 9040 1451 57 FOR TRUNCATION, MISSED P-WAVES, 1/V CAPTURE, AND SMOOTH 9040 1451 58 CONNECTION TO THE END OF THE THERMAL REGION CROSS SECTIONS 9040 1451 59 AT 5 EV. AVERAGE CAPTURE WIDTH = 2.44 X 10-2 EV, S-WAVE 9040 1451 60 STRENGTH FUNCTION = 0.826 X 10-4, P-WAVE STRENGTH FUNCTION 9040 1451 61 ASSUMED = 1.6 X 10-4, 5 TO 4000 EV INFINITLY DILUTE CAPTURE 9040 1451 62 RESONANCE INTEGRAL = 81.58 B. 9040 1451 63 9040 1451 64 UNRESOLVED RESONANCE REGION - G.DE SAUSSURE AND R.L.MACKLIN(REF3)9040 1451 65 EVALUATION OF CAPTURE CROSS-SECTION USED FROM 4 TO 25KEV. 9040 1451 66 ABOVE 25KEV THIS WAS JOINED SMOOTHLY TO THE POENITZ EVALUAT-9040 1451 67 ION FROM 40KEV TO 50KEV. THESE WERE THEN FITTED USING THE 9040 1451 68 CODE UR(REF30) TO GIVE THE UNRESOLVED RESONANCE 9040 1451 69 PARAMETERS. IN THIS FIT THE S- AND D-WAVE PARAMETERS WERE 9040 1451 70 KEPT CONSTANT AT THE VALUES GIVEN BY DE SAUSSURE AND MACKLIN9040 1451 71 THE P-WAVE GAMMA WIDTH WAS INCREASED TO 2.52E-02EV AND THE 9040 1451 72 P-WAVE REDUCED NEUTRON WIDTH VARIED TO FIT THE CAPTURE 9040 1451 73 CROSS-SECTION. 9040 1451 74 THE CAPTURE CROSS-SECTION INPUT USED TO EXTRACT THE 9040 1451 75 UNRESOLVED RESONANCE PARAMETERS IN FILE 2/151 ARE GIVEN HERE9040 1451 76 FROM 4KEV TO 50KEV AT 1KEV INTERVAL. THESE ARE - 9040 1451 77 1.130,0.982,0.908,0.850,0.803,0.764,0.730,0.702,0.677,0.655,9040 1451 78 0.636,0.618,0.601,0.585,0.571,0.557,0.545,0.533,0.521,0.511,9040 1451 79 0.500,0.491,0.482,0.473,0.465,0.459,0.452,0.448,0.443,0.439,9040 1451 80 0.435,0.431,0.429,0.426,0.424,0.422,0.420,0.420,0.420,0.420,9040 1451 81 0.417,0.414,0.411,0.407,0.401,0.395,0.390. 9040 1451 82 9040 1451 83 MF = 3 9040 1451 84 9040 1451 85 THERMAL REGION(1.0E-05 TO 5.0EV) - MAINLY BASED ON LEONARD(REF 2)9040 1451 86 EVALUATION WITH THE FOLLOWING CHANGES. THE CAPTURE CROSS- 9040 1451 87 SECTION IN REF 2 NORMALISED TO 7.40B AT 2.53E-02 EV AND USED9040 1451 88 FROM 1.0E-05EV TO 2.53E-02EV. FROM 2.6E-02EV TO 14EV THE FIT9040 1451 89 TO THEIR CAPTURE DATA BY CHRIEN AND LIOU(REF 32) USED. THE 9040 1451 90 SCATTERING CROSS-SECTION WAS CHANGED TO ACCOMMODATE CHANGES 9040 1451 91 IN CAPTURE USING TOTAL SLIGHTLY MODIFIED FROM THAT GIVEN IN 9040 1451 92 REF 2. THESE SMALL CHANGES ARE DESCRIBED IN REF 31. 9040 1451 93 2.53E-02EV CROSS-SECTION CAPTURE 7.4 B 9040 1451 94 DILUTE CAPTURE RESONANCE INTEGRAL 86.1 B 9040 1451 95 (0.5 TO 2.0E+07 EV) 9040 1451 96 TOTAL CROSS-SECTION FROM 50KEV TO 20MEV - A.B.SMITH(ANL)(REF1) 9040 1451 97 MAINLY BASED ON REF9-13 FROM 0.025 TO 1 MEV,FROM 1 TO 5MEV 9040 1451 98 BASED ON REF 9-11,14-16.FROM 5 TO 15MEV EVALUATION BASED ON 9040 1451 99 REF11,15,17.FROM 15 TO 20MEV EVALUATION BASED ON NUCLEAR 9040 1451 100 MODEL CALCULATIONS DESCRIBED IN REF18 AND 19.TOTAL CROSS- 9040 1451 101 SECTION MODIFIED BY ABOUT 3PER-CENT BETWEEN 50 TO 150KEV 9040 1451 102 JOIN SMOOTHLY WITH THAT CALCULATED FROM THE UNRESOLVED 9040 1451 103 RESONANCE PARAMETERS BELOW 50KEV. 9040 1451 104 ELASTIC SCATTERING CROSS-SECTION FROM 50KEV TO 20MEV OBTAINED AS 9040 1451 105 THE DIFFERENCE BETWEEN TOTAL AND OTHER PARTIAL CROSSSECTIONS9040 1451 106 FISSION CROSS-SECTION UP TO 20MEV - W.P.POENITZ(REF1) DETAILS OF 9040 1451 107 THE EVALUATION AND THE DATA SETS USED ARE IN REF1. 9040 1451 108 FISSION CROSS-SECTION CHANGED TO BE CONSISTENT WITH 9040 1451 109 U-235(N,F) EVALUATION GIVEN IN REF 33 9040 1451 110 CAPTURE CROSS-SECTION 50KEV -20MEV - W.P.POENITZ. DETAILS OF THE 9040 1451 111 EVALUATION AND THE DATA SETS USED ARE GIVEN IN REF1. 9040 1451 112 CAPTURE CROSS-SECTION CHANGED TO BE CONSISTENT WITH 9040 1451 113 U-235(N,F) EVALUATION GIVEN IN REF 33 9040 1451 114 INELASTIC SCATTERING CROSS-SECTIONS - J.W.MEADOWS ET.AL.(REF 1) 9040 1451 115 EVALUATION BASED MAINLY ON THE DATA IN REF 20-25. INTER- 9040 1451 116 POLATED BETWEEN EXPERIMENTAL DATA AND EXTRAPOLATED TO 20MEV 9040 1451 117 USING COUPLED CHANNEL NUCLEAR MODEL CALCULATIONS OF REF26. 9040 1451 118 (N,2N) AND (N,3N) CROSS-SECTIONS - J.W.MEADOWS ET.AL.(REF1) 9040 1451 119 EXPERIMENTAL DATA USED(REF1) RENORMALISED TO A COMMON SET OF9040 1451 120 STANDARDS BEFORE EVALUATION. 9040 1451 121 9040 1451 122 MF = 4 9040 1451 123 9040 1451 124 ELASTIC ANGULAR DISTRIBUTIONS - J.W.MEADOWS ET.AL.(REF1) 9040 1451 125 EVALUATION BASED ON EXPERIMENTAL DATA TO 2.5MEV(REF1) AND 9040 1451 126 NUCLEAR MODEL CALCULATIONS FROM 2.5 TO 20MEV(REF26) 9040 1451 127 INELASTIC ANGULAR DISTRIBUTIONS - J.W.MEADOWS ET.AL.(REF1) 9040 1451 128 ANGULAR DISTRIBUTIONS BASED ON COUPLED CHANNEL NUCLEAR MODEL9040 1451 129 CALCULATED AND EXPERIMENTAL DATA FOR INCIDENT ENERGIES LESS 9040 1451 130 OR EQUAL TO 2.5MEV AND ON MODEL CALCULATIONS(REF 26) FROM 9040 1451 131 2.5 TO 20MEV. 9040 1451 132 MT=16,17,18 ASSUMED TO BE ISOTROPIC 9040 1451 133 9040 1451 134 MF = 5 9040 1451 135 9040 1451 136 MT=16,17 - J.W.MEADOWS ET.AL.(REF 1 ) 9040 1451 137 THESE DETERMINED USING THE STATISTICAL MODEL OF SEGEV(REF27)9040 1451 138 WITH A PRECOMPOUND COMPONENT 9040 1451 139 MT=18 THE VARIATION OF THE MEAN ENERGY OF THE FISSION SPECTRUM 9040 1451 140 WAS CALCULATED USING THE METHOD OF HOWERTON AND DOYAS(REF28)9040 1451 141 AND NORMALISED TO THE 14.3MEV DATA OF VASIL'EV ET.AL(REF29) 9040 1451 142 TO GIVE A MEAN ENERGY OF 2.255MEV AT 14MEV AND THE 9040 1451 143 CORRESPONDING WATT SPECTRUM SHAPE PARAMETERS OBTAINED. 9040 1451 144 MT=91 - J.W.MEADOWS ET.AL.(REF1) 9040 1451 145 EVALUATION BASED ON THE MEASURED EVAPORATION TEMPERATURES OF9040 1451 146 REF23 AND 25. IN ADDITION, A HARDER PRECOMPOUND COMPONENT 9040 1451 147 VARYING FROM 0.0 AT 6MEV TO 20PER-CENT AT 20MEV PATTERNED 9040 1451 148 AFTER U-238 WAS ADDED 9040 1451 149 MT=455 (REF 5) 9040 1451 150 9040 1451 151 MF = 12 9040 1451 152 MT = 18 9040 1451 153 FOR ALL INCIDENT ENERGIES THE MULTIPLICITY OF PHOTONS FROM 9040 1451 154 FISSION WAS DERIVED FROM THE DATA OF REF. 34 WHICH REPORTED THE 9040 1451 155 PHOTON SPECTRUM AND TOTAL PHOTON ENERGY FOR THERMAL FISSION OF 9040 1451 156 U-235. IT WAS ASSUMED THAT THE MULTIPLICITY IS INDEPENDENT OF 9040 1451 157 INCIDENT NEUTRON ENERGY. 9040 1451 158 MT = 102 9040 1451 159 FOR ALL INCIDENT NEUTRON ENERGIES PHOTON PRODUCTION FROM 9040 1451 160 NEUTRON CAPTURE IS REPRESENTED BY AN ENERGY DEPENDENT MULTIPLI- 9040 1451 161 CITY TO BE APPLIED TO THE (N,GAMMA) CROSS SECTION AND BY AN 9040 1451 162 ENERGY INDEPENDENT SPECTRUM. THE SPECTRUM USED WAS BASED ON AN 9040 1451 163 UNDOCUMENTED MEASURED SPECTRUM FOR U-238 WITH A MINOR ADJUSTMENT9040 1451 164 FOR SMALL Q-VALUE DIFFERENCE BETWEEN TH-232 AND U-238. THE 9040 1451 165 AVERAGE ENERGY OF TE ASSUMED SPECTRUM WAS THEN DIVIDED INTO THE 9040 1451 166 Q-VALUE TO OBTAIN A MULTIPLICITY AT ZERO NEUTRON ENERGY. THE 9040 1451 167 MULTIPLICITY AT 20 MEV WAS OBTAINED (REF 35) BY USE OF THE 9040 1451 168 FORMULA M(E) = M0(EN+Q)/Q WHERE M0 IS THE MULTIPLICITY AT ZERO 9040 1451 169 NEUTRON ENERGY AS DESCRIBED ABOVE. 9040 1451 170 MF = 13 9040 1451 171 MT = 3 9040 1451 172 EXPLICIT REPRESENTATION OF THREE PHOTONS (.04971, .1632 AND 9040 1451 173 .3344 MEV) FROM INELASTIC SCATTERING WAS DERIVED FROM FILE 3 9040 1451 174 DATA AND KNOWN BRANCHING RATIOS. FOR INCIDENT NEUTRON ENERGIES 9040 1451 175 GT .7251 MEV THE METHOD OF REF. 36 WAS USED TO CALCULATE PHOTON 9040 1451 176 PRODUCTION CROSS SECTIONS AND SPECTRA FROM ALL REACTIONS EXCEPT 9040 1451 177 PHOTONS FROM THE FIRST THREE INELASTIC GROUPS, NEUTRON CAPTURE 9040 1451 178 AND NEUTRON-INDUCED FISSION. 9040 1451 179 MF = 14 9040 1451 180 MT = 3,18,102 ALL PHOTONS WERE ASSUMED TO BE ISOTROPIC 9040 1451 181 MF = 15 9040 1451 182 MT = 3 9040 1451 183 PHOTON SPECTRA WERE OBTAINED USING THE METHOD OF REF. 36. 9040 1451 184 MT = 18 9040 1451 185 THE MEASURED PHOTON SPECTRUM OF REF. 34 WAS USED FOR ALL 9040 1451 186 INCIDENT NEUTRON ENERGIES BECAUSE THERE ARE NO EXPERIMENTAL DATA9040 1451 187 FOR TH-232. 9040 1451 188 MT = 102 9040 1451 189 THE SECTRUM USED WAS BASED ON AN UNDOCUMENTED MEASURED 9040 1451 190 PHOTON SPECTRUM AT THERMAL NEUTRON ENERGY FOR U-238 WITH A MINOR9040 1451 191 ADJUSTMENT FOR THE SMALL Q-VALUE DIFFERENCE BETWEEN U-238 AND TH9040 1451 192 -232. IT WAS ASSUMED THAT THE SPECTRUM REMAINED UNCHANGED FOR 9040 1451 193 ALL INCIDENT NEUTRON ENERGIES. 9040 1451 194 MF = 31 9040 1451 195 MT = 452 BY R. GWIN (REF. 4) 9040 1451 196 MF = 33 9040 1451 197 MT = 18,102 BASED ON ERROR ESTIMATES IN THESE CROSS SECTIONS IN 9040 1451 198 REF. 32,1 9040 1451 199 9040 1451 200 PRINCIPAL REFERENCES 9040 1451 201 9040 1451 202 1 J.W.MEADOWS,W.P.POENITZ,A.B.SMITH,D.L.SMITH,J.F.WHALEN AND 9040 1451 203 R.J.HOWERTON ANL/NDM-35(FEB.1978) 9040 1451 204 2 D.F.NEWMAN,B.R.LEONARD JR.ET.AL. EPRI NP-222,MAY1977 9040 1451 205 3 G.DE SAUSSURE AND R.L.MACKLIN ORNL/TM-6161(ENDF-255)DEC.1977 9040 1451 206 4 R.GWIN ORNL/TM-6245(ENDF-262)MAY1978. 9040 1451 207 5 M.C.BRADY AND T.R.ENGLAND NSE 103,129(1989) 9040 1451 208 **DATA INSERTED INTO FILE AT BNL** 9040 1451 209 6. R.SHER + C.BECK EPRI 1771/81 + REV. 1/83 + PC TO MAGURNO 2/83 9040 1451 210 7 S.F.MUGHABGHAB AND D.I.GARBER,BNL-325(3RD EDN)1973 9040 1451 211 8 H.DERRIEN,NEANDC(E)163U(1975) 9040 1451 212 9 J.F.WHALEN AND A.B.SMITH,NUC.SCI.AND ENG.67,129(1978) 9040 1451 213 10J.MEADOWS,A.SMITH AND J.WHALEN,PRIV.COMM.1977 9040 1451 214 11U.FASOLI ET.AL.NUCL.PHYS.A151,369(1970) 9040 1451 215 12M.DIVADEENAM ET.AL. DISS.ABS.28,3834(1968) 9040 1451 216 13C.UTTLEY ET.AL.66PARIS,1,165,1966 9040 1451 217 14L.GREEN ET.AL.PROC.CONF.ON NUCL.CROSS-SECTIONS AND TECHNOLOGY, 9040 1451 218 KNOXVILLE,1,325(1971) 9040 1451 219 15D.FOSTER ET.AL.PRIV.COMM(1967) 9040 1451 220 16R.BATCHELOR ET.AL.NUCL.PHYS.65,236(1956) 9040 1451 221 17J.COON ET.AL.PHYS.REV.88,562(1952) 9040 1451 222 18P.GUENTHER ET.AL.ACCEPTED FOR PUBLICATION NUC.SCI.AND ENG.(19779040 1451 223 19C.PHILIS ET.AL. ANL/NDM-28(1977) 9040 1451 224 20A.SMITH PHYS.REV.126,718(1962) 9040 1451 225 21W.MCMURRAY ET.AL.SOUTHERN UNIV.NUCLEAR INST.REPORT,SUNI-41(19759040 1451 226 22J.HAOUAT ETAL.PROC.INER.CONF.ON INTERACTIONS OF NEUTRONS WITH 9040 1451 227 NUCLEI,CONF-760715(1976) 9040 1451 228 23R.BATCHELOR AND J.TOWLE,NUCL.PHYS.65,236(1965) 9040 1451 229 24R.BATCHELOR AND J.TOWLE,PROC.PHYS.SOC.73,193(1959) 9040 1451 230 25A.SMITH,PRIV.COMM,1970 AND 1977 9040 1451 231 26A.SMITH ET.AL.ACCEPTED FOR PUBLICATION NUC.SCI.AND ENG.(1977) 9040 1451 232 27M.SEGEV.ET.AL.TRANS.AM.NUCL.SOC,22,679(1975)AND PRIV.COMM(1976)9040 1451 233 28R.J.HOWERTON AND R.J.DOYAS,NUCL.SCI AND ENG,46,414(1971) 9040 1451 234 29YU.A.VASIL'EV ET.AL.PHYSICS OF NUCLEAR FISSION,N.A.PERFILOV AND9040 1451 235 V.P.EISMONT(EDS),ISRAEL PROGRAM OF SCI.TRANS.JERUSALEM(1964) 9040 1451 236 30E.M.PENNINGTON,PRIVATE COMMUNICATION(1973) 9040 1451 237 31M.R.BHAT,ENDF-268(TO BE PUBLISHED) 9040 1451 238 32R.E.CHRIEN AND H.LIOU(1978) TO BE PUBLISHED 9040 1451 239 33W.P.POENITZ,ANL/NDM-45(1978) TO BE PUBLISHED 9040 1451 240 34R.W.PEELE AND F.C.MAIENSCHEIN, NUCL.SCI.ENG. 40, 485 (1970) 9040 1451 241 35R.J. HOWERTON, D.E. CULLEN, R.C. HAIGHT, M.H. MACGREGOR, S.T. 9040 1451 242 PERKINS, AND E.F. PLECHARTY, "THE LLL EVALUATED NUCLEAR DATA 9040 1451 243 LIBRARY (ENDL): EVALUATION TECHNIQUES, REACTION INDEX, AND 9040 1451 244 DESCRIPTIONS OF INDIVIDUAL EVALUATIONS," UCRL-50400, VOL. 15, 9040 1451 245 PART A, LAWERENCE LIVERMORE LABORATORY (1975). 9040 1451 246 36S.T.PERKINS,R.C.HAIGHT AND R.J.HOWERTON,NUCL.SCI.ENG.57,1(1975)9040 1451 247 37D.K.OLSEN, ORNL/TM-8056(1982), ENDF-319. 9040 1451 248 1 451 252 19040 1451 249 2 151 691 09040 1451 250 3 16 12 09040 1451 251 3 102 107 09040 1451 252 9040 1 0 253 9040 0 0 254 9.023200+4 2.300400+2 0 0 1 09040 2151 255 9.023200+4 1.000000+0 0 0 2 09040 2151 256 5.000000+0 4.000000+3 1 2 0 09040 2151 257 0.000000+0 9.720000-1 0 0 2 09040 2151 258 2.300400+2 0.000000+0 0 0 1458 2439040 2151 259 -2.220000+1 5.000000-1 2.746600-2 6.266000-3 2.120000-2 0.000000+09040 2151 260 -2.952000+0 5.000000-1 2.212800-2 9.277000-4 2.120000-2 0.000000+09040 2151 261 2.180600+1 5.000000-1 2.716000-2 2.060000-3 2.510000-2 0.000000+09040 2151 262 2.346400+1 5.000000-1 3.045000-2 3.850000-3 2.660000-2 0.000000+09040 2151 263 5.951900+1 5.000000-1 2.780000-2 3.800000-3 2.400000-2 0.000000+09040 2151 264 6.923200+1 5.000000-1 6.620000-2 4.320000-2 2.300000-2 0.000000+09040 2151 265 1.130300+2 5.000000-1 3.663000-2 1.313000-2 2.350000-2 0.000000+09040 2151 266 1.208700+2 5.000000-1 4.651000-2 2.251000-2 2.400000-2 0.000000+09040 2151 267 1.291900+2 5.000000-1 2.258100-2 3.381000-3 1.920000-2 0.000000+09040 2151 268 1.543600+2 5.000000-1 2.459900-2 1.986000-4 2.440000-2 0.000000+09040 2151 269 1.703900+2 5.000000-1 8.655000-2 6.125000-2 2.530000-2 0.000000+09040 2151 270 1.927200+2 5.000000-1 3.840000-2 1.690000-2 2.150000-2 0.000000+09040 2151 271 1.994000+2 5.000000-1 2.964000-2 1.024000-2 1.940000-2 0.000000+09040 2151 272 2.195200+2 5.000000-1 2.444400-2 4.364000-5 2.440000-2 0.000000+09040 2151 273 2.212900+2 5.000000-1 5.475000-2 3.025000-2 2.450000-2 0.000000+09040 2151 274 2.516500+2 5.000000-1 5.788000-2 3.178000-2 2.610000-2 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9.600000-4 3.842570+1 9.800000-4 3.803120+1 1.000000-3 3.764830+19040 3102 979 1.200000-3 3.436570+1 1.400000-3 3.181280+1 1.600000-3 2.975560+19040 3102 980 1.800000-3 2.805110+1 2.000000-3 2.660900+1 2.200000-3 2.536810+19040 3102 981 2.400000-3 2.428650+1 2.530000-3 2.365290+1 2.600000-3 2.333120+19040 3102 982 2.800000-3 2.248000+1 3.000000-3 2.171610+1 3.200000-3 2.102420+19040 3102 983 3.400000-3 2.039450+1 3.600000-3 1.981830+1 3.800000-3 1.928770+19040 3102 984 4.000000-3 1.879790+1 4.200000-3 1.834310+1 4.400000-3 1.791940+19040 3102 985 4.600000-3 1.752390+1 4.800000-3 1.715370+1 5.000000-3 1.680480+19040 3102 986 5.200000-3 1.647730+1 5.400000-3 1.616730+1 5.600000-3 1.587480+19040 3102 987 5.800000-3 1.559790+1 6.000000-3 1.533360+1 6.200000-3 1.508280+19040 3102 988 6.400000-3 1.484380+1 6.600000-3 1.461640+1 6.800000-3 1.439770+19040 3102 989 7.000000-3 1.418980+1 7.200000-3 1.398960+1 7.400000-3 1.379820+19040 3102 990 7.600000-3 1.361450+1 7.800000-3 1.343760+1 8.000000-3 1.326660+19040 3102 991 8.200000-3 1.310330+1 8.400000-3 1.294490+1 8.600000-3 1.279240+19040 3102 992 8.800000-3 1.264470+1 9.000000-3 1.250280+1 9.200000-3 1.236480+19040 3102 993 9.400000-3 1.223070+1 9.600000-3 1.210150+1 9.800000-3 1.197710+19040 3102 994 1.000000-2 1.185560+1 1.200000-2 1.081190+1 1.400000-2 1.000050+19040 3102 995 1.600000-2 9.345900+0 1.800000-2 8.803170+0 2.000000-2 8.343620+09040 3102 996 2.200000-2 7.947910+0 2.400000-2 7.602450+0 2.530000-2 7.400000+09040 3102 997 2.600000-2 7.298400+0 2.800000-2 7.029600+0 3.000000-2 6.788000+09040 3102 998 3.200000-2 6.569400+0 3.400000-2 6.370200+0 3.600000-2 6.187900+09040 3102 999 3.800000-2 6.020000+0 4.000000-2 5.864800+0 4.200000-2 5.720700+09040 3102 1000 4.400000-2 5.586600+0 4.600000-2 5.461300+0 4.800000-2 5.343700+09040 3102 1001 5.000000-2 5.233300+0 5.200000-2 5.129200+0 5.400000-2 5.031100+09040 3102 1002 5.600000-2 4.938100+0 5.800000-2 4.849900+0 6.000000-2 4.766100+09040 3102 1003 6.200000-2 4.686400+0 6.400000-2 4.610500+0 6.600000-2 4.538000+09040 3102 1004 6.800000-2 4.468600+0 7.000000-2 4.402300+0 7.200000-2 4.338700+09040 3102 1005 7.400000-2 4.277700+0 7.600000-2 4.219100+0 7.800000-2 4.162800+09040 3102 1006 8.000000-2 4.108400+0 8.200000-2 4.056200+0 8.400000-2 4.005800+09040 3102 1007 8.600000-2 3.957000+0 8.800000-2 3.910000+0 9.000000-2 3.864600+09040 3102 1008 9.200000-2 3.820500+0 9.400000-2 3.777900+0 9.600000-2 3.736700+09040 3102 1009 9.800000-2 3.696600+0 1.000000-1 3.657800+0 1.200000-1 3.323800+09040 3102 1010 1.400000-1 3.063300+0 1.600000-1 2.852600+0 1.800000-1 2.677400+09040 3102 1011 2.000000-1 2.528800+0 2.200000-1 2.400500+0 2.400000-1 2.288200+09040 3102 1012 2.530000-1 2.222400+0 2.600000-1 2.189000+0 2.800000-1 2.100300+09040 3102 1013 3.000000-1 2.020400+0 3.200000-1 1.948000+0 3.400000-1 1.881900+09040 3102 1014 3.600000-1 1.821300+0 3.800000-1 1.765400+0 4.000000-1 1.713600+09040 3102 1015 4.200000-1 1.665500+0 4.400000-1 1.620700+0 4.600000-1 1.578700+09040 3102 1016 4.800000-1 1.539300+0 5.000000-1 1.502200+0 5.200000-1 1.467300+09040 3102 1017 5.400000-1 1.434300+0 5.600000-1 1.403100+0 5.800000-1 1.373300+09040 3102 1018 6.000000-1 1.345100+0 6.200000-1 1.318300+0 6.400000-1 1.292600+09040 3102 1019 6.600000-1 1.268200+0 6.800000-1 1.244800+0 7.000000-1 1.222400+09040 3102 1020 7.200000-1 1.200900+0 7.400000-1 1.180300+0 7.600000-1 1.160500+09040 3102 1021 7.800000-1 1.141500+0 8.000000-1 1.123200+0 8.200000-1 1.105500+09040 3102 1022 8.400000-1 1.088500+0 8.600000-1 1.072000+0 8.800000-1 1.056100+09040 3102 1023 9.000000-1 1.040800+0 9.200000-1 1.026000+0 9.400000-1 1.011600+09040 3102 1024 9.600000-1 9.977300-1 9.800000-1 9.842400-1 1.000000+0 9.711600-19040 3102 1025 1.200000+0 8.591200-1 1.400000+0 7.724400-1 1.600000+0 7.032300-19040 3102 1026 1.800000+0 6.465100-1 2.000000+0 5.990700-1 2.200000+0 5.588300-19040 3102 1027 2.400000+0 5.242800-1 2.530000+0 5.043100-1 2.600000+0 4.942200-19040 3102 1028 2.744900+0 4.748620-1 2.800000+0 4.679600-1 3.000000+0 4.446900-19040 3102 1029 3.200000+0 4.240200-1 3.400000+0 4.055400-1 3.600000+0 3.888600-19040 3102 1030 3.800000+0 3.738800-1 4.000000+0 3.602000-1 4.200000+0 3.478200-19040 3102 1031 4.400000+0 3.364400-1 4.600000+0 3.260500-1 4.800000+0 3.164600-19040 3102 1032 5.000000+0 3.076800-1 5.000000+0 1.979800-1 5.500000+0 1.887700-19040 3102 1033 6.000000+0 1.807300-1 6.500000+0 1.736400-1 7.200000+0 1.649800-19040 3102 1034 8.000000+0 1.565200-1 9.000000+0 1.475700-1 1.000000+1 1.399900-19040 3102 1035 1.100000+1 1.334800-1 1.220000+1 1.267400-1 1.350000+1 1.204900-19040 3102 1036 1.500000+1 1.143000-1 1.650000+1 1.089900-1 1.800000+1 1.043500-19040 3102 1037 2.000000+1 9.899100-2 2.200000+1 9.438400-2 2.400000+1 9.036600-29040 3102 1038 2.700000+1 8.519800-2 3.000000+1 8.082600-2 3.300000+1 7.706400-29040 3102 1039 3.600000+1 7.378300-2 4.000000+1 6.999700-2 4.500000+1 6.599400-29040 3102 1040 5.000000+1 6.260700-2 5.500000+1 5.969400-2 6.000000+1 8.438400-29040 3102 1041 6.500000+1 8.245300-2 7.200000+1 8.015100-2 8.000000+1 7.797100-29040 3102 1042 9.000000+1 7.576300-2 1.000000+2 7.399000-2 1.100000+2 7.255200-29040 3102 1043 1.220000+2 7.116900-2 1.350000+2 6.999900-2 1.500000+2 6.897600-29040 3102 1044 1.650000+2 6.822700-2 1.800000+2 6.769300-2 2.000000+2 6.724400-29040 3102 1045 2.200000+2 6.703100-2 2.400000+2 6.700400-2 2.700000+2 6.723600-29040 3102 1046 3.000000+2 6.771900-2 3.300000+2 6.839600-2 3.600000+2 6.922400-29040 3102 1047 4.000000+2 7.051500-2 4.500000+2 7.235900-2 5.000000+2 7.439800-29040 3102 1048 5.500000+2 7.658700-2 6.000000+2 7.889300-2 6.500000+2 8.129400-29040 3102 1049 7.200000+2 8.478200-2 8.000000+2 8.891200-2 9.000000+2 9.423700-29040 3102 1050 1.000000+3 9.969900-2 1.100000+3 1.052700-1 1.220000+3 1.120600-19040 3102 1051 1.350000+3 1.195200-1 1.500000+3 1.282300-1 1.650000+3 1.370300-19040 3102 1052 1.800000+3 1.458900-1 2.000000+3 1.578000-1 2.200000+3 1.697800-19040 3102 1053 2.400000+3 1.818200-1 2.700000+3 1.999600-1 3.000000+3 2.181800-19040 3102 1054 3.300000+3 2.364700-1 3.600000+3 2.548000-1 4.000000+3 2.793000-19040 3102 1055 4.000000+3 0.000000+0 2.500000+4 0.000000+0 5.000000+4 0.000000+09040 3102 1056 5.000000+4 3.900000-1 6.000000+4 3.300000-1 7.000000+4 2.900000-19040 3102 1057 8.000000+4 2.600000-1 9.000000+4 2.400000-1 1.000000+5 2.250000-19040 3102 1058 1.250000+5 2.020000-1 1.500000+5 1.870000-1 1.750000+5 1.780000-19040 3102 1059 2.000000+5 1.650000-1 2.500000+5 1.500000-1 3.000000+5 1.450000-19040 3102 1060 4.000000+5 1.420000-1 5.000000+5 1.500000-1 6.000000+5 1.650000-19040 3102 1061 7.000000+5 1.650000-1 8.000000+5 1.600000-1 9.000000+5 1.480000-19040 3102 1062 1.000000+6 1.350000-1 1.250000+6 1.130000-1 1.500000+6 9.900000-29040 3102 1063 1.750000+6 8.400000-2 2.000000+6 6.400000-2 2.500000+6 4.200000-29040 3102 1064 3.000000+6 3.000000-2 4.000000+6 1.800000-2 6.000000+6 8.000000-39040 3102 1065 8.000000+6 3.800000-3 1.000000+7 2.000000-3 1.400000+7 1.500000-39040 3102 1066 2.000000+7 1.400000-3 0.000000+0 0.000000+0 0.000000+0 0.000000+09040 3102 1067 9040 3 0 1068 9040 0 0 1069 0 0 0 1070 9.123100+4 2.290500+2 1 1 0 19131 1451 1 0.000000+0 1.000000+0 0 0 0 69131 1451 2 1.000000+0 0.000000+0 0 0 10 69131 1451 3 0.000000+0 0.000000+0 0 0 52 39131 1451 4 91-PA-231 HEDL EVAL-NOV77 MANN 9131 1451 5 DIST-FEB90 900205 9131 1451 6 ----ENDF/B-VI MATERIAL 9131 9131 1451 7 -----INCIDENT NEUTRON DATA 9131 1451 8 ------ENDF-6 FORMAT 9131 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9131 1451 10 ACTIVATION II 9131 1451 11 ******************************************************************9131 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 9131 1451 13 * * * * * * *9131 1451 14 MF=1 9131 1451 15 MT=452 NU. SYSTEMATICS (REF. 4),MT=455 BRADY+,NSE 103,129(1989) 9131 1451 16 MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF. 5) 9131 1451 17 MF=2 9131 1451 18 MT=151 RESOLVED PARAMETERS FROM BNL-325 (REF. 1), EXCEPT FOR 9131 1451 19 NEGATIVE ENERGY RESONANCE WHERE NEUTRON AND FISSION WIDTHS 9131 1451 20 CHANGED TO MATCH THERMAL CAPTURE AND FISSION CROSS SECTIONS 9131 1451 21 (227. B AND .010 B VERSUS 210. +- 20. B AND .010 +- .005 B FROM9131 1451 22 BNL-325, RESPECTIVELY). THE CALCULATED CAPTURE RESONANCE 9131 1451 23 INTEGRAL FROM THE RESOLVED REGION (1237) IS SLIGHTLY LESS 9131 1451 24 THAN FOR ENTIRE REGION GIVEN IN BNL-325 (1500+-100). 9131 1451 25 UNRESOLVED PARAMETERS (E=14.3 TO 1000 EV) BASED ON RESOLVED. 9131 1451 26 MF=3 9131 1451 27 MT=1 TOTAL. FROM OPTICAL MODEL 9131 1451 28 MT=2 ELASTIC. DIFFERENCE BETWEEN TOTAL AND SUM OF PARTIALS 9131 1451 29 MT=4 INELASTIC. SUM OF MT=51,...,62,91 9131 1451 30 MT=16 (N,2N) 9131 1451 31 MT=18 FISSION. BASED ON MUIR AND VESSER (REF. 2), LASL BOMB 9131 1451 32 DATA. LOW ENERGY (.LT. 100 KEV) AND HIGH ENERGY (.GT. 3 MEV)9131 1451 33 FROM STATISTICAL MODEL CALCULATIONS (REF. 3). 9131 1451 34 MT=51,...,62,91 INELASTIC. BASED ON STATISTICAL MODEL 9131 1451 35 CALCULATIONS (REF. 3). 9131 1451 36 MT=102 CAPTURE. BASED ON STATISTICAL MODEL CALCULATIONS (REF. 9131 1451 37 3) 9131 1451 38 MF=4 9131 1451 39 MT=1 TOTAL. BASED ON OPTICAL MODEL (POTENTIAL SCATTERING ) 9131 1451 40 MT=16 (N,2N). ASSUMED ISOTROPIC 9131 1451 41 MT=18 FISSION ASSUMED ISOTROPIC. 9131 1451 42 MT=51,...,62,91 INELASTIC. ASSUMED ISOTROPIC 9131 1451 43 MF=5 9131 1451 44 MT=16 (N,2N). SIMPLE EVAPORATION MODEL 9131 1451 45 MT=18 FISSION. MAXWELLIAN DISTRIBUTION (T=1.33 MEV) 9131 1451 46 MT=91 CONTINUUM INELASTIC. SIMPLE EVAPORATION MODEL. 9131 1451 47 MT=455 DELAYED NEUT. YIELDS, BRADY,ENGLAND NSE 103,129(1989) 9131 1451 48 REFERENCES 9131 1451 49 1. S.F. MUGHABGHAB AND D.I. GARBER, BNL-325, VOL. 1 (1973), 9131 1451 50 BROOKHAVEN NATIONAL LABORATORY. 9131 1451 51 2. D.W. MUIR AND L.R. VESSOR, LA-4648-MS (1971), LOS ALAMOS 9131 1451 52 SCIENTIFIC LABORATORY 9131 1451 53 3. F.M. MANN AND R.E. SCHENTER, HEDL-TME-77-54 (1977) HANFORD 9131 1451 54 4. R.J. HOWERTON, NUCL. SC. AND ENG. 62(1977)438 9131 1451 55 5. R. SHER (PRIV. COMM., 1977) 9131 1451 56 1 451 59 19131 1451 57 2 151 53 09131 1451 58 3 102 15 09131 1451 59 9131 1 0 60 9131 0 0 61 9.123100+4 2.290500+2 0 0 1 09131 2151 62 9.123100+4 1.000000+0 0 1 2 09131 2151 63 1.000000-5 1.430000+1 1 1 0 09131 2151 64 1.500000+0 8.333300-1 0 0 1 09131 2151 65 2.290500+2 0.000000+0 0 0 186 319131 2151 66 -3.180000-1 1.000000+0 5.612200-2 1.200000-4 5.600000-2 1.800000-69131 2151 67 3.960000-1 1.000000+0 4.307700-2 7.529400-5 4.300000-2 1.800000-69131 2151 68 4.940000-1 2.000000+0 4.002100-2 8.470600-6 4.000000-2 1.300000-59131 2151 69 7.430000-1 2.000000+0 4.001400-2 7.247100-6 4.000000-2 7.000000-69131 2151 70 1.238000+0 2.000000+0 4.603200-2 2.635300-5 4.600000-2 6.000000-69131 2151 71 1.405000+0 1.000000+0 4.500810-2 1.129400-6 4.500000-2 7.000000-69131 2151 72 1.960000+0 1.000000+0 4.601370-2 6.682400-6 4.600000-2 7.000000-69131 2151 73 2.790000+0 2.000000+0 3.901630-2 9.317600-6 3.900000-2 7.000000-69131 2151 74 3.483000+0 2.000000+0 4.805120-2 4.423500-5 4.800000-2 7.000000-69131 2151 75 4.120000+0 2.000000+0 5.008700-2 8.000000-5 5.000000-2 7.000000-69131 2151 76 4.350000+0 2.000000+0 6.006350-2 5.647100-5 6.000000-2 7.000000-69131 2151 77 4.530000+0 2.000000+0 5.502700-2 1.600000-5 5.500000-2 7.000000-69131 2151 78 5.060000+0 2.000000+0 6.346820-2 4.611800-4 6.300000-2 7.000000-69131 2151 79 5.280000+0 1.000000+0 4.508700-2 8.000000-5 4.500000-2 7.000000-69131 2151 80 5.630000+0 1.000000+0 4.505100-2 4.423500-5 4.500000-2 7.000000-69131 2151 81 5.820000+0 2.000000+0 4.506200-2 5.458800-5 4.500000-2 7.000000-69131 2151 82 6.550000+0 2.000000+0 5.005300-2 4.611800-5 5.000000-2 7.000000-69131 2151 83 6.870000+0 1.000000+0 4.624200-2 2.352900-4 4.600000-2 7.000000-69131 2151 84 7.570000+0 2.000000+0 6.009500-2 8.752900-5 6.000000-2 7.000000-69131 2151 85 7.820000+0 1.000000+0 5.517800-2 1.712900-4 5.500000-2 7.000000-69131 2151 86 8.730000+0 2.000000+0 5.770300-2 6.964700-4 5.700000-2 7.000000-69131 2151 87 9.260000+0 2.000000+0 5.505000-2 4.329400-5 5.500000-2 7.000000-69131 2151 88 9.700000+0 2.000000+0 5.022300-2 2.164700-4 5.000000-2 7.000000-69131 2151 89 1.033000+1 2.000000+0 4.966600-2 6.588200-4 4.900000-2 7.000000-69131 2151 90 1.076000+1 2.000000+0 3.032800-2 3.209400-4 3.000000-2 7.000000-69131 2151 91 1.126000+1 2.000000+0 4.534800-2 3.407100-4 4.500000-2 7.000000-69131 2151 92 1.167000+1 1.000000+0 4.565000-2 6.428200-4 4.500000-2 7.000000-69131 2151 93 1.208000+1 2.000000+0 4.502700-2 2.032900-5 4.500000-2 7.000000-69131 2151 94 1.326000+1 2.000000+0 4.576100-2 7.538800-4 4.500000-2 7.000000-69131 2151 95 1.338000+1 2.000000+0 4.603900-2 1.032500-3 4.500000-2 7.000000-69131 2151 96 1.410000+1 2.000000+0 4.555100-2 5.440000-4 4.500000-2 7.000000-69131 2151 97 1.430000+1 1.000000+3 2 2 0 09131 2151 98 1.500000+0 8.333300-1 0 0 1 09131 2151 99 2.290500+2 0.000000+0 0 0 2 09131 2151 100 1.000000+0 0.000000+0 2 0 36 59131 2151 101 1.000000+0 0.000000+0 1.000000+0 1.000000+0 0.000000+0 1.000000+09131 2151 102 1.430000+1 1.167600-1 0.000000+0 1.305800-5 4.500000-2 7.000000-69131 2151 103 3.000000+1 1.167600-1 0.000000+0 1.305800-5 4.500000-2 7.000000-69131 2151 104 1.000000+2 1.167600-1 0.000000+0 1.305800-5 4.500000-2 7.000000-69131 2151 105 3.000000+2 1.167600-1 0.000000+0 1.305800-5 4.500000-2 7.000000-69131 2151 106 1.000000+3 1.167600-1 0.000000+0 1.305800-5 4.500000-2 7.000000-69131 2151 107 2.000000+0 0.000000+0 2 0 36 59131 2151 108 1.000000+0 0.000000+0 1.000000+0 1.000000+0 0.000000+0 1.000000+09131 2151 109 1.430000+1 5.604300-1 0.000000+0 6.267600-5 4.500000-2 7.000000-69131 2151 110 3.000000+1 5.604300-1 0.000000+0 6.267600-5 4.500000-2 7.000000-69131 2151 111 1.000000+2 5.604300-1 0.000000+0 6.267600-5 4.500000-2 7.000000-69131 2151 112 3.000000+2 5.604300-1 0.000000+0 6.267600-5 4.500000-2 7.000000-69131 2151 113 1.000000+3 5.604300-1 0.000000+0 6.267600-5 4.500000-2 7.000000-69131 2151 114 9131 2 0 115 9131 0 0 116 9.123100+4 2.290500+2 0 0 0 09131 3102 117 5.560000+6 5.560000+6 0 0 1 369131 3102 118 36 2 0 0 0 09131 3102 119 1.000000-5 0.000000+0 1.000000+3 0.000000+0 1.000000+3 1.344600+19131 3102 120 2.000000+3 1.150000+1 3.000000+3 1.050000+1 5.000000+3 9.000000+09131 3102 121 9.000000+3 7.700000+0 1.000000+4 7.330000+0 2.000000+4 5.220000+09131 3102 122 3.000000+4 4.420000+0 5.000000+4 3.680000+0 5.800000+4 3.400000+09131 3102 123 7.800000+4 3.010000+0 8.500000+4 2.860000+0 1.000000+5 2.660000+09131 3102 124 1.010000+5 2.640000+0 1.020000+5 2.610000+0 1.120000+5 2.340000+09131 3102 125 1.340000+5 2.020000+0 1.720000+5 1.760000+0 1.740000+5 1.750000+09131 3102 126 1.840000+5 1.680000+0 1.890000+5 1.640000+0 2.000000+5 1.600000+09131 3102 127 3.000000+5 1.130000+0 5.000000+5 7.184900-1 7.000000+5 4.830800-19131 3102 128 1.000000+6 2.956800-1 1.200000+6 2.236500-1 1.500000+6 2.089100-19131 3102 129 2.000000+6 1.544300-1 3.000000+6 1.045300-1 5.000000+6 7.834700-29131 3102 130 1.000000+7 7.900600-2 1.500000+7 1.205300-1 2.000000+7 2.391800-29131 3102 131 9131 3 0 132 9131 0 0 133 0 0 0 134 9.223300+4 2.310430+2 -1 1 0 19222 1451 1 0.000000+0 1.000000+0 0 0 0 69222 1451 2 1.000000+0 0.000000+0 0 0 10 69222 1451 3 0.000000+0 0.000000+0 0 0 224 29222 1451 4 92-U -233 LANL,ORNL EVAL-DEC78 STEWART ET AL, L. WESTON 9222 1451 5 TANSAO 28, 721, 1978 DIST-FEB90 900205 9222 1451 6 ----ENDF/B-VI MATERIAL 9222 9222 1451 7 -----INCIDENT NEUTRON DATA 9222 1451 8 ------ENDF-6 FORMAT 9222 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9222 1451 10 ACTIVATION II 9222 1451 11 ******************************************************************9222 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 9222 1451 13 * * * * * * *9222 1451 14 9222 1451 15 GAMMA-RAY PRODUCTION ADDED 11/23/81 BY STEWART AND 9222 1451 16 BOICOURT (SECONDARY REFERENCE ON PU-239, SEE HUNTER AND9222 1451 17 STEWART, LA-4901). 9222 1451 18 9222 1451 19 THE FOLLOWING PEOPLE CONTRIBUTED TO VERSION V 9222 1451 20 9222 1451 21 LASL L. STEWART, D. MADLAND, AND P.G. YOUNG 9222 1451 22 ORNL L. WESTON, G. DESAUSSURE, AND R.Q. WRIGHT 9222 1451 23 HEDL F. MANN 9222 1451 24 BAPL N. STEEN 9222 1451 25 BNW B. R. LEONARD, JR. 9222 1451 26 BNL R. KINSEY 9222 1451 27 9222 1451 28 9222 1451 29 ******************************************************* 9222 1451 30 * THERMAL PARAMETERS (0.0253 EV) * 9222 1451 31 * * 9222 1451 32 * ETA 2.2959 CAPTURE 45.76 B * 9222 1451 33 * ALPHA 0.0866 FISSION 528.45 B * 9222 1451 34 * NU PROMPT 2.4873 ABSORPTION 574.21 B * 9222 1451 35 * NU TOTAL 2.4947 ELASTIC 12.6 B * 9222 1451 36 * TOTAL 586.81 B * 9222 1451 37 * * 9222 1451 38 ******************************************************* 9222 1451 39 9222 1451 40 9222 1451 41 FILE 1 9222 1451 42 MT=452 NU BAR TOTAL. SUM OF PROMPT PLUS DELAYED NU BAR. 9222 1451 43 USED THERMAL VALUE RECOMMENDED BY CSEWG STANDARDS SUB- 9222 1451 44 COMMITTEE OF 2.4947 ON 5/27/78. THIS VALUE IS ONE PER- 9222 1451 45 CENT LARGER THAN RECOMMENDED BY LEMMEL (REF 1) AND 9222 1451 46 0.13 PERCENT SMALLER THAN VERSION IV. USED CSEWG 9222 1451 47 RECOMMENDED VALUE FOR NU BAR FOR CF-252 OF 3.766 TO 9222 1451 48 EVALUATE THE ENERGY DEPENDENCE OF NU BAR PROMPT. 9222 1451 49 MT=455 NU BAR DELAYED. THE DELAYED YIELDS AND SPECTRA WERE 9222 1451 50 EVALUATED BY T.R.ENGLAND ET AL AT LANL 9222 1451 51 SEE REFERENCE 2 FOR TECHNICAL DETAILS. THE VALUES 9222 1451 52 HAVE BEEN CHANGED FROM PREVIOUS 9222 1451 53 ENDF/B VERSIONS. 9222 1451 54 MT=456 NU BAR PROMPT. THE ENERGY DEPENDENCE OF PROMPT NU BAR 9222 1451 55 IS CHANGED SIGNIFICANTLY FROM VERSION IV. ALTHOUGH 9222 1451 56 THE THERMAL VALUE IS SLIGHTLY LOWER, THE VALUE AROUND 9222 1451 57 1.5 MEV IS SIGNIFICANTLY HIGHER AND HAS A DIFFERENT 9222 1451 58 SHAPE WITH THREE SLIGHTLY DIFFERENT SLOPES. THIS 9222 1451 59 EVALUATION RELIED HEAVILY ON THE MEASUREMENTS WITH RESPECT9222 1451 60 TO U-235 AND CF-252 USING THE CSEWG RECOMMENDED STANDARDS.9222 1451 61 IN PARTICULAR, THE DATA OF BOLDEMAN, SERGACHEV, NURPEISOV,9222 1451 62 AND BLOCK (REF.5-7) WERE WEIGHTED AT ALL ENERGIES WHILE 9222 1451 63 THE MATHER (REF.8) MEASUREMENTS WERE RELIED UPON ONLY 9222 1451 64 AT HIGH ENERGIES. SMIRENKIN, FLEROV, AND PROTOPOPOV 9222 1451 65 (REF.9-11) ALSO CONTRIBUTED IN THE HIGH-ENERGY RANGE. 9222 1451 66 THIS EVALUATION DECOUPLES THE THERMAL VALUE BASED ON ETA 9222 1451 67 MEASUREMENTS FROM THE FAST RANGE. OTHERWISE, THE NU-BAR 9222 1451 68 ETA DISCREPANCY WOULD BE PERPETUATED TO 20 MEV. 9222 1451 69 (USED CF-252 PROMPT NU BAR OF 3.757). REC. BY CSEWG. 9222 1451 70 MT=458 ENERGY RELEASE PER FISSION FROM SHER REF.12 9222 1451 71 MT=151 RESOLVED RANGE EXTENDS TO 60 EV. MULTI-LEVEL PARAMETERS 9222 1451 72 PROVID(D BY DE SAUSSURE (ORNL) IN ADLER-ADLER FORMALISM 9222 1451 73 FROM ANALYSIS BY REYNOLDS (KAPL). VERSION IV HAD SLBW 9222 1451 74 BUT LARGE FLUCTUATIONS IN FILE 3 BACKGROUND FOR FISSION. 9222 1451 75 9222 1451 76 UNRESOLVED RANGE EXTENDS TO 10 KEV. VERSION IV WAS 9222 1451 77 POINTWISE OVER THIS RANGE. A RE-EVALUATION OF THE POINT 9222 1451 78 WISE CROSS SECTIONS BEGUN BY MANN (HEDL) WERE USED AS 9222 1451 79 THE STARTING POINT BY WESTON (ORNL), WHO OBTAINED NEW 9222 1451 80 AVERAGE CROSS SECTIONS FOR FISSION AND CAPTURE WHICH 9222 1451 81 REQUIRE NO FILE 3 BACKGROUNDS. FISSION CROSS SECTIONS 9222 1451 82 BASED ON CARLSON AND BEHRENS (REF 4), WESTON (REF 16), 9222 1451 83 CAO (REF 17), AND NIZAMUDDIN (REF 19). WESTON DATA 9222 1451 84 (REF 19) WERE USED FOR CAPTURE. USING A POTENTIAL SCAT- 9222 1451 85 TERING RADIUS OF 0.9893, REASONABLE AGREEMENT WITH PAT- 9222 1451 86 TENDENS TOTAL CROSS SECTION WAS OBTAINED (REF.20), ES- 9222 1451 87 PECIALLY BELOW 1 KEV. NEW MEASUREMENTS DESPERATELY 9222 1451 88 NEEDED IN THIS RANGE. 9222 1451 89 FILE OVER RESONANCE RANGE COMPILED BY R.Q. WRIGHT 9222 1451 90 9222 1451 91 9222 1451 92 FILE 3 9222 1451 93 THERMAL RANGE 9222 1451 94 THE CAPTURE AND FISSION CROSS SECTIONS WERE RENORMALIZED 9222 1451 95 BY N. STEEN (BAPL). THE ELASTIC SCATTERING IN THE THER- 9222 1451 96 MAL RANGE CHANGED SIGNIFICANTLY FROM VERSION IV TO CON- 9222 1451 97 FORM TO LEONARDS THERMAL AND WESTONS EVALUATION IN UN- 9222 1451 98 RESOLVED RANGE. THE TOTAL WAS ADJUSTED ACCORDINGLY. 9222 1451 99 9222 1451 100 9222 1451 101 GENERAL NOTE. MUCH OF THE FILE 3 DATA ABOVE 50 KEV RELIED 9222 1451 102 HEAVILY ON MODEL CALCULATIONS PERFORMED BY MADLAND (LASL). 9222 1451 103 CALCULATIONS WERE PARTICULARLY IMPORTANT FOR THIS ISOTOPE SINCE 9222 1451 104 EXPERIMENTAL INFORMATION WAS OFTEN INSUFFICIENT IF NOT COMPLETELY9222 1451 105 MISSING. A DETAILED DESCRIPTION OF THE METHODS USED CAN BE FOUND9222 1451 106 IN REFERENCE 3. NOTE THAT FOR CONVENIENCE, MANY OF THE SPECIFIC 9222 1451 107 REFERENCES FOUND IN BNL-325 ARE NOT REPEATED HERE. 9222 1451 108 9222 1451 109 MT=1 TOTAL CROSS SECTION. NO MEASUREMENTS EXIST FROM 10 TO 40 9222 1451 110 KEV THEREFORE AN EXTRAPOLATION WAS MADE TO GIVE REASONABLE9222 1451 111 AGREEMENT WITH RECENT ANL DATA (REF 13) ABOVE 40 KEV AND 9222 1451 112 CROSS SECTIONS PREDICTED BY MADLAND. THE PRESENT EVALUA- 9222 1451 113 TION, IS BASED ON RECENT ANL MEASUREMENTS AND EARLIER 9222 1451 114 WORK OF GREEN (BAPL) AND FOSTER (BNW), SEE REF 5, BNL-325.9222 1451 115 NO MEASUREMENTS EXIST ABOVE 15 MEV. THIS REEVALUATION 9222 1451 116 RESULTED IN AN INCREASED TOTAL CROSS SECTION UP TO 7 MEV. 9222 1451 117 THE INCREASE NEAR 1.6 MEV BEING AS LARGE AS 8 PERCENT, 9222 1451 118 WHILE THE FOSTER DATA INDICATE A DECREASE OF 4.8 PERCENT 9222 1451 119 NEAR 14 MEV. 9222 1451 120 MT=2 ELASTIC CROSS SECTION. (OBTAINED FROM TOTAL MINUS 9222 1451 121 REACTION) THE INCREASED TOTAL CROSS SECTION REQUIRED A 9222 1451 122 SIGNIFICANT INCREASE IN THE ELASTIC CROSS SECTION OVER 9222 1451 123 THE ENERGY RANGE TO 7 MEV. AT 14 MEV, THE ELASTIC WAS 9222 1451 124 DECREASED DUE TO THE DECREASE IN THE TOTAL. 9222 1451 125 MT=4 INELASTIC CROSS SECTION. SUM OF MT=51-54 AND MT=91. 9222 1451 126 THESE DATA WERE TAKEN FROM MODEL CALCULATIONS OF DISCRETE 9222 1451 127 AND CONTINUUM COMPOUND INELASTIC SCATTERING AND COUPLED- 9222 1451 128 CHANNEL DIRECT INELASTIC SCATTERING. 9222 1451 129 MT=16,17 TAKEN FROM HAUSER-FESHBACH STATISTICAL MODEL 9222 1451 130 CALCULATIONS PERFORMED BY MADLAND 9222 1451 131 MT=18 DATA FROM 10 KEV TO 100 KEV SPARSE AND REASONABLY 9222 1451 132 DISCREPANT. ABOVE 100 KEV, RELIED HEAVILY ON THE RATIO 9222 1451 133 MEASUREMENTS OF CARLSON AND BEHRENS (REF 4) AND THOSE OF 9222 1451 134 MEADOWS (REF 14) NORMALIZED TO VERSION V U-235 FISSION. 9222 1451 135 THE ABSOLUTE DATA OF POENITZ (REF 15) WERE ALSO EMPLOYED, 9222 1451 136 ALTHOUGH GOOD AGREEMENT AMONG THE SETS WAS LACKING. THE 9222 1451 137 EVALUATED CURVE WAS DRAWN AS SMOOTH AS POSSIBLE DUE TO 9222 1451 138 MAGNITUDE OF THE DISCREPANCY AMONG THE SETS. 9222 1451 139 MT=51-54 TAKEN FROM COMPOUND AND DIRECT INELASTIC SCAT. MODEL 9222 1451 140 CALCULATIONS OF MADLAND. 9222 1451 141 MT=102 NO DATA EXIST ABOVE 10 KEV EXCEPT FOR THE ALPHA MEASURE- 9222 1451 142 MENTS OF DIVEN AND HOPKINS (SEE REF.5) WHICH EXTEND TO 1 9222 1451 143 MEV. EXTRAPOLATED TO 20 MEV ASSUMING A RISE DUE TO 9222 1451 144 DIRECT CAPTURE. 9222 1451 145 9222 1451 146 FILE 4 9222 1451 147 ALL NEUTRON ANGULAR DISTRIBUTIONS ISOTROPIC IN LABORATORY 9222 1451 148 SYSTEM EXCEPT FOR THE ELASTIC (MT=2) WHICH WAS TAKEN 9222 1451 149 FROM VERSION IV. THE ELASTIC AND DIRECT INELASTIC SHOULD 9222 1451 150 BE MODIFIED IN THE NEXT UPDATE. 9222 1451 151 9222 1451 152 FILE 5 9222 1451 153 MT=16,17 REPRESENTED BY AN EVAPORATION SPECTRUM WITH LF=9. 9222 1451 154 MT=18 REPRESENTED BY AN ENERGY DEPENDENT WATT SPECTRUM WITH AN 9222 1451 155 AVERAGE ENERGY AT THERMAL OF 2.073 MEV. THIS SPECTRUM 9222 1451 156 BASED ON GRUNDL RATIO DATA TO U-235 AND PU-239. 9222 1451 157 MT=91 REPRESENTED BY AN EVAPORATION SPECTRUM WITH LF=9. 9222 1451 158 9222 1451 159 MT=455 DELAYED NEUTRON SPECTRA EVALUATED IN SIX TIME GROUPS BY 9222 1451 160 T.R.ENGLAND ET AL AT LANL (REF.2). 9222 1451 161 9222 1451 162 FILE 12 9222 1451 163 9222 1451 164 MT=4 TRANSITION PROBABILITIES USED FOR FOUR DISCRETE LEVELS 9222 1451 165 ASSUMING 60 PERCENT - 40 PERCENT SPLIT. CONTINUUM 9222 1451 166 ADDED ABOVE 300 KEV. DUE TO THE FACT THAT ONLY FOUR 9222 1451 167 LEVELS ARE INVOLVED, THE CONTINUUM PROBABILITY IS 9222 1451 168 LARGE. MT=4 IS ZERO ABOVE 1.09 MEV. 9222 1451 169 9222 1451 170 MT=18 MULTIPLICITIES TAKEN FROM HOFFMAN AND HOFFMAN, REF. 21.9222 1451 171 9222 1451 172 MT=102 MULTIPLICITIES GUESSED. NO DATA AVAILABLE. 9222 1451 173 9222 1451 174 FILE 13 9222 1451 175 9222 1451 176 MT=3 ABOVE 1.09 MEV, ALL GAMMA-RAY PRODUCTION REPRESENTED 9222 1451 177 BY THE NONELASTIC CROSS SECTION. DATA FOR PU-239 9222 1451 178 WERE MODIFIED FOR THIS CROSS SECTION. 9222 1451 179 9222 1451 180 FILE 14 9222 1451 181 9222 1451 182 MT=3, MT=4, MT=18, MT=102: ALL ASSUMED ISOTROPIC IN 9222 1451 183 LABORATORY SYSTEM. 9222 1451 184 9222 1451 185 FILE 15 9222 1451 186 9222 1451 187 MT=3 SPECTRA FOR MT = 3 TAKEN FROM PU-239, MAT 1399. 9222 1451 188 9222 1451 189 MT=4 CONTINUUM SPECTRA TAKEN FROM PU-239, MAT 1399. 9222 1451 190 9222 1451 191 MT=18 TAKEN FROM PU-239, MAT 1399. 9222 1451 192 9222 1451 193 MT=102 TAKEN FROM PU-239, MAT 1399 AFTER ADJUSTMENT FOR ENERGY9222 1451 194 DIFFERENCES. 9222 1451 195 9222 1451 196 *************************************************** 9222 1451 197 9222 1451 198 REFERENCES 9222 1451 199 1. H.D. LEMMEL, PROC. OF A SYMPOSIUM ON NEUTRON STANDARDS 9222 1451 200 AND APPLICATIONS HELD AT NBS ON MARCH 28-31,1977. SEE P.170 9222 1451 201 2. M.C. BRADY AND T.R. ENGLAND, NSE 103,129(1989) 9222 1451 202 3. D.G. MADLAND AND P.G. YOUNG, LA-7200-PR (1978) P.11. 9222 1451 203 4. G.W. CARLSON AND J.W. BEHRENS, NSE 66,205 (1978). 9222 1451 204 5. D.I. GARBER AND R.R. KINSEY, BNL-325,VOL.II (1976). 9222 1451 205 6. J.W. BOLDEMAN, JNE 25,321 (1971). AND BOLDEMAN, BERTRAM, 9222 1451 206 AND WALSH, NP A265,337 (1976). 9222 1451 207 7. L. REED, R.W. HOCKENBURY, AND R.C. BLOCK, REPORT 9222 1451 208 COO-3058-39, P.9 (SEPT 1973). 9222 1451 209 8. D.S. MATHER, NUC. PHYS. 66,149 (1965). 9222 1451 210 9. G.N. SMIRENKIN, A.E. 4,188 (1958). 9222 1451 211 10. N.N. FLEROV, A.E. 10,86 (1961). 9222 1451 212 11. A.N. PROTOPOPOV, A.E. 5,71 (1958). 9222 1451 213 12. R.SHER AND C.BECK EPRI NP-1771/81 AND REV. 1/83 9222 1451 214 13. W.P. POENITZ, J.F. WHALEN, P. GUENTHER AND A.B. SMITH, 9222 1451 215 NSE 68, 358 (1978). 9222 1451 216 14. J.W. MEADOWS, NSE 54, 317 (1974). 9222 1451 217 15. W.P. POENITZ, ANL-NDM-36 (1978). 9222 1451 218 16. L. WESTON ET AL., NSE 42, 143 (1970) AND NSE 34, 1 (1968). 9222 1451 219 17. M. CAO ET AL., JNE 24, 111 (1970). 9222 1451 220 18. S. NIZAMUDDIN AND J. BLONS, NSE 54, 116 (1974). 9222 1451 221 19. L. WESTON ET AL., NSE 34, 1 (1968). 9222 1451 222 20. N. PATTENDEN ET AL., NSE 17, 434 (1963). 9222 1451 223 21. D. C. HOFFMAN AND M. M. HOFFMAN, ANN. REV. NUCL. SCI. 24, 9222 1451 224 151 (1974) 9222 1451 225 9222 1451 226 ******************************************************** 9222 1451 227 9222 1451 228 1 451 230 19222 1451 229 3 16 16 09222 1451 230 9222 1 0 231 9222 0 0 232 9.223300+4 2.310430+2 0 0 0 09222 3 16 233 -5.742000+6-5.742000+6 0 0 1 379222 3 16 234 37 2 0 0 0 09222 3 16 235 5.766900+6 0.000000+0 5.800000+6 4.000000-3 6.200000+6 5.400000-29222 3 16 236 6.600000+6 1.900000-1 7.000000+6 2.580000-1 7.200000+6 2.660000-19222 3 16 237 7.400000+6 2.654000-1 7.600000+6 2.602000-1 7.800000+6 2.522000-19222 3 16 238 8.000000+6 2.458000-1 8.200000+6 2.460000-1 8.600000+6 2.590000-19222 3 16 239 9.000000+6 2.840000-1 9.400000+6 3.100000-1 9.800000+6 3.320000-19222 3 16 240 1.020000+7 3.505000-1 1.060000+7 3.680000-1 1.100000+7 3.860000-19222 3 16 241 1.150000+7 4.120000-1 1.200000+7 4.395000-1 1.250000+7 4.720000-19222 3 16 242 1.300000+7 4.990000-1 1.306600+7 5.020000-1 1.350000+7 5.135000-19222 3 16 243 1.400000+7 5.110000-1 1.450000+7 4.910000-1 1.500000+7 4.505000-19222 3 16 244 1.550000+7 3.970000-1 1.600000+7 3.350000-1 1.650000+7 2.740000-19222 3 16 245 1.700000+7 2.180000-1 1.750000+7 1.698000-1 1.800000+7 1.280000-19222 3 16 246 1.850000+7 9.650000-2 1.900000+7 7.100000-2 1.950000+7 5.200000-29222 3 16 247 2.000000+7 3.850000-2 0.000000+0 0.000000+0 0.000000+0 0.000000+09222 3 16 248 9222 3 0 249 9222 0 0 250 0 0 0 251 9.223800+4 2.360060+2 1 1 0 19237 1451 1 0.000000+0 1.000000+0 0 0 0 69237 1451 2 1.000000+0 0.000000+0 0 0 10 69237 1451 3 0.000000+0 0.000000+0 0 0 281 49237 1451 4 92-U -238 ORNL,LANL+ EVAL-NOV89 L.W.WESTON,P.G.YOUNG,W.POENITZ 9237 1451 5 DIST-JUN90 900112 9237 1451 6 ----ENDF/B-VI MATERIAL 9237 9237 1451 7 -----INCIDENT NEUTRON DATA 9237 1451 8 ------ENDF-6 FORMAT 9237 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9237 1451 10 ACTIVATION II 9237 1451 11 ******************************************************************9237 1451 12 9237 1451 13 ******************************************************************9237 1451 14 9237 1451 15 PRINCIPAL EVALUATORS 9237 1451 16 RESOLVED RESONANCE REGION: (10-5 to 10,000 eV) 9237 1451 17 ORNL-G.DeSaussure, D.K.Olsen, Roger Macklin 9237 1451 18 HARWELL- M.C.Moxon, M.G.Sowerby 9237 1451 19 UNRESOLVED RESONANCE REGION: (10 TO 149 keV) 9237 1451 20 F.H.Froehner(KFK) and W.P.Poenitz(ANL) 9237 1451 21 REACTIONS ABOVE 149 keV: 9237 1451 22 MODEL CODE CALCULATIONS: (LANL)-P.G.Young and R.E.MacFarlane 9237 1451 23 FISSION: W.P.Poenitz(ANL) 9237 1451 24 NU-BAR DELAYED AND DELAYED NEUTRON SPECTRA: 9237 1451 25 KAISER AND CARPENTER (Ka78) 9237 1451 26 GAMMA PRODUCTION FILES: R. HOWERTON (LLL) 9237 1451 27 UNCERTAINTY FILES: L.W.WESTON (ORNL) 9237 1451 28 9237 1451 29 *****************************************************************9237 1451 30 9237 1451 31 ENDF/B-VI EVALUATION ABOVE THE UNRESOLVED RESONANCE REGION 9237 1451 32 P.G.Young and R.E.MacFarlane (LANL) 9237 1451 33 9237 1451 34 Above the unresolved resonance region, new evaluations were 9237 1451 35 performed of the neutron total, (n,2n), (,n,3n), (n,4n), (n,f), 9237 1451 36 (n,nf), (n,2nf), (n,3nf), and (n,gamma) cross sections as well as9237 1451 37 prompt nubar. The elastic and inelastic data from ENDF/B-V were 9237 1451 38 carried over for Version VI. 9237 1451 39 To provide the new data, coupled channel optical model calcu- 9237 1451 40 lations were performed with the ECIS code (Ra70) for the lowest 9237 1451 41 3 members of the U238 ground state rotational band. These calcu- 9237 1451 42 lations were used to provide initial (prior) values for a covar- 9237 1451 43 iance analysis of the total cross section and to provide neutron 9237 1451 44 transmission coefficients for nuclear reaction theory 9237 1451 45 calculations with the GNASH (Ar88,Yo77) and COMNUC (Du70) Hauser-9237 1451 46 Feshbach statistical/fission/preequilibrium codes. These theory 9237 1451 47 calculations were used to provide the MF=6 neutron distributions 9237 1451 48 from the (n,2n), (n,3n), and (n,4n) reactions as well as prior 9237 1451 49 values for covariance analyses of the cross sections for those 9237 1451 50 reactions. Additionally, the above analyses plus DWBA calcu- 9237 1451 51 lations were used to check the ENDF/B-V evaluation of elastic 9237 1451 52 and inelastic scattering. While some differences were found, 9237 1451 53 the earlier work was generally found to be reliable, and we 9237 1451 54 decided to carry over the ENDF/B-V data because of the effort 9237 1451 55 taken to match experimental data, both at lower energies and at 9237 1451 56 14 MeV. 9237 1451 57 9237 1451 58 **********MF=1 DESCRIPTIVE AND NUBAR INFORMATION*****************9237 1451 59 9237 1451 60 MT=452 Total Nubar. Sum of MT=455 and 456. 9237 1451 61 MT=455 Delayed Neutron Yields. Kaiser and Carpenter (Ka78) 9237 1451 62 MT=456 Prompt Neutron Yields. Taken from Frehaut (Fr86) 9237 1451 63 9237 1451 64 **********MF=2 RESONANCE REGION**********************************9237 1451 65 RESOLVED RESONANCE REGION: 9237 1451 66 The resolved resonance region determines the thermal cross 9237 1451 67 sections. The thermal capture is that adopted by the Standards9237 1451 68 Committee of CSEWG (2.7081 with an uncer. of 0.0095 barns). 9237 1451 69 Thermal (2200 m/s) constants are: 9237 1451 70 Total Cross Section: 12.068 barns 9237 1451 71 Capture Cross Section: 2.709 9237 1451 72 The resolved resonance region has been extended to 10 keV. 9237 1451 73 The evaluation was from the work of D.K.Olsen(ORNL), Roger 9237 1451 74 Macklin(ORNL), M.C.Moxon(Harwell), and M.G.Sowerby(Harwell) 9237 1451 75 UNRESOLVED RESONANCE REGION: 10 to 149 keV 9237 1451 76 The unresolved resonance region was evaluated by F.H.Froehner 9237 1451 77 (KFK) with his code FITACS which does simultaneous fit to 9237 1451 78 experimental data. The unresolved resonance region is to be 9237 1451 79 used only for self shielding calculations and File 3 should be 9237 1451 80 used to determine the dilute cross sections. 9237 1451 81 9237 1451 82 *********** MF=3 SMOOTH CROSS SECTIONS **************************9237 1451 83 9237 1451 84 MT=1 Neutron Total Cross Section 9237 1451 85 10 TO 149 KEV, EVALUATION BY F.H.FROEHNER (KFK) WHICH IS BASED 9237 1451 86 ON FITACS FIT TO EXPERIMENTAL DATA. 9237 1451 87 0.25 to 20 MeV, based on a covariance analysis of the 9237 1451 88 available exp. data, especially Fo71, Sc74, Po81, Po83, Ha73, 9237 1451 89 Br58, Ca73, Pe60, Wh71, Ba65, Ut66, Sh79, and Li79. Similar 9237 1451 90 data exclusions as used in the covariance analysis by Smith et 9237 1451 91 al.(Sm82) were incorporated but additional data were included. 9237 1451 92 Prior cross section for the analysis was taken from the 9237 1451 93 coupled-channel analysis, described above. The GLUCS code sys. 9237 1451 94 was used for the covariance analysis (He80). 9237 1451 95 MT=16 (n,2n) Cross Section 9237 1451 96 Threshold to 20 MeV, based on a covariance analysis of 9237 1451 97 available data (Ba66,Fr80a,Ko80,Yo78,Ma69,Ma72,Ka79,La73,Ro57, 9237 1451 98 Ph56,Pe61,Ve78,An58,Ry80), similar to MT=1. Prior cross sec- 9237 1451 99 tion obtained from GNASH analysis, with approx.20% uncertainty.9237 1451 100 MT=17 (n,3n) Cross Section 9237 1451 101 Threshold to 20 MeV, based on a covariance analysis 9237 1451 102 similar to MT=16. Exp. data used in the analysis were Fr80b, 9237 1451 103 Wh62,Ro57,Ma69,Al61, and Ve78. 9237 1451 104 MT=18 Fission Cross Section (Total) 9237 1451 105 0.01 TO 0.3 EVALUATED BY L.W.WESTON FROM DI80 AND SL77. 9237 1451 106 0.3 to 20 MeV, taken directly from the simultaneous 9237 1451 107 standards analysis (Ca85,Po89). 9237 1451 108 MT=19 First-Chance Fission (n,f) Cross Section 9237 1451 109 0.3 t0 20 MeV, based on the ratio of first-chance to 9237 1451 110 total fission from ENDF/B-V using the present MT=18 sigma. 9237 1451 111 MT=20 Second-Chance Fission (n,nf) Cross Section 9237 1451 112 5.0 to 20 MeV, based on the ratio of second-chance to 9237 1451 113 total fission from ENDF/B-V using the present MT=18 sigma. 9237 1451 114 MT=21 Third-Chance Fission (n,2nf) Cross Section 9237 1451 115 12 to 20 MeV, based on the ratio of third-chance to 9237 1451 116 total fission from ENDF/B-V using the present MT=18 sigma. 9237 1451 117 MT=37 (n,4n) Cross Section 9237 1451 118 Threshold to 20 MeV, taken directly from the GNASH 9237 1451 119 analysis described above. 9237 1451 120 MT=38 Fourth-Chance Fission (n,3nf) Cross Section 9237 1451 121 18 to 20 MeV, based on the ratio of fourth-chance to 9237 1451 122 total fission from ENDF/B-V using the present MT=18 sigma. 9237 1451 123 MT=102 Radiative Capture Cross Section 9237 1451 124 10 TO 149 KEV, EVALUATION BY F.H.FROEHNER (KFK) WHICH IS BASED 9237 1451 125 ON FITACS FIT TO THE EXPERIMENTAL DATA. 9237 1451 126 0.10 to 20 MeV, taken directly from simultaneous 9237 1451 127 standards analysis (Ca85,Po89). 9237 1451 128 9237 1451 129 ************MF=6 CORRELATED ENERGY-ANGLE DISTRIBUTIONS********** 9237 1451 130 9237 1451 131 MT=16 GNASH Hauser-Feshbach statistical/preequilibrium calc. 9237 1451 132 Neutron distributions only. 9237 1451 133 MT=17 GNASH Hauser-Feshbach statistical/preequilibrium calc. 9237 1451 134 Neutron distributions only. 9237 1451 135 MT=37 GNASH Hauser-Feshbach statistical/preequilibrium calc. 9237 1451 136 Neutron distributions only. 9237 1451 137 9237 1451 138 ******************REFERENCES************************************ 9237 1451 139 9237 1451 140 Al61 K.Allen et al., J.Nuc.En.14,100(1961). 9237 1451 141 An58 G.Antropov et al., A.E. 5,456(1958). 9237 1451 142 Ar88 E.D.Arthur, LA-UR-88-382 (1988). 9237 1451 143 Ba66 D.Barr, (LANL) pers.communication to R.Howerton (1966). 9237 1451 144 Ba65 R.Batchelor et al., Nuc.Phys.65,236(1965). 9237 1451 145 Br58 A.Bratenahl et al., Phys.Rev.110,927(1958). 9237 1451 146 Ca73 J.Cabe et al., CEA-R-4524 (1973). 9237 1451 147 Ca85 A.Carlson et al., Nuc.Data for Basic & Applied Science, 9237 1451 148 Santa Fe, NM (1985) p.1429. 9237 1451 149 DI80 F.C.DIFILLIPPO ET AL., PR/C 21, 1400. 9237 1451 150 Du70 C.L.Dunford, AI-AEC-12931 (1970). 9237 1451 151 Fo71 D.Foster & D.Glasgow, Phys.Rev.C3,576(1971). 9237 1451 152 Fr80a J.Frehaut et al., Nucl.Sci.Eng.74,29(1980). 9237 1451 153 Fr80b J.Frehaut et al., BNL-NCS-512457 (1980) p399. 9237 1451 154 Fr86 J.Frehaut, NEANDC(E) 238/L (1986). 9237 1451 155 Ha73 S.Hayes et al., Nuc.Sci.Eng.50,243(1973). 9237 1451 156 He80 D.Hetrick & C.Y.Fu, ORNL/TM-7341 (1980). 9237 1451 157 Ka78 R.Kaiser & S.Carpenter (ANL-West) personal communication. 9237 1451 158 Ko80 N.Kornilov et al., ZFK-410 (1980)p68. 9237 1451 159 La73 J.Landrum et al., Phys.Rev.C8,1938(1973).]9238 1451 9237 1451 160 Li79 P.Lisowski et al., (LANL WNR measurement)pers.comm.(1979). 9237 1451 161 Ma69 D.Mather, AWRE-O-47 (1969). 9237 1451 162 Ma72 D.Mather et al., AWRE-O-72 (1972). 9237 1451 163 Pe60 J.Peterson et al., Phys.Rev.120, 521(1960). 9237 1451 164 Pe61 J.Perkin, J.Nuc.En.14,69(1961). 9237 1451 165 Ph56 J.Phillips, AERE-NP/R-2033 (1956). 9237 1451 166 Po81 W.Poenitz et al., Nuc.Sci.Eng.78, 333(1981). 9237 1451 167 Po83 W.Poenitz et al., ANL-NDM-80, 1983. 9237 1451 168 Po89 W.Poenitz, (ANL-West) personal communication (1989). 9237 1451 169 Ra70 J.Raynal,IAEA SMR-9/8 (1970). 9237 1451 170 Ro57 L.Rosen et al., LA-2111 (1958). 9237 1451 171 Ry80 T.Ryves, J.Phys.G 6,771(1980). 9237 1451 172 Sc74 R.Schwartz et al., Nuc.Sci.Engr.54,322(1974). 9237 1451 173 Sh78 R.Shamu et al., personal communication, 1978. 9237 1451 174 SL77 R.SLOVACEK ET AL., NSE 62, 455 9237 1451 175 Sm82 A.Smith et al., ANL/NDM-74 (1982). 9237 1451 176 Ut66 C.Uttley et al., Paris Conf. (1966) v1, p165. 9237 1451 177 Ve78 L.Veeser & E.Arthur, Harwell Nuc.Data Conf. (1978)p1054. 9237 1451 178 Wh62 P.White et al., J.Nuc.En.A/B 16,261(1962). 9237 1451 179 Wh71 J.Whalen et al., ANL-7710 (1971) p9. 9237 1451 180 Yo77 P.G.Young & E.D.Arthur, LA-6947 (1977). 9237 1451 181 Yo78 Chou You-Pu, HSJ-77091 (1978). 9237 1451 182 9237 1451 183 *****************************************************************9237 1451 184 DESCRIPTION OF DATA CARRIED OVER FROM ENDF/B-V 9237 1451 185 9237 1451 186 Principal Evaluators -- ENDF/B-V 9237 1451 187 E.M.Pennington (ANL), A.B.Smith (ANL), W.P.Poenitz (ANL) 9237 1451 188 R.Howerton (LLL) - gamma production files 9237 1451 189 contributing evaluators 9237 1451 190 R.Kaiser and S.Carpenter (ANL-west) - nu-bar delayed and delayed 9237 1451 191 neutron spectra 9237 1451 192 MF = 3 smooth cross sections 9237 1451 193 Cross sections above 45 kev were evaluated by A.Smith. 9237 1451 194 more details are provided under each reaction type below. Most 9237 1451 195 of the evaluation above 45 kev is described in ANL/NDM-32. 9237 1451 196 MT = 2 (elastic scattering cross section) 9237 1451 197 Elastic scattering cross sections and angular distributions 9237 1451 198 were evaluated using data referenced in ANL/NDM-32. Coupled- 9237 1451 199 channel optical model calculations assisted in the analysis 9237 1451 200 (ref.9). Below about 1 mev, the elastic cross section was 9237 1451 201 determined for consistency with the total and partial non- 9237 1451 202 elastics. Above 1 mev, the total and elastic cross sections 9237 1451 203 determine the non-elastic. The angular distributions are 9237 1451 204 entirely experimental below 1.8 MeV, and calculated at higher 9237 1451 205 energies. At most energies the ENDF/B-V elastic cross section 9237 1451 206 is smaller than ENDF/B-IV. 9237 1451 207 MT = 4,51-77,91 (total inelastic, inelastic to 27 levels, and 9237 1451 208 continuum inelastic) 9237 1451 209 The evaluation is a correlation of theory (ref.9) and expt. 9237 1451 210 Experimental data referenced in ANL/NDM-32 are considered. 9237 1451 211 Levels at higher energies are composites of actual levels. The 9237 1451 212 total inelastic cross section is generally much higher than in 9237 1451 213 ENDF/B-IV, except near threshold and over a region below 1 MeV.9237 1451 214 The individual levels have tails extending to much higher 9237 1451 215 energies than in ENDF/B-IV, resulting in a much smaller 9237 1451 216 continuum. Thus inelastic scattering at high incident energies 9237 1451 217 leads to higher average final energies in ENDF/B-V than in 9237 1451 218 ENDF/B-IV. This tends to counteract the effect on the flux 9237 1451 219 spectrum of having higher total inelastic in ENDF/B-V than in 9237 1451 220 ENDF/B-IV. In performing the inelastic evaluation, one revision9237 1451 221 was made in the first draft (ref.10) to give improved agreement9237 1451 222 with calculations for ZPR-6-7. However, no changes outside the 9237 1451 223 estimated uncertainties were made. 9237 1451 224 MF = 4 angular distributions 9237 1451 225 MT = 2 (elastic) 9237 1451 226 The elastic angular distributions are expressed as f(l) coeff. 9237 1451 227 in the center of mass system at 31 energies. They were obtained9237 1451 228 as described above under MF=3, MT=2 above 45 kev. Below 45 kev,9237 1451 229 ENDF/B-IV was used. The 20 MeV f(l) were modified in order to 9237 1451 230 avoid negative excursions caused by the restriction to NL=20. 9237 1451 231 MT = 18,19,20,21,38,91 9237 1451 232 Angular distributions were taken as isotropic in lab system. 9237 1451 233 MT = 51-77 (inelastic levels) 9237 1451 234 The angular distributions for the inelastic levels are given as9237 1451 235 probabilities in the C.-of-M. system. They were calculated with9237 1451 236 the model described in ref.9. comparisons with expt. are given 9237 1451 237 in ANL/NDM-32. In ENDF/B-IV all but the four highest pseudo 9237 1451 238 levels were assumed isotropic. 9237 1451 239 MF = 5 secondary energy dist. 9237 1451 240 MT = 18 (total fission) 9237 1451 241 The total fission spectrum is an energy-dependent watt spectrum9237 1451 242 (LF=11) with parameters chosen to give the same average energy 9237 1451 243 as the combination of MT=19,20,21,38. 9237 1451 244 MT = 19 (first chance fission) 9237 1451 245 An energy-dependent Watt spectrum was determined using methods 9237 1451 246 similar to those of ref.15. A Watt spectrum has more neutrons 9237 1451 247 at intermediate energies, and fewer at low and high energies 9237 1451 248 than a Maxwellian of the same average energy. 9237 1451 249 MT = 20,21,38 (2nd,3rd,4th chance fission) 9237 1451 250 A combination of a Watt spectrum and 1,2, or 3 LF=9 laws for 9237 1451 251 MT=20,21,38, respectively, is used. 9237 1451 252 MT = 91 (inelastic continuum) lf=1 by A.Smith 9237 1451 253 MT = 455 (delayed neutron spectra) ref.1. 9237 1451 254 MF = 12 9237 1451 255 MT = 18 (fission) and 102 (n,gamma) multiplicities are given 9237 1451 256 MF = 13 9237 1451 257 MT = 3 (non-elastic) 9237 1451 258 Photon production cross sections are given above inel. thresh. 9237 1451 259 MF = 14 9237 1451 260 MT = 3,18,102 photon angular distributions are isotropic. 9237 1451 261 MF = 15 9237 1451 262 MT = 3,18,102 9237 1451 263 Continuous photon energy spectra are present. Description 9237 1451 264 of the evaluation of MF=12-15 is included in ANL/NDM-32 9237 1451 265 REFERENCES 9237 1451 266 1. R.E.Kaiser and S.G.Carpenter (ANL-west) priv. comm. (Mar.78) 9237 1451 267 **data inserted into file at BNL by R. Kinsey 4/18/78** 9237 1451 268 2. S.A.Cox ANL/NDM-5 (1974) 9237 1451 269 3. C.Besant et al sem. fast pulsed reactors CONF-760111 (1976) 9237 1451 270 4. F.Manero and V.Konshin at. energy review 10 no.4 (1972) 9237 1451 271 5. M.Soleilhac revised data received from NNCSC. 9237 1451 272 6. B.Nurpeisov et al Sov. At. Energy translation 807 (Mar,1976) 9237 1451 273 7. G.deSaussure et al. PNE 3,87 (1979) 9237 1451 274 8. D.Olsen et al Nuc. Sci. Eng. 62,479 (1977) 9237 1451 275 9. P.Guenther,D.Havel,A.Smith ANL-NDM-22 (1976) 9237 1451 276 10. E.Pennington,W.Poenitz,A.Smith TANS 26,591 (1977) 9237 1451 277 11. W.P.Poenitz ANL/NDM-45 (1979) 9237 1451 278 12. W.P.Poenitz and A.B.Smith,ed. ANL-76-90 (1976) 9237 1451 279 13. R.Slovacek et al Nucl. Sci. Eng. 62,455 (1977) 9237 1451 280 14. M.Caner,M.Segev,W.Yiftah Nucl. Sci. Eng. 59,395 (1976) 9237 1451 281 15. E.Kujawski and L.Stewart TANS 24,453 (1976) 9237 1451 282 16. L.W.Weston p.c. to B.A.Magurno Nov.12,1982 9237 1451 283 17. Sher +Beck EPRI NP-1771/81 +rev. 1/83 +pc to Magurno 2/83 9237 1451 284 **************************************************************** 9237 1451 285 1 451 289 19237 1451 286 2 151 2049 19237 1451 287 3 102 32 19237 1451 288 33 102 35 09237 1451 289 9237 1 0 290 9237 0 0 291 9.223800+4 2.360060+2 0 0 1 09237 2151 292 9.223800+4 1.000000+0 0 0 2 09237 2151 293 1.000000-5 1.000000+4 1 3 0 09237 2151 294 0.000000+0 9.428482-1 0 0 2 29237 2151 295 2.360060+2 0.000000+0 0 0 4806 8019237 2151 296 -4.133000+2 5.000000-1 2.033000-1 2.300000-2 0.000000+0 0.000000+09237 2151 297 -3.933000+2 5.000000-1 8.259900-2 2.300000-2 0.000000+0 0.000000+09237 2151 298 -3.733000+2 5.000000-1 8.047500-2 2.300000-2 0.000000+0 0.000000+09237 2151 299 -3.533000+2 5.000000-1 7.828800-2 2.300000-2 0.000000+0 0.000000+09237 2151 300 -3.333000+2 5.000000-1 1.830000-1 2.300000-2 0.000000+0 0.000000+09237 2151 301 -3.133000+2 5.000000-1 7.372700-2 2.300000-2 0.000000+0 0.000000+09237 2151 302 -2.933000+2 5.000000-1 7.133200-2 2.300000-2 0.000000+0 0.000000+09237 2151 303 -2.733000+2 5.000000-1 3.306400-1 2.300000-2 0.000000+0 0.000000+09237 2151 304 -2.533000+2 5.000000-1 6.629200-2 2.300000-2 0.000000+0 0.000000+09237 2151 305 -2.333000+2 5.000000-1 2.443800-1 2.300000-2 0.000000+0 0.000000+09237 2151 306 -2.133000+2 5.000000-1 6.083500-2 2.300000-2 0.000000+0 0.000000+09237 2151 307 -1.933000+2 5.000000-1 1.390000-1 2.300000-2 0.000000+0 0.000000+09237 2151 308 -1.733000+2 5.000000-1 5.260000-2 2.300000-2 0.000000+0 0.000000+09237 2151 309 -1.533000+2 5.000000-1 2.480000-1 2.300000-2 0.000000+0 0.000000+09237 2151 310 -1.333000+2 5.000000-1 2.310000-2 2.300000-2 0.000000+0 0.000000+09237 2151 311 -1.133000+2 5.000000-1 4.160000-2 2.300000-2 0.000000+0 0.000000+09237 2151 312 -9.330000+1 5.000000-1 1.930000-2 2.300000-2 0.000000+0 0.000000+09237 2151 313 -7.330000+1 5.000000-1 1.700000-2 2.300000-2 0.000000+0 0.000000+09237 2151 314 -5.330000+1 5.000000-1 7.300000-3 2.300000-2 0.000000+0 0.000000+09237 2151 315 -3.330000+1 5.000000-1 8.086000-4 2.300000-2 8.203000-7 0.000000+09237 2151 316 6.674000+0 5.000000-1 1.493000-3 2.300000-2 9.990000-9 0.000000+09237 2151 317 2.087100+1 5.000000-1 1.026000-2 2.291000-2 5.420000-8 0.000000+09237 2151 318 3.668200+1 5.000000-1 3.413000-2 2.289000-2 9.770000-9 0.000000+09237 2151 319 6.603200+1 5.000000-1 2.460000-2 2.336000-2 5.265000-8 0.000000+09237 2151 320 8.074900+1 5.000000-1 1.865000-3 2.300000-2 6.049000-8 0.000000+09237 2151 321 1.025600+2 5.000000-1 7.170000-2 2.342000-2 1.286000-8 0.000000+09237 2151 322 1.169020+2 5.000000-1 2.549000-2 2.299000-2 0.000000+0 0.000000+09237 2151 323 1.456600+2 5.000000-1 8.470000-4 2.300000-2 0.000000+0 0.000000+09237 2151 324 1.652900+2 5.000000-1 3.367000-3 2.300000-2 0.000000+0 0.000000+09237 2151 325 1.896700+2 5.000000-1 1.732000-1 2.238000-2 3.573000-8 0.000000+09237 2151 326 2.085100+2 5.000000-1 5.111000-2 2.394000-2 8.347000-8 0.000000+09237 2151 327 2.373800+2 5.000000-1 2.716000-2 2.454000-2 3.542000-8 0.000000+09237 2151 328 2.572160+2 5.000000-1 3.400000-5 2.300000-2 0.000000+0 0.000000+09237 2151 329 2.736600+2 5.000000-1 2.578000-2 2.210000-2 0.000000+0 0.000000+09237 2151 330 2.910000+2 5.000000-1 1.687000-2 2.212000-2 0.000000+0 0.000000+09237 2151 331 3.113200+2 5.000000-1 1.089000-3 2.300000-2 0.000000+0 0.000000+09237 2151 332 3.477900+2 5.000000-1 8.200000-2 2.251000-2 2.320000-7 0.000000+09237 2151 333 3.534500+2 5.000000-1 2.400000-5 2.300000-2 0.000000+0 0.000000+09237 2151 334 3.769300+2 5.000000-1 1.129000-3 2.300000-2 1.400000-7 0.000000+09237 2151 335 3.976200+2 5.000000-1 6.207000-3 2.300000-2 0.000000+0 0.000000+09237 2151 336 4.102400+2 5.000000-1 2.009000-2 2.390000-2 0.000000+0 0.000000+09237 2151 337 4.340700+2 5.000000-1 9.787000-3 2.288000-2 0.000000+0 0.000000+09237 2151 338 4.631700+2 5.000000-1 5.613000-3 2.280000-2 1.346000-6 0.000000+09237 2151 339 4.784300+2 5.000000-1 4.126000-3 2.300000-2 2.290000-7 0.000000+09237 2151 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6.603730+3 1.500000+0 7.207600-4 2.300000-2 0.000000+0 0.000000+09237 2151 1817 6.612960+3 1.500000+0 2.573500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1818 6.622140+3 1.500000+0 1.229400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1819 6.637951+3 5.000000-1 7.979200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1820 6.640860+3 1.500000+0 5.788000-5 2.300000-2 0.000000+0 0.000000+09237 2151 1821 6.660750+3 1.500000+0 1.670000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1822 6.673070+3 1.500000+0 2.556200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1823 6.688000+3 1.500000+0 1.726500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1824 6.700790+3 1.500000+0 1.826000-3 2.300000-2 0.000000+0 0.000000+09237 2151 1825 6.703993+3 5.000000-1 9.886500-5 2.300000-2 0.000000+0 0.000000+09237 2151 1826 6.719370+3 5.000000-1 5.645400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1827 6.721380+3 1.500000+0 2.129400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1828 6.729993+3 1.500000+0 2.814000-4 2.300000-2 0.000000+0 0.000000+09237 2151 1829 6.731960+3 5.000000-1 7.477000-4 2.300000-2 0.000000+0 0.000000+09237 2151 1830 6.741210+3 1.500000+0 9.938100-4 2.300000-2 0.000000+0 0.000000+09237 2151 1831 6.754010+3 5.000000-1 6.885800-3 2.350000-2 0.000000+0 0.000000+09237 2151 1832 6.768180+3 1.500000+0 1.063800-2 2.300000-2 0.000000+0 0.000000+09237 2151 1833 6.775890+3 5.000000-1 4.997400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1834 6.778330+3 1.500000+0 1.680800-4 2.300000-2 0.000000+0 0.000000+09237 2151 1835 6.791360+3 1.500000+0 2.666800-4 2.300000-2 0.000000+0 0.000000+09237 2151 1836 6.795960+3 5.000000-1 4.590400-2 2.350000-2 0.000000+0 0.000000+09237 2151 1837 6.816570+3 5.000000-1 1.065700-2 2.350000-2 0.000000+0 0.000000+09237 2151 1838 6.819980+3 1.500000+0 1.581400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1839 6.834660+3 1.500000+0 1.546300-4 2.300000-2 0.000000+0 0.000000+09237 2151 1840 6.836243+3 5.000000-1 1.167100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1841 6.848350+3 1.500000+0 4.919800-3 2.350000-2 0.000000+0 0.000000+09237 2151 1842 6.869870+3 1.500000+0 1.850000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1843 6.871550+3 5.000000-1 3.382200-2 2.350000-2 0.000000+0 0.000000+09237 2151 1844 6.887760+3 5.000000-1 1.140100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1845 6.901110+3 1.500000+0 2.181300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1846 6.902870+3 5.000000-1 2.691200-2 2.350000-2 0.000000+0 0.000000+09237 2151 1847 6.911140+3 1.500000+0 7.063500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1848 6.915743+3 1.500000+0 8.408900-3 2.350000-2 0.000000+0 0.000000+09237 2151 1849 6.917420+3 5.000000-1 1.532500-2 2.350000-2 0.000000+0 0.000000+09237 2151 1850 6.926650+3 1.500000+0 4.237700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1851 6.933790+3 5.000000-1 1.585900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1852 6.941370+3 1.500000+0 4.211700-3 2.350000-2 0.000000+0 0.000000+09237 2151 1853 6.954020+3 5.000000-1 1.245700-2 2.300000-2 0.000000+0 0.000000+09237 2151 1854 6.975931+3 1.500000+0 3.231700-4 2.300000-2 0.000000+0 0.000000+09237 2151 1855 6.989640+3 1.500000+0 1.643800-3 2.300000-2 0.000000+0 0.000000+09237 2151 1856 6.994750+3 1.500000+0 3.181700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1857 7.003870+3 5.000000-1 5.170900-4 2.300000-2 0.000000+0 0.000000+09237 2151 1858 7.015250+3 1.500000+0 3.175200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1859 7.015681+3 1.500000+0 1.126300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1860 7.035940+3 5.000000-1 1.805600-2 2.300000-2 0.000000+0 0.000000+09237 2151 1861 7.048750+3 1.500000+0 3.473400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1862 7.054610+3 1.500000+0 1.115900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1863 7.076420+3 1.500000+0 4.186300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1864 7.088570+3 1.500000+0 1.544600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1865 7.096410+3 5.000000-1 7.584100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1866 7.108610+3 1.500000+0 1.101300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1867 7.119980+3 5.000000-1 5.510600-4 2.300000-2 0.000000+0 0.000000+09237 2151 1868 7.127860+3 5.000000-1 3.781100-2 2.350000-2 0.000000+0 0.000000+09237 2151 1869 7.134000+3 1.500000+0 3.846900-4 2.300000-2 0.000000+0 0.000000+09237 2151 1870 7.169270+3 5.000000-1 2.222700-2 2.350000-2 0.000000+0 0.000000+09237 2151 1871 7.174400+3 5.000000-1 1.501400-2 2.300000-2 0.000000+0 0.000000+09237 2151 1872 7.183702+3 1.500000+0 1.738000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1873 7.199020+3 1.500000+0 1.791400-2 2.350000-2 0.000000+0 0.000000+09237 2151 1874 7.212550+3 1.500000+0 6.207400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1875 7.215230+3 5.000000-1 1.893500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1876 7.226181+3 1.500000+0 1.576900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1877 7.234010+3 1.500000+0 3.590500-4 2.300000-2 0.000000+0 0.000000+09237 2151 1878 7.242030+3 5.000000-1 9.319300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1879 7.262223+3 1.500000+0 2.584800-3 2.300000-2 0.000000+0 0.000000+09237 2151 1880 7.272480+3 1.500000+0 5.561300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1881 7.281300+3 5.000000-1 1.854700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1882 7.291270+3 5.000000-1 4.628100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1883 7.297620+3 1.500000+0 5.442600-4 2.300000-2 0.000000+0 0.000000+09237 2151 1884 7.303980+3 1.500000+0 2.571700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1885 7.321050+3 1.500000+0 2.770300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1886 7.332810+3 1.500000+0 3.072700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1887 7.340420+3 1.500000+0 9.359800-3 2.350000-2 0.000000+0 0.000000+09237 2151 1888 7.362760+3 1.500000+0 1.537500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1889 7.365710+3 5.000000-1 1.748300-2 2.350000-2 0.000000+0 0.000000+09237 2151 1890 7.368110+3 5.000000-1 7.343500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1891 7.382590+3 1.500000+0 5.217000-4 2.300000-2 0.000000+0 0.000000+09237 2151 1892 7.386980+3 1.500000+0 1.328000-3 2.300000-2 0.000000+0 0.000000+09237 2151 1893 7.403650+3 1.500000+0 7.175100-4 2.300000-2 0.000000+0 0.000000+09237 2151 1894 7.414870+3 5.000000-1 6.379900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1895 7.416432+3 1.500000+0 2.028400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1896 7.422250+3 1.500000+0 2.026600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1897 7.430411+3 1.500000+0 3.270000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1898 7.438530+3 1.500000+0 2.520000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1899 7.453090+3 1.500000+0 8.180700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1900 7.464110+3 5.000000-1 1.419900-4 2.300000-2 0.000000+0 0.000000+09237 2151 1901 7.469050+3 1.500000+0 3.639100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1902 7.489480+3 1.500000+0 7.946300-4 2.300000-2 0.000000+0 0.000000+09237 2151 1903 7.505380+3 5.000000-1 3.488900-4 2.300000-2 0.000000+0 0.000000+09237 2151 1904 7.512250+3 1.500000+0 8.595600-5 2.300000-2 0.000000+0 0.000000+09237 2151 1905 7.515100+3 1.500000+0 8.521500-5 2.300000-2 0.000000+0 0.000000+09237 2151 1906 7.523744+3 5.000000-1 2.625600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1907 7.530070+3 1.500000+0 3.210600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1908 7.534830+3 5.000000-1 1.629500-2 2.350000-2 0.000000+0 0.000000+09237 2151 1909 7.548661+3 1.500000+0 9.792600-4 2.300000-2 0.000000+0 0.000000+09237 2151 1910 7.552030+3 5.000000-1 2.356200-2 2.350000-2 0.000000+0 0.000000+09237 2151 1911 7.583661+3 1.500000+0 4.674700-4 2.300000-2 0.000000+0 0.000000+09237 2151 1912 7.601580+3 5.000000-1 3.331800-3 2.300000-2 0.000000+0 0.000000+09237 2151 1913 7.603280+3 1.500000+0 9.950900-3 2.350000-2 0.000000+0 0.000000+09237 2151 1914 7.631780+3 1.500000+0 3.988500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1915 7.639770+3 1.500000+0 4.494900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1916 7.660960+3 5.000000-1 3.320300-2 2.350000-2 0.000000+0 0.000000+09237 2151 1917 7.677474+3 1.500000+0 1.934100-2 2.350000-2 0.000000+0 0.000000+09237 2151 1918 7.685703+3 1.500000+0 1.945100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1919 7.695030+3 1.500000+0 4.369400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1920 7.706350+3 5.000000-1 2.506700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1921 7.707830+3 1.500000+0 3.960600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1922 7.713750+3 1.500000+0 4.317700-4 2.300000-2 0.000000+0 0.000000+09237 2151 1923 7.722641+3 1.500000+0 4.972300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1924 7.724610+3 5.000000-1 1.149300-2 2.350000-2 0.000000+0 0.000000+09237 2151 1925 7.739974+3 5.000000-1 1.579600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1926 7.745920+3 5.000000-1 1.061100-2 2.300000-2 0.000000+0 0.000000+09237 2151 1927 7.756860+3 5.000000-1 2.042900-2 2.350000-2 0.000000+0 0.000000+09237 2151 1928 7.769810+3 1.500000+0 1.009500-2 2.300000-2 0.000000+0 0.000000+09237 2151 1929 7.773840+3 5.000000-1 2.947200-2 2.350000-2 0.000000+0 0.000000+09237 2151 1930 7.789230+3 1.500000+0 4.108400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1931 7.793310+3 1.500000+0 9.089300-4 2.300000-2 0.000000+0 0.000000+09237 2151 1932 7.795320+3 5.000000-1 3.350400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1933 7.819820+3 1.500000+0 4.425700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1934 7.836590+3 5.000000-1 1.699500-4 2.300000-2 0.000000+0 0.000000+09237 2151 1935 7.851260+3 5.000000-1 6.115000-4 2.300000-2 0.000000+0 0.000000+09237 2151 1936 7.863953+3 1.500000+0 1.414200-4 2.300000-2 0.000000+0 0.000000+09237 2151 1937 7.865110+3 1.500000+0 2.893200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1938 7.876662+3 5.000000-1 1.495600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1939 7.880995+3 1.500000+0 2.043700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1940 7.882370+3 5.000000-1 5.083100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1941 7.884330+3 1.500000+0 8.324400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1942 7.892370+3 1.500000+0 3.819700-4 2.300000-2 0.000000+0 0.000000+09237 2151 1943 7.902170+3 1.500000+0 1.776400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1944 7.904170+3 5.000000-1 2.612100-2 2.350000-2 0.000000+0 0.000000+09237 2151 1945 7.910891+3 1.500000+0 1.373500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1946 7.916530+3 5.000000-1 1.041300-2 2.300000-2 0.000000+0 0.000000+09237 2151 1947 7.925770+3 1.500000+0 3.879300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1948 7.933480+3 1.500000+0 2.869400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1949 7.934954+3 5.000000-1 3.602000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1950 7.941210+3 5.000000-1 2.351300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1951 7.943270+3 1.500000+0 5.363600-3 2.350000-2 0.000000+0 0.000000+09237 2151 1952 7.956183+3 1.500000+0 8.910000-4 2.300000-2 0.000000+0 0.000000+09237 2151 1953 7.958250+3 1.500000+0 2.860800-3 2.300000-2 0.000000+0 0.000000+09237 2151 1954 7.965530+3 1.500000+0 4.874300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1955 7.984170+3 5.000000-1 6.781000-3 2.300000-2 0.000000+0 0.000000+09237 2151 1956 7.986933+3 1.500000+0 2.209800-2 2.350000-2 0.000000+0 0.000000+09237 2151 1957 7.990412+3 1.500000+0 3.542600-4 2.300000-2 0.000000+0 0.000000+09237 2151 1958 8.001860+3 5.000000-1 1.933500-2 2.350000-2 0.000000+0 0.000000+09237 2151 1959 8.018570+3 1.500000+0 1.839000-3 2.300000-2 0.000000+0 0.000000+09237 2151 1960 8.028704+3 1.500000+0 8.395900-4 2.300000-2 0.000000+0 0.000000+09237 2151 1961 8.066380+3 5.000000-1 6.704300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1962 8.077475+3 1.500000+0 1.321900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1963 8.086204+3 5.000000-1 3.142100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1964 8.098662+3 1.500000+0 1.315300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1965 8.102912+3 1.500000+0 1.115200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1966 8.109820+3 5.000000-1 1.172900-3 2.300000-2 0.000000+0 0.000000+09237 2151 1967 8.114080+3 1.500000+0 7.149100-4 2.300000-2 0.000000+0 0.000000+09237 2151 1968 8.122630+3 1.500000+0 2.303500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1969 8.132210+3 1.500000+0 8.085900-4 2.300000-2 0.000000+0 0.000000+09237 2151 1970 8.151210+3 5.000000-1 9.260700-3 2.300000-2 0.000000+0 0.000000+09237 2151 1971 8.152850+3 1.500000+0 1.552800-2 2.350000-2 0.000000+0 0.000000+09237 2151 1972 8.168662+3 1.500000+0 3.286200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1973 8.171621+3 5.000000-1 7.484100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1974 8.185892+3 1.500000+0 2.381500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1975 8.191290+3 5.000000-1 1.957300-2 2.350000-2 0.000000+0 0.000000+09237 2151 1976 8.214162+3 5.000000-1 4.017000-4 2.300000-2 0.000000+0 0.000000+09237 2151 1977 8.233300+3 5.000000-1 4.793600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1978 8.267970+3 1.500000+0 4.749200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1979 8.273930+3 5.000000-1 7.942700-3 2.350000-2 0.000000+0 0.000000+09237 2151 1980 8.295413+3 1.500000+0 3.737600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1981 8.303826+3 5.000000-1 6.480600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1982 8.339060+3 1.500000+0 7.457100-4 2.300000-2 0.000000+0 0.000000+09237 2151 1983 8.343220+3 1.500000+0 5.218100-3 2.300000-2 0.000000+0 0.000000+09237 2151 1984 8.352954+3 5.000000-1 4.693500-3 2.300000-2 0.000000+0 0.000000+09237 2151 1985 8.372163+3 5.000000-1 1.497000-2 2.350000-2 0.000000+0 0.000000+09237 2151 1986 8.379140+3 1.500000+0 1.226300-3 2.300000-2 0.000000+0 0.000000+09237 2151 1987 8.383050+3 5.000000-1 1.580400-2 2.350000-2 0.000000+0 0.000000+09237 2151 1988 8.384736+3 5.000000-1 1.580100-2 2.350000-2 0.000000+0 0.000000+09237 2151 1989 8.394250+3 1.500000+0 1.221400-3 2.300000-2 0.000000+0 0.000000+09237 2151 1990 8.416140+3 1.500000+0 6.689200-3 2.300000-2 0.000000+0 0.000000+09237 2151 1991 8.418670+3 5.000000-1 1.743600-2 2.350000-2 0.000000+0 0.000000+09237 2151 1992 8.439246+3 1.500000+0 1.260100-4 2.300000-2 0.000000+0 0.000000+09237 2151 1993 8.459180+3 5.000000-1 6.928400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1994 8.489156+3 1.500000+0 2.091400-4 2.300000-2 0.000000+0 0.000000+09237 2151 1995 8.493406+3 5.000000-1 2.122100-2 2.350000-2 0.000000+0 0.000000+09237 2151 1996 8.494286+3 1.500000+0 1.990500-2 2.350000-2 0.000000+0 0.000000+09237 2151 1997 8.500000+3 5.000000-1 3.924300-2 2.300000-2 0.000000+0 0.000000+09237 2151 1998 8.509130+3 1.500000+0 5.643600-3 2.300000-2 0.000000+0 0.000000+09237 2151 1999 8.511371+3 5.000000-1 1.424000-2 2.350000-2 0.000000+0 0.000000+09237 2151 2000 8.525670+3 5.000000-1 6.045700-3 2.350000-2 0.000000+0 0.000000+09237 2151 2001 8.529000+3 1.500000+0 5.634400-3 2.300000-2 0.000000+0 0.000000+09237 2151 2002 8.537500+3 5.000000-1 4.537600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2003 8.553906+3 1.500000+0 3.635600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2004 8.556496+3 5.000000-1 3.659900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2005 8.558220+3 1.500000+0 1.659600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2006 8.563705+3 5.000000-1 6.232500-3 2.300000-2 0.000000+0 0.000000+09237 2151 2007 8.577576+3 5.000000-1 1.917300-3 2.300000-2 0.000000+0 0.000000+09237 2151 2008 8.580180+3 1.500000+0 3.625100-3 2.300000-2 0.000000+0 0.000000+09237 2151 2009 8.582790+3 5.000000-1 1.883800-2 2.300000-2 0.000000+0 0.000000+09237 2151 2010 8.591486+3 1.500000+0 1.648300-3 2.300000-2 0.000000+0 0.000000+09237 2151 2011 8.603390+3 1.500000+0 1.749400-4 2.300000-2 0.000000+0 0.000000+09237 2151 2012 8.608000+3 5.000000-1 1.500800-2 2.350000-2 0.000000+0 0.000000+09237 2151 2013 8.612540+3 1.500000+0 2.817500-2 2.350000-2 0.000000+0 0.000000+09237 2151 2014 8.621286+3 1.500000+0 1.638100-3 2.300000-2 0.000000+0 0.000000+09237 2151 2015 8.639246+3 5.000000-1 1.454000-2 2.350000-2 0.000000+0 0.000000+09237 2151 2016 8.643920+3 1.500000+0 4.588900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2017 8.655640+3 1.500000+0 1.870000-2 2.350000-2 0.000000+0 0.000000+09237 2151 2018 8.665040+3 5.000000-1 9.954600-4 2.300000-2 0.000000+0 0.000000+09237 2151 2019 8.697446+3 1.500000+0 4.565600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2020 8.708826+3 5.000000-1 2.511500-3 2.300000-2 0.000000+0 0.000000+09237 2151 2021 8.716970+3 5.000000-1 1.857000-2 2.300000-2 0.000000+0 0.000000+09237 2151 2022 8.721122+3 1.500000+0 6.263300-4 2.300000-2 0.000000+0 0.000000+09237 2151 2023 8.726460+3 5.000000-1 5.259700-4 2.300000-2 0.000000+0 0.000000+09237 2151 2024 8.728246+3 1.500000+0 1.601200-3 2.300000-2 0.000000+0 0.000000+09237 2151 2025 8.743116+3 1.500000+0 1.596100-3 2.300000-2 0.000000+0 0.000000+09237 2151 2026 8.758156+3 1.500000+0 6.145400-4 2.300000-2 0.000000+0 0.000000+09237 2151 2027 8.761000+3 5.000000-1 6.042000-3 2.300000-2 0.000000+0 0.000000+09237 2151 2028 8.763326+3 1.500000+0 8.175400-3 2.350000-2 0.000000+0 0.000000+09237 2151 2029 8.768170+3 1.500000+0 1.587400-3 2.300000-2 0.000000+0 0.000000+09237 2151 2030 8.783746+3 1.500000+0 2.531100-3 2.350000-2 0.000000+0 0.000000+09237 2151 2031 8.790946+3 1.500000+0 2.166400-3 2.300000-2 0.000000+0 0.000000+09237 2151 2032 8.792955+3 5.000000-1 1.617600-2 2.350000-2 0.000000+0 0.000000+09237 2151 2033 8.798455+3 1.500000+0 6.498700-3 2.300000-2 0.000000+0 0.000000+09237 2151 2034 8.810930+3 1.500000+0 1.572500-3 2.300000-2 0.000000+0 0.000000+09237 2151 2035 8.823156+3 1.500000+0 1.178000-3 2.300000-2 0.000000+0 0.000000+09237 2151 2036 8.841122+3 5.000000-1 7.641500-3 2.300000-2 0.000000+0 0.000000+09237 2151 2037 8.842800+3 1.500000+0 4.502000-3 2.300000-2 0.000000+0 0.000000+09237 2151 2038 8.853116+3 1.500000+0 7.461900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2039 8.862520+3 1.500000+0 5.811000-4 2.300000-2 0.000000+0 0.000000+09237 2151 2040 8.865560+3 5.000000-1 5.044800-3 2.350000-2 0.000000+0 0.000000+09237 2151 2041 8.876826+3 5.000000-1 1.707200-3 2.300000-2 0.000000+0 0.000000+09237 2151 2042 8.879455+3 1.500000+0 8.406800-3 2.350000-2 0.000000+0 0.000000+09237 2151 2043 8.884746+3 1.500000+0 1.059900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2044 8.898180+3 1.500000+0 5.429700-3 2.350000-2 0.000000+0 0.000000+09237 2151 2045 8.901236+3 1.500000+0 4.476100-3 2.300000-2 0.000000+0 0.000000+09237 2151 2046 8.909196+3 1.500000+0 3.491700-3 2.300000-2 0.000000+0 0.000000+09237 2151 2047 8.912560+3 5.000000-1 5.839500-3 2.350000-2 0.000000+0 0.000000+09237 2151 2048 8.919750+3 5.000000-1 9.214100-3 2.300000-2 0.000000+0 0.000000+09237 2151 2049 8.928210+3 1.500000+0 1.531500-3 2.300000-2 0.000000+0 0.000000+09237 2151 2050 8.943590+3 1.500000+0 2.793200-3 2.300000-2 0.000000+0 0.000000+09237 2151 2051 8.949890+3 1.500000+0 8.399000-3 2.300000-2 0.000000+0 0.000000+09237 2151 2052 8.957786+3 5.000000-1 2.204100-2 2.300000-2 0.000000+0 0.000000+09237 2151 2053 8.959550+3 1.500000+0 2.113900-2 2.350000-2 0.000000+0 0.000000+09237 2151 2054 8.973246+3 1.500000+0 1.515600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2055 8.991220+3 1.500000+0 1.023900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2056 8.993706+3 1.500000+0 5.415900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2057 9.002414+3 1.500000+0 5.902900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2058 9.013236+3 5.000000-1 4.285600-2 2.350000-2 0.000000+0 0.000000+09237 2151 2059 9.014866+3 1.500000+0 6.388300-3 2.300000-2 0.000000+0 0.000000+09237 2151 2060 9.022786+3 1.500000+0 3.416200-2 2.350000-2 0.000000+0 0.000000+09237 2151 2061 9.024220+3 5.000000-1 1.112900-2 2.300000-2 0.000000+0 0.000000+09237 2151 2062 9.033600+3 1.500000+0 5.396700-3 2.300000-2 0.000000+0 0.000000+09237 2151 2063 9.055040+3 5.000000-1 4.092300-3 2.300000-2 0.000000+0 0.000000+09237 2151 2064 9.060696+3 1.500000+0 1.130600-2 2.300000-2 0.000000+0 0.000000+09237 2151 2065 9.071550+3 5.000000-1 3.671400-2 2.350000-2 0.000000+0 0.000000+09237 2151 2066 9.073446+3 1.500000+0 8.292100-3 2.350000-2 0.000000+0 0.000000+09237 2151 2067 9.076590+3 1.500000+0 2.449300-3 2.300000-2 0.000000+0 0.000000+09237 2151 2068 9.079496+3 5.000000-1 3.595700-2 2.350000-2 0.000000+0 0.000000+09237 2151 2069 9.088250+3 1.500000+0 2.444800-3 2.300000-2 0.000000+0 0.000000+09237 2151 2070 9.103420+3 1.500000+0 1.469300-3 2.300000-2 0.000000+0 0.000000+09237 2151 2071 9.105456+3 5.000000-1 1.198400-2 2.300000-2 0.000000+0 0.000000+09237 2151 2072 9.111786+3 1.500000+0 2.047600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2073 9.123831+3 1.500000+0 3.402600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2074 9.138956+3 5.000000-1 2.355600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2075 9.151050+3 1.500000+0 3.877300-2 2.350000-2 0.000000+0 0.000000+09237 2151 2076 9.152970+3 5.000000-1 1.765000-2 2.350000-2 0.000000+0 0.000000+09237 2151 2077 9.161906+3 1.500000+0 1.738500-3 2.300000-2 0.000000+0 0.000000+09237 2151 2078 9.172770+3 1.500000+0 9.251400-3 2.300000-2 0.000000+0 0.000000+09237 2151 2079 9.183020+3 5.000000-1 1.763400-2 2.300000-2 0.000000+0 0.000000+09237 2151 2080 9.186736+3 1.500000+0 1.815000-2 2.350000-2 0.000000+0 0.000000+09237 2151 2081 9.193920+3 1.500000+0 1.920000-3 2.300000-2 0.000000+0 0.000000+09237 2151 2082 9.204206+3 5.000000-1 1.473200-3 2.300000-2 0.000000+0 0.000000+09237 2151 2083 9.207560+3 1.500000+0 1.914900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2084 9.213210+3 1.500000+0 4.665200-4 2.300000-2 0.000000+0 0.000000+09237 2151 2085 9.228050+3 1.500000+0 4.615900-4 2.300000-2 0.000000+0 0.000000+09237 2151 2086 9.238390+3 1.500000+0 2.870200-3 2.300000-2 0.000000+0 0.000000+09237 2151 2087 9.244866+3 5.000000-1 1.443800-3 2.300000-2 0.000000+0 0.000000+09237 2151 2088 9.246390+3 1.500000+0 7.552400-3 2.350000-2 0.000000+0 0.000000+09237 2151 2089 9.250696+3 1.500000+0 1.031100-3 2.300000-2 0.000000+0 0.000000+09237 2151 2090 9.283831+3 1.500000+0 4.304200-3 2.300000-2 0.000000+0 0.000000+09237 2151 2091 9.291790+3 5.000000-1 7.144700-3 2.300000-2 0.000000+0 0.000000+09237 2151 2092 9.304060+3 1.500000+0 4.294900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2093 9.311390+3 1.500000+0 4.291600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2094 9.325020+3 1.500000+0 9.089600-4 2.300000-2 0.000000+0 0.000000+09237 2151 2095 9.327170+3 5.000000-1 1.403100-2 2.350000-2 1.120000-4 0.000000+09237 2151 2096 9.341430+3 1.500000+0 4.237700-4 2.300000-2 0.000000+0 0.000000+09237 2151 2097 9.357576+3 1.500000+0 1.377600-3 2.300000-2 0.000000+0 0.000000+09237 2151 2098 9.365290+3 1.500000+0 4.266900-3 2.300000-2 0.000000+0 0.000000+09237 2151 2099 9.375500+3 1.500000+0 8.583600-4 2.350000-2 0.000000+0 0.000000+09237 2151 2100 9.379036+3 5.000000-1 5.433700-3 2.300000-2 0.000000+0 0.000000+09237 2151 2101 9.403560+3 1.500000+0 2.802600-3 2.300000-2 0.000000+0 0.000000+09237 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0.000000+09237 2151 2305 5.000000+4 1.068700+1 7.183650-2 1.316960-3 2.323690-2 0.000000+09237 2151 2306 5.500000+4 1.056900+1 1.000490-1 1.301680-3 2.329150-2 0.000000+09237 2151 2307 6.000000+4 1.045210+1 1.205790-1 1.286570-3 2.334590-2 0.000000+09237 2151 2308 7.000000+4 1.022260+1 1.509830-1 1.256970-3 2.345590-2 0.000000+09237 2151 2309 8.000000+4 9.998350+0 1.736300-1 1.228140-3 2.356620-2 0.000000+09237 2151 2310 9.000000+4 9.779200+0 1.916700-1 1.200040-3 2.367730-2 0.000000+09237 2151 2311 1.000000+5 9.565060+0 2.065770-1 1.172670-3 2.378880-2 0.000000+09237 2151 2312 1.200000+5 9.151280+0 2.300500-1 1.120040-3 2.401360-2 0.000000+09237 2151 2313 1.400000+5 8.756100+0 2.478480-1 1.070090-3 2.424070-2 0.000000+09237 2151 2314 1.490290+5 8.583590+0 2.545650-1 1.048390-3 2.434410-2 0.000000+09237 2151 2315 2.500000+0 0.000000+0 5 0 144 239237 2151 2316 0.000000+0 0.000000+0 2.000000+0 1.000000+0 0.000000+0 0.000000+09237 2151 2317 1.000000+4 8.299250+0 0.000000+0 1.027740-3 2.280600-2 0.000000+09237 2151 2318 1.200000+4 8.262180+0 0.000000+0 1.022880-3 2.282740-2 0.000000+09237 2151 2319 1.400000+4 8.225280+0 0.000000+0 1.018050-3 2.284870-2 0.000000+09237 2151 2320 1.600000+4 8.188530+0 0.000000+0 1.013240-3 2.287000-2 0.000000+09237 2151 2321 1.800000+4 8.151940+0 0.000000+0 1.008450-3 2.289140-2 0.000000+09237 2151 2322 2.000000+4 8.115530+0 0.000000+0 1.003690-3 2.291280-2 0.000000+09237 2151 2323 2.300000+4 8.061240+0 0.000000+0 9.966010-4 2.294500-2 0.000000+09237 2151 2324 2.600000+4 8.007320+0 0.000000+0 9.895640-4 2.297720-2 0.000000+09237 2151 2325 3.000000+4 7.936130+0 0.000000+0 9.802820-4 2.302050-2 0.000000+09237 2151 2326 3.500000+4 7.847890+0 0.000000+0 9.687930-4 2.307440-2 0.000000+09237 2151 2327 4.000000+4 7.760740+0 0.000000+0 9.574650-4 2.312850-2 0.000000+09237 2151 2328 4.500000+4 7.674530+0 0.000000+0 9.462730-4 2.318260-2 0.000000+09237 2151 2329 4.509020+4 7.672980+0 0.000000+0 9.460720-4 2.318350-2 0.000000+09237 2151 2330 5.000000+4 7.589370+0 5.101460-2 9.352360-4 2.323690-2 0.000000+09237 2151 2331 5.500000+4 7.505260+0 7.104670-2 9.243480-4 2.329150-2 0.000000+09237 2151 2332 6.000000+4 7.421930+0 8.562190-2 9.135810-4 2.334590-2 0.000000+09237 2151 2333 7.000000+4 7.258440+0 1.072040-1 8.924990-4 2.345590-2 0.000000+09237 2151 2334 8.000000+4 7.098690+0 1.232750-1 8.719600-4 2.356620-2 0.000000+09237 2151 2335 9.000000+4 6.942590+0 1.360730-1 8.519530-4 2.367730-2 0.000000+09237 2151 2336 1.000000+5 6.790070+0 1.466460-1 8.324610-4 2.378880-2 0.000000+09237 2151 2337 1.200000+5 6.495360+0 1.632840-1 7.949790-4 2.401360-2 0.000000+09237 2151 2338 1.400000+5 6.213960+0 1.758910-1 7.594130-4 2.424070-2 0.000000+09237 2151 2339 1.490290+5 6.091120+0 1.806460-1 7.439600-4 2.434410-2 0.000000+09237 2151 2340 9237 2 0 2341 9237 0 0 2342 9.223800+4 2.360058+2 0 0 0 09237 3102 2343 4.804400+6 4.804400+6 0 0 1 859237 3102 2344 85 2 0 0 0 09237 3102 2345 1.000000-5 0.000000+0 4.000000+3 0.000000+0 1.000000+4 0.000000+09237 3102 2346 1.000000+4 7.195620-1 1.200000+4 6.673840-1 1.400000+4 6.251870-19237 3102 2347 1.600000+4 5.899420-1 1.800000+4 5.598540-1 2.000000+4 5.337830-19237 3102 2348 2.300000+4 5.005230-1 2.600000+4 4.727250-1 3.000000+4 4.420910-19237 3102 2349 3.500000+4 4.115250-1 4.000000+4 3.872870-1 4.500000+4 3.677600-19237 3102 2350 4.509020+4 3.674430-1 5.000000+4 3.243370-1 5.500000+4 2.937340-19237 3102 2351 6.000000+4 2.690910-1 7.000000+4 2.330560-1 8.000000+4 2.084250-19237 3102 2352 9.000000+4 1.907220-1 1.000000+5 1.774880-1 1.200000+5 1.592620-19237 3102 2353 1.400000+5 1.475890-1 1.490290+5 1.436790-1 1.600000+5 1.393950-19237 3102 2354 1.700000+5 1.349000-1 1.800000+5 1.319000-1 1.900000+5 1.285000-19237 3102 2355 2.000000+5 1.274000-1 2.100000+5 1.244000-1 2.200000+5 1.226000-19237 3102 2356 2.300000+5 1.210000-1 2.350000+5 1.201000-1 2.400000+5 1.194000-19237 3102 2357 2.450000+5 1.192000-1 2.500000+5 1.184000-1 2.600000+5 1.173000-19237 3102 2358 2.700000+5 1.162000-1 2.800000+5 1.158000-1 3.000000+5 1.150000-19237 3102 2359 3.250000+5 1.140000-1 3.500000+5 1.138000-1 3.750000+5 1.128000-19237 3102 2360 4.000000+5 1.119000-1 4.250000+5 1.112000-1 4.500000+5 1.106000-19237 3102 2361 4.750000+5 1.098000-1 5.000000+5 1.093000-1 5.200000+5 1.095000-19237 3102 2362 5.400000+5 1.101000-1 5.700000+5 1.102000-1 6.000000+5 1.113000-19237 3102 2363 6.500000+5 1.160000-1 7.000000+5 1.189000-1 7.500000+5 1.192000-19237 3102 2364 8.000000+5 1.205000-1 8.500000+5 1.217000-1 9.000000+5 1.228000-19237 3102 2365 9.400000+5 1.248000-1 9.600000+5 1.260000-1 1.000000+6 1.251000-19237 3102 2366 1.100000+6 1.143000-1 1.250000+6 9.270000-2 1.400000+6 7.820000-29237 3102 2367 1.600000+6 6.400000-2 1.800000+6 5.600000-2 2.000000+6 4.610000-29237 3102 2368 2.200000+6 3.762000-2 2.500000+6 2.800000-2 3.000000+6 1.900000-29237 3102 2369 3.500000+6 1.400000-2 4.000000+6 1.000000-2 5.000000+6 6.000000-39237 3102 2370 6.000000+6 3.400000-3 7.000000+6 2.000000-3 8.000000+6 1.300000-39237 3102 2371 9.000000+6 1.000000-3 1.000000+7 1.100000-3 1.200000+7 2.000000-39237 3102 2372 1.400000+7 1.000000-3 1.600000+7 4.000000-4 1.800000+7 2.000000-49237 3102 2373 2.000000+7 1.000000-4 0.000000+0 0.000000+0 0.000000+0 0.000000+09237 3102 2374 9237 3 0 2375 9237 0 0 2376 9.223800+4 2.360060+2 0 0 0 2923733102 2377 0.000000+0 0.000000+0 0 102 1 6923733102 2378 0.000000+0 0.000000+0 0 1 0 0923733102 2379 4.000000+3 2.000000+4 525 107 4 2923733102 2380 4.000000+3 1.000000+0 2.000000+4 0.000000+0 0.000000+0 0.000000+0923733102 2381 0.000000+0 0.000000+0 0 1 6 3923733102 2382 1.000000-5 0.000000+0 4.000000+3 1.600000-3 2.000000+7 0.000000+0923733102 2383 0.000000+0 0.000000+0 0 1 8 4923733102 2384 1.000000-5 0.000000+0 1.000000+0 4.000000-4 1.000000+6 0.000000+0923733102 2385 2.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0923733102 2386 0.000000+0 0.000000+0 0 1 6 3923733102 2387 1.000000-5 0.000000+0 1.000000+6 8.100000-3 2.000000+7 0.000000+0923733102 2388 0.000000+0 0.000000+0 0 1 6 3923733102 2389 1.000000-5 0.000000+0 5.000000+6 7.840000-2 2.000000+7 0.000000+0923733102 2390 0.000000+0 0.000000+0 0 1 36 18923733102 2391 1.000000-5 5.490000-5 1.000000+0 0.000000+0 4.000000+3 4.760000-3923733102 2392 7.000000+3 1.940000-3 1.000000+4 3.140000-3 2.000000+4 2.700000-3923733102 2393 3.000000+4 1.000000-4 4.000000+4 1.200000-3 6.000000+4 2.700000-3923733102 2394 8.000000+4 3.800000-3 1.000000+5 1.400000-3 2.000000+5 1.000000-4923733102 2395 4.000000+5 1.000000-4 6.000000+5 6.800000-4 8.000000+5 3.190000-3923733102 2396 1.000000+6 4.000000-4 2.000000+6 1.800000-3 2.000000+7 0.000000+0923733102 2397 0.000000+0 0.000000+0 0 2 52 26923733102 2398 1.000000-5 0.000000+0 1.000000+0 4.110000-2 1.458000+0 4.140000-2923733102 2399 1.595000+0 4.150000-2 1.726000+0 4.160000-2 1.855000+0 4.220000-2923733102 2400 2.382000+0 4.300000-2 3.059000+0 4.480000-2 3.928000+0 4.830000-2923733102 2401 5.044000+0 4.650000-2 6.476000+0 2.980000-2 8.315000+0 3.630000-2923733102 2402 1.068000+1 4.000000-2 1.371000+1 4.100000-2 1.760000+1 2.410000-2923733102 2403 2.260000+1 4.090000-2 2.902000+1 1.940000-2 3.727000+1 4.070000-2923733102 2404 4.785000+1 4.550000-2 6.144000+1 2.200000-2 7.889000+1 3.610000-2923733102 2405 1.013000+2 1.940000-2 1.301000+2 1.180000-2 1.670000+2 4.580000-2923733102 2406 4.000000+3 0.000000+0 2.000000+7 0.000000+0 0.000000+0 0.000000+0923733102 2407 0.000000+0 0.000000+0 525 107 1 0923733102 2408 0.000000+0 0.000000+0 0 2 0 0923733102 2409 4.000000+3 2.000000+4 525 107 4 2923733102 2410 4.000000+3 1.000000+0 2.000000+4 0.000000+0 0.000000+0 0.000000+0923733102 2411 923733 0 2412 9237 0 0 2413 0 0 0 2414 9.524100+4 2.389860+2 1 1 0 19543 1451 1 0.000000+0 0.000000+0 0 0 0 69543 1451 2 1.000000+0 0.000000+0 0 0 10 69543 1451 3 0.000000+0 0.000000+0 0 0 145 59543 1451 4 95-AM-241 CNDC EVAL-FEB88 ZHOU DELIN,GU FUHUA ET AL. 9543 1451 5 DIST-FEB90 900205 9543 1451 6 ----ENDF/B-VI MATERIAL 9543 9543 1451 7 -----INCIDENT NEUTRON DATA 9543 1451 8 ------ENDF-6 FORMAT 9543 1451 9 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************9543 1451 10 ACTIVATION II 9543 1451 11 ******************************************************************9543 1451 12 ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC 9543 1451 13 * * * * * * *9543 1451 14 HISTORY 9543 1451 15 THE ORIGINAL EVALUATION WAS PERFORMED BY 9543 1451 16 GU FUHUA, YU BAOSHENG, ZHOU DELIN, ZHUANG YOUXIANG 9543 1451 17 SHI XIANGJUN, YAN SHIWEI, WANG CUILAN, ZHANG JENGSHANG 9543 1451 18 UNDER THE CONTRACTS BETWEEN IAEA/NDS AND IAE,1985. 1| AND 9543 1451 19 REVISED BY 9543 1451 20 ZHOU DELIN, YU BAOSHENG, LIU TONG 9543 1451 21 SHI XIANGJUN, YAN SHIWEI 9543 1451 22 1988. 2| THE CAPTURE CROSS SECTIONS AND RESONANCE PARAMETERS 9543 1451 23 HAVE BEEN REVIEWED AND REEVALUATED BY ZHOU DELIN ET AL.1988 3|.9543 1451 24 MF=1, GENERAL INFORMATION 9543 1451 25 MT=451, COMMENTS AND DICTIONARY 9543 1451 26 MT=452, TOTAL NUMBER OF NEUTRONS PER FISSION 9543 1451 27 IT IS THE SUM OF DELAY NEUTRONS (MT=455) AND PROMPT 9543 1451 28 NEUTRONS PER FISSION (MT=456). 9543 1451 29 MT=455, T.R.ENGLAND +,LA-11151,LA-11534,LAURA-88-4118 9543 1451 30 MT=456, NUMBER OF PROMPT NEUTRONS PER FISSION 9543 1451 31 DATA ARE TAKEN FROM Y. KIKUCHI ET AL. 4|. 9543 1451 32 MF=2, MT=151, RESONANCE PARAMETERS 9543 1451 33 RESOLVED RESONANCE PARAMETERS FOR SLBW FORMULA IN 1.0E-5 TO 9543 1451 34 1.5E+2 EV RESONANCE ENERGY REGION 9543 1451 35 RESOLVED PARAMETERS WERE RECOMMENDED AS FOLLOWING: 9543 1451 36 IT WAS NOTICED THAT THE PARAMETERS OF THE FIRST SEVERAL WELL 9543 1451 37 DEFINED RESONANCES (0.308, 0,576, 1.276, 1.928, 2.372, 2.358 9543 1451 38 EV, FOR EXAMPLE) GIVEN BY DERRIEN ET AL. 5| (TRANSMISSION), 9543 1451 39 KALEBIN ET AL. 6| (TRANSMISSION) AS WELL AS WESTON ET AL. 7| 9543 1451 40 (ABSORPTION, NOMALIZED TO THERMAL CAPTURE CROSS SECTION OF 582 9543 1451 41 B) RESPECTIVELY ARE IN EXCELLENT AGREEMENT WITH EACH OTHER. 9543 1451 42 THIS FACT MEANS THAT THE RESONANCE PARAMETERS FOR THE FULL 9543 1451 43 RESONANCE ENERGY REGION CAN BE COMBINED BY AVERAGING WEIGHTED 9543 1451 44 WITH RANDOM ERROR ONLY WITHOUT TAKING THE 8% SYSTEMATIC ERROR 9543 1451 45 IN ABSORPTION MEASUREMENT 7| INTO ACCOUNT. SO THAT THE 9543 1451 46 RECOMMENDED VALUES FOR MOST RESONANCES WERE AVERAGED IN EQUAL 9543 1451 47 WEIGHT EXCEPT THOSE FOR WHICH THE RANDOM ERRORS OF WESTON ET 9543 1451 48 AL.'S MEASUREMENT OR/AND THE ERRORS OF KALEBIN ET AL.'S 9543 1451 49 MEASUREMENT ARE MUCH LARGER THAN DERRIEN ET AL.'S, IN SUCH 9543 1451 50 CASES THE AVERAGE WERE MADE WITH UNEQUAL WEIGHTS PROPERLY. 9543 1451 51 UNRESOLVED RESONANCE PARAMETERS IN 1.5E+2 EV TO 30 KEV ENERGY 9543 1451 52 REGION 9543 1451 53 KIKUCH'S PARAMETERS 4| WERE USED AS INPUT DATA AND ADJUSTED 9543 1451 54 TO FIT THE CAPTURE CROSS SECTIONS (EVALUATED ON THE BASES OF 9543 1451 55 WESTON ET AL.'S, VANPRAET ET AL.'S 8|, WISSHAK ET AL.'S 9| 9543 1451 56 AND DERRIEN ET AL.'S MEASUREMENTS) AND FISSION CROSS SECTION 9543 1451 57 OF DABBS 10| (AVERAGED IN PROPER ENERGY RANGE) THEN THE 9543 1451 58 RECOMMENDED UNRESOLVED RESONANCE PARAMETERS WERE OBTAINED. 9543 1451 59 THERMAL ENERGY CROSS SECTIONS 9543 1451 60 FISSION CROSS SECTION THE VALUE OF 3.15 B WAS ADOPTED. 9543 1451 61 CAPTURE CROSS SECTION 620+-13 B, THE WEIGHTED AVERAGED VALUE 9543 1451 62 OF THE FOLLOWING DATA WAS ADOPTED: 9543 1451 63 .KALEBIN: 625+-20 (=640-3.15-11.5, TRANSMISSION); 9543 1451 64 .DOVBENKO ET AL.: 654+-104 (CAPTURE) 11|; 9543 1451 65 .HARBOUR ET AL.: 612+-25 (CAPTURE, DEDUCED RESULT TAKEN FROM 9543 1451 66 AN ANALYSIS BY STORY, 1978. QUOTTED FROM LYNN ET AL.) 12|; 9543 1451 67 .POMERANCE: 625+-35 (QUOTED FROM LYNN ET AL.) 12|; 9543 1451 68 .WISSHAK ET AL.: 625+-35 (ISOMERIC RATIO, INDIRECTLY) 13|; 9543 1451 69 .WESTON ET AL.: 582+-50 (ABSORPTION, A RELATIVE MEASUREMENT 9543 1451 70 NORMALIZED TO THERMAL CAPTURE CROSS SECTION OF 582 B. IT MAY 9543 1451 71 BE CONSIDERED TO NORMALIZE TO DERRIEN'S MEASUREMENT AT FIRST 9543 1451 72 SEVERAL RESONANCES EQUIVALENTLY. THEN THE 8% SYSTEMATIC 9543 1451 73 UNCERTAINTY IN THE ENERGY REGION OF >0.2 EV MUST BE ADDED TO 9543 1451 74 THERMAL VALUE) 3|. 9543 1451 75 MF=3, NEUTRON CROSS SECTION 9543 1451 76 MT=1,3,4,16,17,51-65,91,102 TOTAL, ELASTIC SCATTERING, 9543 1451 77 INELASTIC SCATTERING, (N,2N), (N,3N) AND CAPTURE CROSS 9543 1451 78 SETIONS 9543 1451 79 CALCULATED WITH OPTICAL MODEL (THE PARAMETERS HAVE BEEN 9543 1451 80 ADJUSTED TO FIT THE PHILLIPS' DATA. 14|),HAUSER-FESHBACH 9543 1451 81 STATISTICAL THEORY WITH WIDTH FLUCTUATION CORRECTION, 9543 1451 82 EXCITON AND EVAPORATION MODELS. 1|. 9543 1451 83 MT=18 FISSION CROSS SECTION 9543 1451 84 CROSS SECTIONS IN THE NEUTRON ENERGY REGION GREATER THAN 9543 1451 85 1 KEV WERE EVALUATED BY GU-FUHUA ET AL. 1! AND REVISED BY 9543 1451 86 ZHOU DELIN CONSIDERING THE DABBS' NEW MEASUREMENT . 9543 1451 87 BELOW 1 KEV THE DABBS' MEASUREMENT HAS ALSO BEEN USED 9543 1451 88 FOR UNRESOLVED RESONANCE PARAMETERS ADJUSTMENT. 3| 9543 1451 89 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9543 1451 90 MT=2,51-65 ANGULAR DISTRIBUTIONS OF ELASTIC AND INELASTIC 9543 1451 91 SCATTERING 9543 1451 92 CALCULATED WITH OPTICAL MODEL AND HAUSER-FESHBACH THEORY. 9543 1451 93 MT=16,17,18,91 ANGULAR DISTRIBUTIONS OF (N,2N), (N,3N), 9543 1451 94 FISSION AND INELASTIC SCATTERING (CONTINUUM PART) REACTIONS 9543 1451 95 ASSUMED ISOTROPIC IN THE C.M. (FOR 16,17 & 18) OR LABORATORY 9543 1451 96 (FOR 91) SYSTEM. 9543 1451 97 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9543 1451 98 MT=16,17,18,91 9543 1451 99 CALCULATED WITH HAUSER-FESHBACH AND EVAPORATION MODEL TAKING 9543 1451 100 THE PREEQUILIBRIUM PROCESS INTO ACCOUNT. MT=18 MAXWELLIAN 9543 1451 101 DISTRIBUTION. THE PARAMETERS T(E) ARE ESTEMATED FROM HU JIMIN 9543 1451 102 ET AL. 15| . 9543 1451 103 MF=9 9543 1451 104 MT=102 9543 1451 105 THE DATA OF ISOMERIC RATIO HAVE BEEN REVISED BASED ON THE NEW 9543 1451 106 EVALUATION 2! AND THE SHAPE OF THE THEORETICAL CALCULATION OF 9543 1451 107 13! . 9543 1451 108 MF=12,13,14,15 9543 1451 109 THE DATA CALCULATED BY R. HOWERTON (P.C.) FROM MF=2,3,5. 9543 1451 110 MF=32,33 9543 1451 111 THE FILE 32 AND 33 OF ENDF/B-V, REV.2 ARE ADOPTED. BUT THE 9543 1451 112 THE COVARIANCES OF MT=151 OF FILE 32 AND THE COVARIANCES OF 9543 1451 113 MT=18 OF FILE 33 HAVE BEEN MODIFIED PRELIMINARYLY TO MATCH 9543 1451 114 THE PRESENT EVALUATIONS. 9543 1451 115 9543 1451 116 REFERENCES 9543 1451 117 1| GU FUHUA ET AL., NEUTRON DATA EVALUATION FOR AM-241, 9543 1451 118 1985.(UNPUBLISHED). 9543 1451 119 2| THOU DELIN ET AL., NEUTRON DATA EVALUATION FOR AM-241, 9543 1451 120 1988. (UNPUBLISHED). 9543 1451 121 3| ZHOU DELIN , ON THE CAPTURE DATA EVALUATION FOR 9543 1451 122 AM-241, 1988. (TO BE PUBLISHED). 9543 1451 123 4| KIKUCH Y., JAERI-M 82-096, 1982. 9543 1451 124 5| DERRIEN H. ET AL., WASH75 P.637, 1975. 9543 1451 125 6| KALEBIN S. ET AL., A.E. 40, 373 (1976). 9543 1451 126 7| WESTON L. ET AL., NUCL. SCI. ENG., 61, 356 (1976). 9543 1451 127 8| VANPRAET . ET AL., SANTA FE(85), P.493, 1985. 9543 1451 128 9| WISSHAK K. ET AL., NUCL. SCI. ENG., 76, 148 (1980). 9543 1451 129 10| DABBS J. ET AL., NUCL. SCI. ENG., 83, 22 (1983). 9543 1451 130 11| DOVBENKO A. ET AL., LA-TR-71-74, 1971. 9543 1451 131 12| LYNN J. ET AL., PROGRESS IN NUCLEAR ENERGY, V.5, 9543 1451 132 P.255, 1980. 9543 1451 133 HARBOUR R. ET AL., NUCL. SCI. ENG., 50, 364 (1973). 9543 1451 134 POMERANCE H. ORNL-1879, P.50, 1955. 9543 1451 135 13| WISSHAK K. ET AL., NUCL. SCI. ENG., 81, 396 (1982). 9543 1451 136 ***************** PROGRAM FIXUP (VERSION 89-2) ******************9543 1451 137 *RECONSTRUCTED MT NUMBERS 9543 1451 138 4 =+( 50, 91) 9543 1451 139 103 =+(600,649) 9543 1451 140 104 =+(650,699) 9543 1451 141 105 =+(700,749) 9543 1451 142 106 =+(750,799) 9543 1451 143 107 =+(800,849) 9543 1451 144 101 =+( 18, 18)+(102,116) 9543 1451 145 27 =+(101,101) 9543 1451 146 3 =+( 4, 5)+( 16, 17)+( 22, 37)+( 41, 42) 9543 1451 147 19 =+( 18, 18)-( 20, 21)-( 38, 38) 9543 1451 148 1 =+( 2, 3) 9543 1451 149 1 451 154 19543 1451 150 2 151 378 19543 1451 151 3 102 33 19543 1451 152 32 151 590 19543 1451 153 33 102 9 19543 1451 154 9543 1 0 155 9543 0 0 156 9.524100+4 2.389860+2 0 0 1 09543 2151 157 9.524100+4 1.000000+0 0 1 2 09543 2151 158 1.000000-5 1.500000+2 1 1 0 09543 2151 159 2.500000+0 9.370000-1 0 0 1 09543 2151 160 2.389500+2 0.000000+0 0 0 1170 1959543 2151 161 -5.000000-1 2.500000+0 4.489400-2 8.747800-5 4.460000-2 2.065000-49543 2151 162 -4.500000-1 2.500000+0 4.486600-2 5.932400-5 4.460000-2 2.065000-49543 2151 163 -4.000000-1 2.500000+0 4.488500-2 7.833800-5 4.460000-2 2.065000-49543 2151 164 -3.200000-1 2.500000+0 4.485700-2 5.007600-5 4.460000-2 2.065000-49543 2151 165 -2.000000-1 2.500000+0 4.486200-2 5.535000-5 4.460000-2 2.065000-49543 2151 166 3.080000-1 2.500000+0 4.727000-2 5.693500-5 4.690000-2 3.132900-49543 2151 167 5.760000-1 2.500000+0 4.752800-2 9.290000-5 4.730000-2 1.350000-49543 2151 168 1.276000+0 2.500000+0 4.866700-2 3.220000-4 4.790000-2 4.450000-49543 2151 169 1.928000+0 2.500000+0 4.477600-2 1.113300-4 4.460000-2 6.480000-59543 2151 170 2.372000+0 2.500000+0 4.423900-2 7.166600-5 4.400000-2 1.670000-49543 2151 171 2.598000+0 2.500000+0 4.791600-2 1.500000-4 4.760000-2 1.664000-49543 2151 172 3.973000+0 2.500000+0 4.486000-2 2.096600-4 4.450000-2 1.500000-49543 2151 173 4.968000+0 2.500000+0 4.436700-2 1.773300-4 4.380000-2 3.900000-49543 2151 174 5.415000+0 2.500000+0 4.557600-2 7.660000-4 4.420000-2 6.100000-49543 2151 175 5.800000+0 2.500000+0 4.443200-2 2.000000-6 4.420000-2 2.300000-49543 2151 176 6.117000+0 2.500000+0 4.429400-2 1.236600-4 4.380000-2 3.700000-49543 2151 177 6.745000+0 2.500000+0 4.451900-2 3.285700-5 4.420000-2 2.860000-49543 2151 178 7.659000+0 2.500000+0 4.434600-2 4.557000-5 4.420000-2 1.000000-49543 2151 179 8.173000+0 2.500000+0 4.292700-2 1.070000-4 4.270000-2 1.200000-49543 2151 180 9.113000+0 2.500000+0 4.475700-2 3.773300-4 4.420000-2 1.800000-49543 2151 181 9.851000+0 2.500000+0 4.524800-2 3.976600-4 4.390000-2 9.500000-49543 2151 182 1.011600+1 2.500000+0 4.447800-2 2.550000-5 4.420000-2 2.528000-49543 2151 183 1.040300+1 2.500000+0 4.252700-2 3.210000-5 4.240000-2 9.480000-59543 2151 184 1.099700+1 2.500000+0 4.710900-2 4.033300-4 4.650000-2 2.054000-49543 2151 185 1.158300+1 2.500000+0 4.440300-2 2.133300-5 4.420000-2 1.817000-49543 2151 186 1.213700+1 2.500000+0 4.436700-2 9.333300-6 4.420000-2 1.580000-49543 2151 187 1.287900+1 2.500000+0 4.451900-2 1.326600-4 4.420000-2 1.866800-49543 2151 188 1.387400+1 2.500000+0 4.438700-2 2.150000-5 4.420000-2 1.651400-49543 2151 189 1.436000+1 2.500000+0 4.460100-2 7.071400-5 4.420000-2 3.302800-49543 2151 190 1.468200+1 2.500000+0 4.306700-2 2.364600-3 4.030000-2 4.020800-49543 2151 191 1.568900+1 2.500000+0 3.968200-2 2.386600-4 3.930000-2 1.436000-49543 2151 192 1.638800+1 2.500000+0 4.318200-2 1.224000-3 4.180000-2 1.579600-49543 2151 193 1.684900+1 2.500000+0 4.228100-2 6.216600-4 4.120000-2 4.595200-49543 2151 194 1.772900+1 2.500000+0 3.810000-2 3.980000-4 3.730000-2 4.020800-49543 2151 195 1.816700+1 2.500000+0 4.436100-2 1.700000-5 4.420000-2 1.436000-49543 2151 196 1.944500+1 2.500000+0 4.484500-2 2.141400-4 4.420000-2 4.308000-49543 2151 197 2.033300+1 2.500000+0 4.447200-2 4.271400-5 4.420000-2 2.292000-49543 2151 198 2.088000+1 2.500000+0 4.470100-2 8.320000-5 4.420000-2 4.182900-49543 2151 199 2.174000+1 2.500000+0 4.465500-2 7.720000-5 4.420000-2 3.781800-49543 2151 200 2.221000+1 2.500000+0 4.475500-2 2.800000-5 4.420000-2 5.271600-49543 2151 201 2.274800+1 2.500000+0 4.455700-2 6.820000-5 4.420000-2 2.887900-49543 2151 202 2.307900+1 2.500000+0 4.287600-2 3.874300-4 4.220000-2 2.887900-49543 2151 203 2.333700+1 2.500000+0 4.308700-2 4.612800-4 4.250000-2 1.260600-49543 2151 204 2.419200+1 2.500000+0 4.067100-2 1.291000-3 3.920000-2 1.799200-49543 2151 205 2.500800+1 2.500000+0 4.444300-2 1.400000-5 4.420000-2 2.292000-49543 2151 206 2.563400+1 2.500000+0 3.927400-2 1.263000-3 3.760000-2 4.114100-49543 2151 207 2.649800+1 2.500000+0 4.481300-2 4.870000-4 4.420000-2 1.260600-49543 2151 208 2.666900+1 2.500000+0 4.492100-2 6.180000-4 4.420000-2 1.031400-49543 2151 209 2.757500+1 2.500000+0 4.545300-2 1.650000-4 4.460000-2 6.876000-49543 2151 210 2.772600+1 2.500000+0 4.534500-2 5.720000-4 4.420000-2 5.730000-49543 2151 211 2.835500+1 2.500000+0 4.540100-2 5.630000-4 4.470000-2 1.375200-49543 2151 212 2.890300+1 2.500000+0 4.928800-2 4.820000-4 4.860000-2 2.062800-49543 2151 213 2.950400+1 2.500000+0 4.543100-2 6.920000-4 4.460000-2 1.386700-49543 2151 214 2.995600+1 2.500000+0 4.451000-2 8.100000-5 4.420000-2 2.292000-49543 2151 215 3.082200+1 2.500000+0 4.477700-2 2.330000-4 4.420000-2 3.438000-49543 2151 216 3.102000+1 2.500000+0 4.480000-2 3.360000-4 4.420000-2 2.635800-49543 2151 217 3.125100+1 2.500000+0 4.403900-2 1.186500-3 4.260000-2 2.521200-49543 2151 218 3.203000+1 2.500000+0 4.842000-2 2.990000-4 4.780000-2 3.208800-49543 2151 219 3.351000+1 2.500000+0 4.443700-2 6.000000-5 4.420000-2 1.774800-49543 2151 220 3.402800+1 2.500000+0 4.610000-2 6.385000-4 4.540000-2 6.120000-59543 2151 221 3.446000+1 2.500000+0 4.474200-2 1.255000-4 4.420000-2 4.161600-49543 2151 222 3.492800+1 2.500000+0 4.357000-2 6.110000-4 4.280000-2 1.591200-49543 2151 223 3.548500+1 2.500000+0 4.480700-2 4.355000-4 4.420000-2 1.713600-49543 2151 224 3.625000+1 2.500000+0 4.464900-2 1.670000-4 4.420000-2 2.815200-49543 2151 225 3.648300+1 2.500000+0 4.458200-2 1.000000-4 4.420000-2 2.815200-49543 2151 226 3.697900+1 2.500000+0 4.793600-2 3.124000-3 4.420000-2 6.120000-49543 2151 227 3.836600+1 2.500000+0 4.688200-2 2.315000-3 4.420000-2 3.672000-49543 2151 228 3.883000+1 2.500000+0 4.453700-2 5.500000-5 4.420000-2 2.815200-49543 2151 229 3.961700+1 2.500000+0 4.193600-2 1.307800-3 4.020000-2 4.284000-49543 2151 230 4.006700+1 2.500000+0 4.567900-2 4.880000-4 4.420000-2 9.914400-49543 2151 231 4.039600+1 2.500000+0 4.550500-2 1.023500-3 4.420000-2 2.815200-49543 2151 232 4.129800+1 2.500000+0 4.469400-2 9.050000-5 4.420000-2 4.039200-49543 2151 233 4.179100+1 2.500000+0 4.472600-2 3.850000-4 4.420000-2 1.407600-49543 2151 234 4.213000+1 2.500000+0 4.454700-2 1.500000-4 4.420000-2 1.970600-49543 2151 235 4.329400+1 2.500000+0 4.506600-2 8.050000-4 4.420000-2 6.120000-59543 2151 236 4.357400+1 2.500000+0 4.494400-2 5.820000-4 4.420000-2 1.615700-49543 2151 237 4.441600+1 2.500000+0 4.455000-2 1.325000-4 4.420000-2 2.178700-49543 2151 238 4.492100+1 2.500000+0 4.444500-2 8.175000-5 4.420000-2 1.635600-49543 2151 239 4.607300+1 2.500000+0 4.457600-2 6.777500-4 4.380000-2 9.813600-59543 2151 240 4.656600+1 2.500000+0 4.465000-2 3.930000-4 4.420000-2 5.724600-59543 2151 241 4.753500+1 2.500000+0 4.299300-2 1.080000-3 4.160000-2 3.134900-49543 2151 242 4.876500+1 2.500000+0 4.088400-2 7.340000-4 4.000000-2 1.499300-49543 2151 243 4.933200+1 2.500000+0 4.480800-2 2.400000-4 4.420000-2 3.680100-49543 2151 244 5.027800+1 2.500000+0 4.707800-2 2.442000-3 4.420000-2 4.361600-49543 2151 245 5.084700+1 2.500000+0 4.475000-2 3.930000-4 4.420000-2 1.567500-49543 2151 246 5.198400+1 2.500000+0 4.589800-2 1.385000-3 4.420000-2 3.134900-49543 2151 247 5.301400+1 2.500000+0 4.448000-2 1.650000-4 4.420000-2 1.151500-49543 2151 248 5.349300+1 2.500000+0 4.448800-2 1.840000-4 4.420000-2 1.036400-49543 2151 249 5.440700+1 2.500000+0 4.455300-2 7.300000-5 4.420000-2 2.796500-49543 2151 250 5.499000+1 2.500000+0 4.621600-2 1.443000-3 4.425000-2 5.229500-49543 2151 251 5.559500+1 2.500000+0 4.452800-2 2.130000-4 4.420000-2 1.151500-49543 2151 252 5.594500+1 2.500000+0 4.574700-2 1.432000-3 4.420000-2 1.151500-49543 2151 253 5.615800+1 2.500000+0 4.523100-2 9.490000-4 4.420000-2 8.225000-59543 2151 254 5.737200+1 2.500000+0 4.861700-2 4.146000-3 4.420000-2 2.714300-49543 2151 255 5.906600+1 2.500000+0 4.522700-2 5.890000-4 4.420000-2 4.379000-49543 2151 256 6.004500+1 2.500000+0 4.456700-2 2.850000-4 4.420000-2 8.225000-59543 2151 257 6.038100+1 2.500000+0 4.444700-2 1.400000-4 4.420000-2 1.069200-49543 2151 258 6.125800+1 2.500000+0 4.600200-2 1.672000-3 4.420000-2 1.304900-49543 2151 259 6.161300+1 2.500000+0 4.500900-2 4.340000-4 4.420000-2 3.751500-49543 2151 260 6.254900+1 2.500000+0 4.458400-2 2.220000-4 4.420000-2 1.617600-49543 2151 261 6.350700+1 2.500000+0 4.533700-2 1.990000-4 4.420000-2 9.382100-49543 2151 262 6.403900+1 2.500000+0 4.855200-2 4.042000-3 4.420000-2 3.100400-49543 2151 263 6.453900+1 2.500000+0 4.661900-2 1.954000-3 4.420000-2 4.650600-49543 2151 264 6.516400+1 2.500000+0 4.999400-2 5.187000-3 4.420000-2 6.066000-49543 2151 265 6.573300+1 2.500000+0 4.541900-2 1.090000-3 4.420000-2 1.294100-49543 2151 266 6.631400+1 2.500000+0 4.584300-2 1.036000-3 4.420000-2 6.066000-49543 2151 267 6.687400+1 2.500000+0 4.654800-2 2.105000-3 4.420000-2 2.426400-49543 2151 268 6.852500+1 2.500000+0 4.533800-2 4.310000-4 4.420000-2 7.073500-49543 2151 269 6.958500+1 2.500000+0 4.564500-2 1.116000-3 4.420000-2 3.286700-49543 2151 270 6.982400+1 2.500000+0 4.702500-2 2.661000-3 4.420000-2 1.643400-49543 2151 271 7.125300+1 2.500000+0 4.511200-2 5.830000-4 4.420000-2 3.286700-49543 2151 272 7.146300+1 2.500000+0 4.563800-2 1.109000-3 4.420000-2 3.286700-49543 2151 273 7.184100+1 2.500000+0 4.556300-2 1.034000-3 4.420000-2 3.286700-49543 2151 274 7.227600+1 2.500000+0 4.475500-2 2.260000-4 4.420000-2 3.286700-49543 2151 275 7.496900+1 2.500000+0 4.497100-2 4.810000-4 4.420000-2 2.904900-49543 2151 276 7.571500+1 2.500000+0 4.474200-2 3.780000-4 4.420000-2 1.641900-49543 2151 277 7.594300+1 2.500000+0 4.487900-2 5.150000-4 4.420000-2 1.641900-49543 2151 278 7.677900+1 2.500000+0 4.464300-2 1.090000-4 4.420000-2 3.340600-49543 2151 279 7.819100+1 2.500000+0 1.195000-2 1.486000-3 1.030000-2 1.641900-49543 2151 280 7.855100+1 2.500000+0 6.214300-2 1.179000-3 6.080000-2 1.641900-49543 2151 281 7.955500+1 2.500000+0 4.522000-2 7.300000-4 4.420000-2 2.904900-49543 2151 282 8.005000+1 2.500000+0 4.495400-2 5.460000-4 4.420000-2 2.084000-49543 2151 283 8.039300+1 2.500000+0 4.497700-2 5.880000-4 4.420000-2 1.894500-49543 2151 284 8.107700+1 2.500000+0 4.475200-2 1.060000-4 4.420000-2 4.458400-49543 2151 285 8.145800+1 2.500000+0 4.475000-2 1.042000-4 4.420000-2 4.458400-49543 2151 286 8.208900+1 2.500000+0 2.840700-2 1.454000-3 2.670000-2 2.526000-49543 2151 287 8.290000+1 2.500000+0 4.495500-2 4.390000-4 4.420000-2 3.157500-49543 2151 288 8.337000+1 2.500000+0 4.492100-2 4.310000-4 4.420000-2 2.904900-49543 2151 289 8.400600+1 2.500000+0 3.984600-2 1.456000-3 3.810000-2 2.904900-49543 2151 290 8.468500+1 2.500000+0 4.666900-2 2.141000-3 4.420000-2 3.283800-49543 2151 291 8.661000+1 2.500000+0 4.490800-2 2.250000-4 4.420000-2 4.830300-49543 2151 292 8.748100+1 2.500000+0 4.575700-2 1.260000-4 4.420000-2 1.431200-39543 2151 293 8.798400+1 2.500000+0 7.547700-2 3.918000-3 7.070000-2 8.587200-49543 2151 294 8.929700+1 2.500000+0 4.512200-2 3.320000-4 4.420000-2 5.903700-49543 2151 295 8.960200+1 2.500000+0 8.965400-2 2.364000-3 8.670000-2 5.903700-49543 2151 296 9.341200+1 2.500000+0 6.019300-2 6.296000-3 5.370000-2 1.966000-49543 2151 297 9.461000+1 2.500000+0 4.520400-2 7.540000-4 4.420000-2 2.502400-49543 2151 298 9.528501+1 2.500000+0 4.481000-2 3.600000-4 4.420000-2 2.502400-49543 2151 299 9.568600+1 2.500000+0 4.731300-2 2.863000-3 4.420000-2 2.502400-49543 2151 300 9.610000+1 2.500000+0 4.726900-2 2.906000-3 4.420000-2 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