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11-Na- 23 NEA EVAL-APR99 E. Fort et al. DIST-JAN09 20090105 ----JEFF-311 MATERIAL 1125 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** JEFF-3.1 ************************* ** ** ** Original data taken from: JEFF-3.0 ** ** ** ****************************************************************** ***************************** JEFF-3.0 *********************** DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92) Modifications by E. Fort et al. (see comments below) ****************************************************************** THIS IS NOT AN EVALUATION IN THE CLASSICAL SENSE. THE ORIGINAL JEF-2 EVALUATION (EVAL MARS 87 BY H. YAMAKOSHI WHICH, IN TURN WAS ESSENTIALY BASED ON AN "OLD" AMERICAN WORK.) WAS DEMONSTRATED, BY THE EXTENSIVE VALIDATION WORK [1] TO BE OF INSUFFICIENT QUALITY, IN SUCH A WAY THAT THE RESULT OF THE GENERAL ADJUSTMENT COULD BE QUESTIONNED (LINEARITY CONDITION). THEN, IT WAS A NECESSITY TO INTRODUCE IN THE ADJUSTEMENT "A PRIORI" DATA OF BETTER QUALITY. IN THIS CONTEXT THE BEST CHOICE OF DATA WAS REPRESENTED BY A WORK BY KOPECKY, SHELLEY, MARTEN AND H. WEIGMAN PRESENTED AT THE TRIESTE CONFERENCE [II]. IT IS THIS CHOICE WHICH IS PROPOSED TO THE JEFF PROJECT. THE AUTHORS OF REFERENCE [II] HAVE ANALYSED SIMULTANEOUSLY INELASTIC CROSS SECTION DATA OBTAINED AT GEEL [III] AND THE TOTAL CROSS SECTION DATA OBTAINED AT ORELA [IV]. THE ANALYSIS HAS BEEN PERFORMED USING SAMMY CODE AND R MATRIX FORMALISM IN THE REICH-MOORE APPROXIMATION WITH TWO ELASTIC CHANNELS AND TWO INELASTIC CHANNELS FOR EVERY GIVEN RESONANCE. THE QUALITY OF THE FIT BETWEEN THE INELASTIC THRESHOLD AND 2.0 MEV IS EXCELLENT AND WAS OBTAINED BY USING A SINGLE SET OF RESONANCE PARAMETERS. THIS WAS A CONVINCING ISSUE ENABLING US TO PROPOSE THIS SET OF DATA AS A STARTING VERSION OF AN EVALUATION TO BE COMPLETED IN THE FUTURE BY USING THE CLASSICAL RULES. BELOW 450 KEV (INELASTIC THRESHOLD) THE DATA ARE UNCHANGED WITH RESPECT TO JEF2 EVALUATION. ABOVE 2 MEV, THE JEF2 DATA WERE SCALED BY 0.69 FOR WHAT CONCERNS THE INELASTIC CROSS SECTION AND BY 1.32 FOR WHAT CONCERNS THE ELASTIC CROSS SECTION. THESE CORRECTIVE FACTORS WERE DETERMINED IN ORDER TO MATCH WITH KOPECKY'S DATA AT LOWER ENERGY. THEY ARE ALSO CONSISTENT WITH THE VALIDATION INDICATION. THE PROPOSED DATA SET HAS BEEN SUCCESSFULLY TESTED AGAINST INTEGRAL DATA. WITH RESPECT TO THE JEF2.2 EVALUATION, THERMAL CONSTANTS AND RESONANCE CAPTURE INTEGRAL ARE UNCHANGED AND THE CAPTURE CROSS SECTION ON THE FULL ENERGIE RANGE ALSO. [I] E. FORT, W. ASSAL, A,AVERY, PBLAISE, J.C. BOSQ, S. CATHLAU C. DEAN, J.P. FINK, G. RIMPAULT, J. ROWLANDS, P. SMITH, M. SALVARORES, R.SOULE, V.ZAMMIT. JEF2 VALIDATION. PART 1. GENERAL PURPOSE FILE. JEF/DOC [II] S. KOPECKY, R. SHELLEY, H. MARTEN AND H. WEIGMAN. CONFERENCE PROCEEDINGS. NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY. TRIESTE MAY 1987. [III] H. MARTEN, J. WARTENA AND H. WEIGMAN IRMM REPORT GE/R/ND/02/94 1994 [IV] D.C. LARSON PRIVATE COMUNICATION TO THE AUTHORS OF REFERENCE [II] ****************************************************************** * JEF-2 DATA WERE TAKEN FROM JENDL-3 ****************************************************************** * 2-FEB-90: MODIFICATIONS TO THIS FILE IN THE ENERGY RANGE * 1.0E-5 EV TO 700 KEV IS PROPOSED BY M. MOXON AND * M. SOWERBY, HARWELL, AND WILL BE INCLUDED IN THE * NEAR FUTURE. ******** HYSTORY OF JE2 87-03 NEW EVALUATION WAS MADE FOR JENDL-3. 89-08 THE DATA FOR MF=15,MT=102 MODIFIED. ****************************************************************** MF=1 GENERAL INFORMATION MT=451 DESCRIPTIVE DATA AND DICTIONARY MF=2 RESONANCE PARAMETERS MT=151 RESOLVED RESONANCE PARAMETERS RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY REGION FROM 1.0E-5 EV TO 350 KEV. PARAMETERS WERE MAINLY TAKEN FROM THE RECOMMENDED DATA OF BNL /1/, AND THE DATA FOR SOME LEVELS WERE MODIFIED SO THAT THE CALCULATED TOTAL CROSS SECTIONS FOR NA-23 WERE FITTED TO THE EXPERIMENTAL DATA. THE SCATTERING RADIUS WAS ASSUMED TO BE 5.2 FERMI. CALCULATED 2200 M/SEC CROSS SECTIONS AND RESONANCE INTEGRALS ARE AS FOLLOWS: 2200 M/S CROSS SECTION(B) RES. INTEGRAL(B) ELASTIC 3.024 CAPTURE 0.531 0.3122 TOTAL 3.555 MF=3 NEUTRON CROSS SECTIONS BELOW 350 KEV, BACKGROUND CROSS SECTION WAS GIVEN FOR THE TOTAL AND ELASTIC SCATTERING CROSS SECTIONS. THE CROSS-SECTION DATA ARE REPRODUCED FROM THE EVALUATED RESOLVED RESONANCE PARAMETERS WITH MLBW FORMULA. ABOVE 350 KEV, THE TOTAL AND PARTIAL CROSS SECTIONS WERE GIVEN POINTWISE. MT=1 TOTAL IN THE ENERGIES BETWEEN 350 KEV AND 14 MEV, EVALUATED BASED ON THE EXPERIMENTAL DATA OF CIERJACKS/2/ IN TRACING THEIR FINE STRUCTURES. ABOVE 14 MEV, BASED ON THE EXPERIMENTAL DATA OF LANGSFORD/3/, STOLER/4/ AND LARSON/5/. MT=2 ELASTIC SCATTERING OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS FROM THE TOTAL CROSS SECTION. MT=4, 51-77, 91 INELASTIC SCATTERING BELOW 5 MEV, THE INELASTIC SCATTERING CROSS SECTION TO THE 1ST LEVEL(MT=51) WAS EVALUATED BASED ON THE EXPERIMENTAL DATA OF TOWLE AND GILBOY/6/, CHRIEN AND SMITH/7/, AND LIND AND DAT/8/. BELOW 5 MEV, THE INELASTIC SCATTERING CROSS SECTION TO THE 2ND AND 3RD LEVEL(MT=52, 53) WAS EVALUATED BASED ON THE EXPERIMENTAL DATA OF FREEMAN AND MONTAGUE/9/, LIND AND DAT/8/, AND TOWLE AND OWENS/10/. FOR THE INELASTIC SCATTERING CROSS SECTIONS TO THE 1ST TO 3RD LEVELS ABOVE 5 MEV AND THE OTHER INELASTIC SCATTERING DATA, OPTICAL AND STATISTICAL MODEL CALCULATIONS WERE MADE WITH THE CASTHY CODE/11/, TAKING ACCOUNT OF THE CONTRIBUTION FROM THE COMPETING PROCESSES. THE DIRECT COMPONENT WAS CALCULATED WITH WITH THE DWUCK CODE/12/ FOR FIVE LOWEST LEVELS. THE DEFORMATION PARAMETERS WERE ESTIMATED BASED ON A WEAK COUPLING MODEL. THE OPTICAL POTENTIAL PARAMETERS USED ARE: V = 46.0 - 0.25*EN, VSO = 6.0 (MEV) WS = 14.0 - 0.2*EN, WV = 0.125*EN (MEV) R = 1.286, RS = 1.39, RSO = 1.07 (FM) A = 0.62, ASO = 0.62, B = 0.7 (FM) THE LEVEL DATA USED IN THE ABOVE TWO CALCULATIONS WERE TAKEN FROM REF./13/ AS FOLLOWS: MT LEVEL ENERGY(MEV) SPIN-PARITY 0.0 3/2+ 51 0.4399 5/2+ 52 2.0764 7/2+ 53 2.3909 1/2+ 54 2.6398 1/2- 55 2.7037 9/2+ 56 2.9824 3/2+ 57 3.6783 3/2- 58 3.8480 5/2- 59 3.9147 5/2+ 60 4.4320 1/2+ 61 4.7756 7/2+ 62 5.3800 3/2+ 63 5.5360 11/2+ 64 5.7410 3/2+ 65 5.7660 5/2+ 66 5.9310 1/2- 67 5.9670 3/2- 68 6.0430 1/2- 69 6.1170 11/2+ 70 6.1910 11/2+ 71 6.2360 13/2+ 72 6.3080 1/2+ 73 6.3506 9/2- 74 6.5770 5/2+ 75 6.6170 9/2+ 76 6.7340 3/2+ 77 6.8680 5/2+ LEVELS ABOVE 6.9 MEV WERE ASSUMED TO BE OVERLAPPING. MT=16 (N,2N) MAINLY BASED ON THE EXPERIMENTAL DATA OF ADAMSKI/14/. MT=22 (N,NA) CALCULATED WITH THE GNASH CODE/15/ AND NORMALIZED TO THE EXPERIMENTAL DATA OF WOELFER/16/ AT 16.4 MEV. MT=28 (N,NP) CALCULATED WITH THE GNASH CODE/15/. MT=102 CAPTURE CALCULATED WITH THE CASTHY CODE/11/ AND NORMALIZED TO 0.3 MB AT 500 KEV. MT=103 (N,P) BELOW 10 MEV, BASED ON THE EXPERIMENTAL DATA/17,18/. ABOVE 10 MEV, CALCULATED WITH THE GNASH CODE/15/ AND NORMALIZ- ED TO CONNECT SMOOTHLY WITH THE DATA BELOW 10 MEV. MT=107 (N,A) BELOW 12 MEV, BASED ON THE EXPERIMENTAL DATA/17,18/. ABOVE 12 MEV, CALCULATED WITH THE GNASH CODE/15/ AND NORMALIZ- ED TO CONNECT SMOOTHLY WITH THE DATA BELOW 10 MEV. MT=251 MU-BAR CALCULATED WITH THE OPTICAL MODEL. MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS MT=2 CALCULATED WITH THE CASTHY CODE/11/. MT=51-77 CALCULATED WITH THE CASTHY CODE/11/ AND THE DWUCK CODE/7/. MT=91 CALCULATED WITH THE CASTHY CODE/11/. MT=16, 22, 28 ISOTROPIC IN THE LABORATORY SYSTEM. MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS MT=16, 22, 28, 91 CALCULATED WITH THE GNASH CODE/15/. MF=12 PHOTON PRODUCTION MULTIPLICITIES MT=102 CALCULATED WITH THE GNASH CODE/15/ AND MODIFIED AT THERMAL BASED ON THE EXPERIMENTAL DATA OF MAERKER/19/. MF=13 PHOTON PRODUCTION CROSS SECTIONS MT=3 CALCULATED WITH THE GNASH CODE/15/. MF=14 PHOTON ANGULAR DISTRIBUTIONS MT=3, 102 ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM. MF=15 CONTINUOUS PHOTON ENERGY SPECTRA MT=3 CALCULATED WITH THE GNASH CODE/15/. MT=102 CALCULATED WITH THE GNASH CODE/15/ AND MODIFIED AT THERMAL BASED ON THE EXPERIMENTAL DATA OF MAERKER/19/. REFERENCES 1) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS", VOL. 1, PART B (1984). 2) CIERJACKS S. ET AL. : KFK-1000 (1969). 3) LANGSFORD A. ET AL. : 1965 ANTWERP CONF. 529 (1965). 4) STOLER P. ET AL. : 1971 KNOXVILLE CONF. VOL.1, 311 (1971). 5) LARSON D.C. ET AL. : ORNL-TM-5614 (1976). 6) TOWLE J.H. AND GILBOY W.B. : NUCL. PHYS. 32, 610 (1962). 7) CHRIEN J.P. AND SMITH A.B. : NUCL. SCI. ENG. 26, 500 (1966). 8) LIND D.A. AND DAY R.B. : ANN. PHYS. 12, 485 (1961). 9) FREEMAN J.M. AND MONTAGUE J.H. : NUCL. PHYS. 9, 181 (1958). 10) TOWLE J.H. AND OWENS R.O. : NUCL. PHYS. A100, 257 (1967). 11) IGARASI S. : J. NUCL. SCI. TECH. 12, 67 (1975). 12) KUNZ P.D. : UNPUBLISHED. 13) ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE) 14) ADAMSKI L. ET AL. : ANNA. NUCL. ENER. 7, 397 (1980). 15) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977). 16) WOELFER G. ET AL. : Z. PHYS. 194, 75 (1966). 17) WILLIAMSON C.F. : PHYS. REV. 122, 1877 (1961). 18) BASS R. ET AL. : 1965 ANTWERP CONF. 495 (1966). 19) MAERKER R.E. : ORNL-TM-5203 (1976).Back |