JEFF-3.1 General Purpose Neutron File, May 2005. 2310 0 0 0 9.824900+4 2.469350+2 1 1 2 29852 1451 1 0.000000+0 0.000000+0 0 0 0 69852 1451 2 1.000000+0 2.000000+7 3 0 10 319852 1451 3 0.000000+0 0.000000+0 0 0 203 799852 1451 4 98-Cf-249 JAERI EVAL-JUL95 T.NAKAGAWA AND T.LIU 9852 1451 5 DIST-MAY05 REV1-MAY05 20050504 9852 1451 6 ----JEFF-31 MATERIAL 9852 REVISION 2 9852 1451 7 -----INCIDENT NEUTRON DATA 9852 1451 8 ------ENDF-6 FORMAT 9852 1451 9 ***************************** JEFF-3.1 *************************9852 1451 10 ** **9852 1451 11 ** Original data taken from: JENDL-3.3 **9852 1451 12 ** **9852 1451 13 ******************************************************************9852 1451 14 9852 1451 15 05-01 NEA/OECD (Rugama) 8 delayed neutron groups 9852 1451 16 Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002) 9852 1451 17 9852 1451 18 HISTORY 9852 1451 19 85-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9852 1451 20 T.NAKAGAWA (JAERI). DETAILS ARE GIVEN IN REF. /1/. 9852 1451 21 95-07 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU. 9852 1451 22 00-05 MODIFICATION AND COMPILATION WERE MADE BY T.NAKAGAWA 9852 1451 23 9852 1451 24 ***** Modified parts from JENDL-3.2 ******************* 9852 1451 25 MF=2 Scattering radius in the unresolved resonance 9852 1451 26 region. 9852 1451 27 ALL DATA OF MF'S = 3, 4 AND 5. 9852 1451 28 ******************************************************* 9852 1451 29 9852 1451 30 9852 1451 31 MF=1 GENERAL INFORMATION 9852 1451 32 MT=451 COMMENTS AND DICTIONARY 9852 1451 33 MT=452 NUMBER OF NEUTRONS PER FISSION 9852 1451 34 SUM OF MT'S = 455 AND 456. 9852 1451 35 MT=455 DELAYED NEUTRON DATA 9852 1451 36 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9852 1451 37 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9852 1451 38 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9852 1451 39 9852 1451 40 MF=2,MT=151 RESONANCE PARAMETERS (TAKEN FROM JENDL-3.2) 9852 1451 41 RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 EV TO 70 EV 9852 1451 42 RESONANCE ENERGIES, NEUTRON AND FISSION WIDTHS WERE TAKEN 9852 1451 43 FROM THE EXPERIMENTAL DATA OF BENJAMIN+ /4/. THE RADIATIVE 9852 1451 44 WIDTH WAS ASSUMED TO BE 0.04 EV ACCORDING TO DABBS+ /5/. 9852 1451 45 A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL 9852 1451 46 CROSS SECTIONS. NO BACKGROUND CORRECTION WAS APPLIED. 9852 1451 47 9852 1451 48 UNRESOLVED RESONANCES : 70 EV - 30 KEV 9852 1451 49 OBTAINED FROM OPTICAL MODEL CALCULATION: 9852 1451 50 S1=3.15E-4, S2=0.83E-4. 9852 1451 51 ESTIMATED FROM RESOLVED RESONANCES: 9852 1451 52 DOBS=1.16 EV, GAM-G=40 MILLI-EV ,S0=1.06E-4 9852 1451 53 FISSION WIDTHS WERE ESTIMATED FROM THE CHANNEL THEORY OF 9852 1451 54 FISSION /6/. S0, S1 AND S2 VALUES WERE ADJUSTED SO AS TO 9852 1451 55 REPRODUCE THE FISSION CROSS SECTION MEASURED BY DABBS+ /5/. 9852 1451 56 Scattering radius of 8.85 fm was determined so as to give the 9852 1451 57 same ealstic scattering cross section above 30 keV. 9852 1451 58 9852 1451 59 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9852 1451 60 2200 M/S VALUE RES. INT. 9852 1451 61 TOTAL 2176.7 B - 9852 1451 62 ELASTIC 6.22 B - 9852 1451 63 FISSION 1666 B 2220 B 9852 1451 64 CAPTURE 504.5 B 695 B 9852 1451 65 9852 1451 66 MF=3 NEUTRON CROSS SECTIONS 9852 1451 67 MT=1 TOTAL CROSS SECTION 9852 1451 68 CALCULATED WITH CASTHY CODE /7/ BASED ON THE SHERICAL 9852 1451 69 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./8/ WERE 9852 1451 70 USED. 9852 1451 71 9852 1451 72 V = 45.036-0.3*EN (MEV) 9852 1451 73 WS= 4.115+0.4*EN (MEV) 9852 1451 74 WV= 0 , VSO = 7.5 (MEV) 9852 1451 75 R = RSO = 1.256 , RS = 1.260 (FM) 9852 1451 76 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9852 1451 77 9852 1451 78 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9852 1451 79 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9852 1451 80 OF GILBERT-CAMERON'S FORMULA /9/ WERE USED. 9852 1451 81 9852 1451 82 ISOTOPE CF-249 CF-250 9852 1451 83 A(1/MEV) 29.4 31.2 9852 1451 84 SPIN-CUTOFF FACT 31.33 32.36 9852 1451 85 PAIRING E(MEV) 0.77 1.673 9852 1451 86 TEMP.(MEV) 0.3693 0.4025 9852 1451 87 C(1/MEV) 4.644 2.111 9852 1451 88 EX(MEV) 3.562 5.423 9852 1451 89 9852 1451 90 THE LEVEL SCHEME TAKEN FROM REF. /10/. 9852 1451 91 NO. ENERGY(KEV) SPIN-PARITY 9852 1451 92 G.S. 0 9/2 - 9852 1451 93 1. 62.49 11/2 - 9852 1451 94 2. 136.2 13/2 - 9852 1451 95 3. 144.96 5/2 + 9852 1451 96 4. 187.94 7/2 + 9852 1451 97 5. 220.0 15/2 - 9852 1451 98 6. 243.07 9/2 + 9852 1451 99 7. 315.0 17/2 - 9852 1451 100 8. 315.1 11/2 + 9852 1451 101 9. 379.52 7/2 + 9852 1451 102 10. 384.0 13/2 + 9852 1451 103 11. 416.8 1/2 + 9852 1451 104 12. 425.0 19/2 - 9852 1451 105 13. 437.56 9/2 + 9852 1451 106 14. 440.0 3/2 + 9852 1451 107 15. 442.98 7/2 + 9852 1451 108 16. 460.0 5/2 + 9852 1451 109 17. 500.7 9/2 + 9852 1451 110 18. 550.0 1/2 + 9852 1451 111 19. 606.0 5/2 + 9852 1451 112 20. 668.0 13/2 - 9852 1451 113 21. 751.0 15/2 - 9852 1451 114 22. 813.20 5/2 - 9852 1451 115 23. 852.19 7/2 - 9852 1451 116 24. 902.5 9/2 - 9852 1451 117 25. 920.0 11/2 + 9852 1451 118 26. 962.0 11/2 - 9852 1451 119 27. 992.0 13/2 + 9852 1451 120 28. 1008.0 9/2 + 9852 1451 121 CONTINUUM LEVELS ASSUMED ABOVE 1031. KEV. 9852 1451 122 9852 1451 123 MT= 2 ELASTIC SCATTERING 9852 1451 124 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9852 1451 125 9852 1451 126 MT= 4 TOTAL INELASTIC SCATTERING 9852 1451 127 SUM OF MT=51 to 78 AND 91. 9852 1451 128 9852 1451 129 MT=16,17 (N,2N), (N,3N) CROSS SECTIONS 9852 1451 130 STAPRE RESULTS CALCULATED BY KONSHIN /11/ were adopted. 9852 1451 131 9852 1451 132 MT=18 FISSION CROSS SECTION 9852 1451 133 DATA WERE TAKEN FROM JENDL-3.2 WHICH WAS EVALUATED ON THE 9852 1451 134 BASIS OF THE MEASURED DATA BY DABBS+ /5/, SILBERT/12/ 9852 1451 135 AND KUPRIYANOV+ /13/. 9852 1451 136 9852 1451 137 MT=51, 52, 55 9852 1451 138 CALCULATED WITH ECIS /14/ AND CASTHY /7/ CODES. 9852 1451 139 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /15/ 9852 1451 140 WERE USED. 9852 1451 141 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9852 1451 142 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9852 1451 143 = 9.52 - 9*((N-Z)/A) (MEV) 10 =