JEFF-3.2 Release - Neutron File March 2014 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 1 0 10 329852 1451 3 0.000000+0 0.000000+0 0 0 213 799852 1451 4 98-Cf-249 JAERI EVAL-JUL95 T.NAKAGAWA AND T.LIU 9852 1451 5 DIST-JAN09 20090105 9852 1451 6 ----JEFF32 MATERIAL 9852 REVISION 2 9852 1451 7 -----INCIDENT NEUTRON DATA 9852 1451 8 ------ENDF-6 FORMAT 9852 1451 9 ***************************** JEFF-3.2 ***********************9852 1451 10 ** **9852 1451 11 ** Original data taken from: JEFF-3.1.1 **9852 1451 12 ** **9852 1451 13 ******************************************************************9852 1451 14 *************************** JEFF-3.1.1 *************************9852 1451 15 ** **9852 1451 16 ** Original data taken from: JEFF-3.1 **9852 1451 17 ** **9852 1451 18 ******************************************************************9852 1451 19 ***************************** JEFF-3.1 *************************9852 1451 20 ** **9852 1451 21 ** Original data taken from: JENDL-3.3 **9852 1451 22 ** **9852 1451 23 ******************************************************************9852 1451 24 9852 1451 25 05-01 NEA/OECD (Rugama) 8 delayed neutron groups 9852 1451 26 Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002) 9852 1451 27 9852 1451 28 HISTORY 9852 1451 29 85-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9852 1451 30 T.NAKAGAWA (JAERI). DETAILS ARE GIVEN IN REF. /1/. 9852 1451 31 95-07 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU. 9852 1451 32 00-05 MODIFICATION AND COMPILATION WERE MADE BY T.NAKAGAWA 9852 1451 33 9852 1451 34 ***** Modified parts from JENDL-3.2 ******************* 9852 1451 35 MF=2 Scattering radius in the unresolved resonance 9852 1451 36 region. 9852 1451 37 ALL DATA OF MF'S = 3, 4 AND 5. 9852 1451 38 ******************************************************* 9852 1451 39 9852 1451 40 9852 1451 41 MF=1 GENERAL INFORMATION 9852 1451 42 MT=451 COMMENTS AND DICTIONARY 9852 1451 43 MT=452 NUMBER OF NEUTRONS PER FISSION 9852 1451 44 SUM OF MT'S = 455 AND 456. 9852 1451 45 MT=455 DELAYED NEUTRON DATA 9852 1451 46 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9852 1451 47 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9852 1451 48 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9852 1451 49 9852 1451 50 MF=2,MT=151 RESONANCE PARAMETERS (TAKEN FROM JENDL-3.2) 9852 1451 51 RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 EV TO 70 EV 9852 1451 52 RESONANCE ENERGIES, NEUTRON AND FISSION WIDTHS WERE TAKEN 9852 1451 53 FROM THE EXPERIMENTAL DATA OF BENJAMIN+ /4/. THE RADIATIVE 9852 1451 54 WIDTH WAS ASSUMED TO BE 0.04 EV ACCORDING TO DABBS+ /5/. 9852 1451 55 A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL 9852 1451 56 CROSS SECTIONS. NO BACKGROUND CORRECTION WAS APPLIED. 9852 1451 57 9852 1451 58 UNRESOLVED RESONANCES : 70 EV - 30 KEV 9852 1451 59 OBTAINED FROM OPTICAL MODEL CALCULATION: 9852 1451 60 S1=3.15E-4, S2=0.83E-4. 9852 1451 61 ESTIMATED FROM RESOLVED RESONANCES: 9852 1451 62 DOBS=1.16 EV, GAM-G=40 MILLI-EV ,S0=1.06E-4 9852 1451 63 FISSION WIDTHS WERE ESTIMATED FROM THE CHANNEL THEORY OF 9852 1451 64 FISSION /6/. S0, S1 AND S2 VALUES WERE ADJUSTED SO AS TO 9852 1451 65 REPRODUCE THE FISSION CROSS SECTION MEASURED BY DABBS+ /5/. 9852 1451 66 Scattering radius of 8.85 fm was determined so as to give the 9852 1451 67 same ealstic scattering cross section above 30 keV. 9852 1451 68 9852 1451 69 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9852 1451 70 2200 M/S VALUE RES. INT. 9852 1451 71 TOTAL 2176.7 B - 9852 1451 72 ELASTIC 6.22 B - 9852 1451 73 FISSION 1666 B 2220 B 9852 1451 74 CAPTURE 504.5 B 695 B 9852 1451 75 9852 1451 76 MF=3 NEUTRON CROSS SECTIONS 9852 1451 77 MT=1 TOTAL CROSS SECTION 9852 1451 78 CALCULATED WITH CASTHY CODE /7/ BASED ON THE SHERICAL 9852 1451 79 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./8/ WERE 9852 1451 80 USED. 9852 1451 81 9852 1451 82 V = 45.036-0.3*EN (MEV) 9852 1451 83 WS= 4.115+0.4*EN (MEV) 9852 1451 84 WV= 0 , VSO = 7.5 (MEV) 9852 1451 85 R = RSO = 1.256 , RS = 1.260 (FM) 9852 1451 86 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9852 1451 87 9852 1451 88 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9852 1451 89 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9852 1451 90 OF GILBERT-CAMERON'S FORMULA /9/ WERE USED. 9852 1451 91 9852 1451 92 ISOTOPE CF-249 CF-250 9852 1451 93 A(1/MEV) 29.4 31.2 9852 1451 94 SPIN-CUTOFF FACT 31.33 32.36 9852 1451 95 PAIRING E(MEV) 0.77 1.673 9852 1451 96 TEMP.(MEV) 0.3693 0.4025 9852 1451 97 C(1/MEV) 4.644 2.111 9852 1451 98 EX(MEV) 3.562 5.423 9852 1451 99 9852 1451 100 THE LEVEL SCHEME TAKEN FROM REF. /10/. 9852 1451 101 NO. ENERGY(KEV) SPIN-PARITY 9852 1451 102 G.S. 0 9/2 - 9852 1451 103 1. 62.49 11/2 - 9852 1451 104 2. 136.2 13/2 - 9852 1451 105 3. 144.96 5/2 + 9852 1451 106 4. 187.94 7/2 + 9852 1451 107 5. 220.0 15/2 - 9852 1451 108 6. 243.07 9/2 + 9852 1451 109 7. 315.0 17/2 - 9852 1451 110 8. 315.1 11/2 + 9852 1451 111 9. 379.52 7/2 + 9852 1451 112 10. 384.0 13/2 + 9852 1451 113 11. 416.8 1/2 + 9852 1451 114 12. 425.0 19/2 - 9852 1451 115 13. 437.56 9/2 + 9852 1451 116 14. 440.0 3/2 + 9852 1451 117 15. 442.98 7/2 + 9852 1451 118 16. 460.0 5/2 + 9852 1451 119 17. 500.7 9/2 + 9852 1451 120 18. 550.0 1/2 + 9852 1451 121 19. 606.0 5/2 + 9852 1451 122 20. 668.0 13/2 - 9852 1451 123 21. 751.0 15/2 - 9852 1451 124 22. 813.20 5/2 - 9852 1451 125 23. 852.19 7/2 - 9852 1451 126 24. 902.5 9/2 - 9852 1451 127 25. 920.0 11/2 + 9852 1451 128 26. 962.0 11/2 - 9852 1451 129 27. 992.0 13/2 + 9852 1451 130 28. 1008.0 9/2 + 9852 1451 131 CONTINUUM LEVELS ASSUMED ABOVE 1031. KEV. 9852 1451 132 9852 1451 133 MT= 2 ELASTIC SCATTERING 9852 1451 134 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9852 1451 135 9852 1451 136 MT= 4 TOTAL INELASTIC SCATTERING 9852 1451 137 SUM OF MT=51 to 78 AND 91. 9852 1451 138 9852 1451 139 MT=16,17 (N,2N), (N,3N) CROSS SECTIONS 9852 1451 140 STAPRE RESULTS CALCULATED BY KONSHIN /11/ were adopted. 9852 1451 141 9852 1451 142 MT=18 FISSION CROSS SECTION 9852 1451 143 DATA WERE TAKEN FROM JENDL-3.2 WHICH WAS EVALUATED ON THE 9852 1451 144 BASIS OF THE MEASURED DATA BY DABBS+ /5/, SILBERT/12/ 9852 1451 145 AND KUPRIYANOV+ /13/. 9852 1451 146 9852 1451 147 MT=51, 52, 55 9852 1451 148 CALCULATED WITH ECIS /14/ AND CASTHY /7/ CODES. 9852 1451 149 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /15/ 9852 1451 150 WERE USED. 9852 1451 151 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9852 1451 152 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9852 1451 153 = 9.52 - 9*((N-Z)/A) (MEV) 10 =