96-Cm-249 ENDF/B-VII.0 Processed by Red Cullen using PREPRO2007. 1 0 0 0 96249.0000 246.936000 2 1 0 39652 1451 1 0.0 0.0 0 0 0 69652 1451 2 1.00000000 20000000.0 3 0 10 79652 1451 3 600.000000 0.0 1 0 265 619652 1451 4 96-Cm-249 JAERI EVAL-OCT95 T.Nakagawa and T.Liu 9652 1451 5 DIST-DEC06 REV3-DEC00 20001213 9652 1451 6 ----ENDF/B-VII MATERIAL 9652 REVISION 3 9652 1451 7 -----INCIDENT NEUTRON DATA 9652 1451 8 ------ENDF-6 FORMAT 9652 1451 9 9652 1451 10 **************************************************************** 9652 1451 11 9652 1451 12 Revision by R. Q. Wright, JANUARY 6, 2006 9652 1451 13 9652 1451 14 Levels in MF = 2, MT = 151 are changed. 9652 1451 15 9652 1451 16 2200-m/s cross sections and resonance integrals 9652 1451 17 2200 m/s value Res. Int. 9652 1451 18 Total 21.28 b - 9652 1451 19 Elastic 9.28 b - 9652 1451 20 Fission 10.25 b 134 b 9652 1451 21 Capture 1.75 b 59.1 b 9652 1451 22 9652 1451 23 ---------------------------------------------------------------- 9652 1451 24 9652 1451 25 The upper limit of the RRR = 150 eV. 9652 1451 26 Evaluation was MLBW but had illegal J values. 9652 1451 27 Cm249 has I = 1/2; for L = 0, J = 1 or 0 are allowed. 9652 1451 28 The original evaluation used J = 1/2 which is incorrect and is 9652 1451 29 not allowed for MLBW. 9652 1451 30 Values of J = 1 or 0 were assigned by RQW. 9652 1451 31 The energy of the bound level was changed from -3.0 eV to 9652 1451 32 -3.3 eV. In addition, the capture widths of the bound level 9652 1451 33 and the 15.0 eV level were increased. 9652 1451 34 The changes result in the 2200-m/s cross sections and resonance 9652 1451 35 integrals shown above, which are very close to the values in 9652 1451 36 the original evaluation. 9652 1451 37 9652 1451 38 **************************************************************** 9652 1451 39 9652 1451 40 HISTORY 9652 1451 41 84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9652 1451 42 T.NAKAGAWA (JAERI) /1/. 9652 1451 43 92-09 JENDL-3.2 9652 1451 44 COMPILED BY T.NAKAGAWA 9652 1451 45 95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9652 1451 46 T.NAKAGAWA AND T.LIU. 9652 1451 47 00-04 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA 9652 1451 48 9652 1451 49 ***** Modified parts from JENDL-3.2 ******************* 9652 1451 50 ALL DATA OF MF'S= 2, 3, 4 AND 5 9652 1451 51 ******************************************************* 9652 1451 52 9652 1451 53 9652 1451 54 MF=1 GENERAL INFORMATION 9652 1451 55 MT=451 COMMENTS AND DICTIONARY 9652 1451 56 MT=452 NUMBER OF NEUTRONS PER FISSION 9652 1451 57 SUM OF MT'S =455 AND 456. 9652 1451 58 MT=455 DELAYED NEUTRON DATA 9652 1451 59 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9652 1451 60 MT=456 Number of prompt neutrons per fission 9652 1451 61 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9652 1451 62 9652 1451 63 MF=2,MT=151 RESONANCE PARAMETERS 9652 1451 64 RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 EV TO 150 EV 9652 1451 65 HYPOTHETICAL RESONANCE LEVELS WERE GENERATED, AND THEIR 9652 1451 66 PARAMETERS WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS9652 1451 67 Level spacing = 20.0 eV, capture width = 0.04 eV, 9652 1451 68 S-0 = 1.0E-4, R = 9.23 FM. ratio of neutron and 9652 1451 69 fission width = 0.4 9652 1451 70 PARAMETERS OF THE FIRST POSITIVE LEVEL WERE ADJUSTED SO AS TO 9652 1451 71 REPRODUCE THE THERMAL CROSS SECTIONS. 9652 1451 72 Capture (Maxwell av.) = 1.6 b /4/ 9652 1451 73 Fission = about 10 b estimated from 9652 1451 74 systematics. 9652 1451 75 9652 1451 76 UNRESOLVED RESONANCES (150 EV TO 25 KEV) 9652 1451 77 D-0=20 EV, RADIATIVE WIDTH = 0.0400 EV, 9652 1451 78 Fission width = energy dependent parameters obtained with 9652 1451 79 ASREP code /5/ so as to reproduce estimated fission cross 9652 1451 80 section. 9652 1451 81 Neutron strength functions = adjusted with ASREP /5/ to 9652 1451 82 toatl and capture cross sections calculated with CASTHY 9652 1451 83 code /6/. 9652 1451 84 9652 1451 85 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9652 1451 86 2200 M/S VALUE RES. INT. 9652 1451 87 TOTAL 20.75 B - 9652 1451 88 ELASTIC 8.76 B - 9652 1451 89 FISSION 10.23 B 166 B 9652 1451 90 CAPTURE 1.76 B 62.2 B 9652 1451 91 9652 1451 92 MF=3 NEUTRON CROSS SECTIONS 9652 1451 93 MT=1 TOTAL CROSS SECTION 9652 1451 94 CALCULATED WITH CASTHY CODE /6/ BASED ON THE SHERICAL 9652 1451 95 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./7/ WERE 9652 1451 96 USED. 9652 1451 97 9652 1451 98 V = 45.036-0.3*EN (MEV) 9652 1451 99 WS= 4.115+0.4*EN (MEV) 9652 1451 100 WV= 0 , VSO = 7.5 (MEV) 9652 1451 101 R = RSO = 1.256 , RS = 1.260 (FM) 9652 1451 102 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9652 1451 103 9652 1451 104 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9652 1451 105 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9652 1451 106 OF GILBERT-CAMERON'S FORMULA /8/ WERE USED. 9652 1451 107 9652 1451 108 ISOTOPE CM-249 CM-250 9652 1451 109 A(1/MEV) 32.0 30.00 9652 1451 110 SPIN-CUTOFF PARA. 32.69 31.74 9652 1451 111 PAIRING E(MEV) 0.720 1.585 9652 1451 112 TEMP. (MEV) 0.370 0.400 9652 1451 113 C(1/MEV) 11.680 1.635 9652 1451 114 EX(MEV) 3.8937 5.0821 9652 1451 115 9652 1451 116 THE LEVEL SCHEME TAKEN FROM REF. /9/. 9652 1451 117 NO. ENERGY(KEV) SPIN-PARITY 9652 1451 118 G.S. 0.0 1/2 + 9652 1451 119 1. 26.234 3/2 + 9652 1451 120 2. 48.203 5/2 + 9652 1451 121 3. 48.743 7/2 + 9652 1451 122 4. 109.0 9/2 + 9652 1451 123 5. 110.16 7/2 + 9652 1451 124 6. 146.0 9/2 + 9652 1451 125 7. 207.99 3/2 + 9652 1451 126 8. 220.0 9/2 + 9652 1451 127 9. 242.01 5/2 + 9652 1451 128 10. 288.99 7/2 + 9652 1451 129 11. 300.0 11/2 + 9652 1451 130 12. 350.0 9/2 + 9652 1451 131 13. 470.21 3/2 - 9652 1451 132 14. 494.49 1/2 - 9652 1451 133 15. 498.0 7/2 - 9652 1451 134 16. 529.61 5/2 + 9652 1451 135 17. 546.86 5/2 - 9652 1451 136 18. 578.43 7/2 + 9652 1451 137 19. 634.0 9/2 + 9652 1451 138 CONTINUUM LEVELS ASSUMED ABOVE 688 KEV. 9652 1451 139 9652 1451 140 MT= 2 ELASTIC SCATTERING 9652 1451 141 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9652 1451 142 9652 1451 143 MT= 4 TOTAL INELASTIC SCATTERING 9652 1451 144 SUM OF MT=51 to 69 AND 91. 9652 1451 145 9652 1451 146 MT=16,17 (N,2N) and (N,3N) 9652 1451 147 STAPRE RESULTS CALCULATED BY KONSHIN /10/ were adopted. 9652 1451 148 9652 1451 149 MT=18 FISSION CROSS SECTION 9652 1451 150 Above 250 keV, Konshin's calculation/10/ was adopted. 9652 1451 151 Below 250 keV, roughly estimated to connect to the 9652 1451 152 average cross section the resolved resonance region. 9652 1451 153 9652 1451 154 MT=51, 52, 53, 54 Inelastic scattering 9652 1451 155 CALCULATED WITH ECIS /11/ AND CASTHY /6/ CODES. 9652 1451 156 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /12/ WERE9652 1451 157 USED for the ECIS calculation. 9652 1451 158 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9652 1451 159 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9652 1451 160 = 9.52 - 9*((N-Z)/A) (MEV) 10 =