JEFF-3.1.2 general purpose neutron file update released Oct.2011 1 0 0 0 9.624900+4 2.469360+2 1 1 2 39652 1451 1 0.000000+0 0.000000+0 0 0 0 69652 1451 2 1.000000+0 2.000000+7 2 0 10 319652 1451 3 0.000000+0 0.000000+0 0 0 203 609652 1451 4 96-Cm-249 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU 9652 1451 5 DIST-JAN09 20090105 9652 1451 6 ----JEF-31 MATERIAL 9652 9652 1451 7 -----INCIDENT NEUTRON DATA 9652 1451 8 ------ENDF-6 FORMAT 9652 1451 9 ***************************** JEFF-3.1.2 ************************9652 1451 10 ** **9652 1451 11 ** Original data taken from: JEFF-3.1.1 **9652 1451 12 ** **9652 1451 13 ******************************************************************9652 1451 14 *************************** JEFF-3.1.1 *************************9652 1451 15 ** **9652 1451 16 ** Original data taken from: JEFF-3.1 **9652 1451 17 ** **9652 1451 18 ******************************************************************9652 1451 19 ***************************** JEFF-3.1 *************************9652 1451 20 ** **9652 1451 21 ** Original data taken from: JENDL-3.3 **9652 1451 22 ** **9652 1451 23 ******************************************************************9652 1451 24 9652 1451 25 HISTORY 9652 1451 26 84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9652 1451 27 T.NAKAGAWA (JAERI) /1/. 9652 1451 28 92-09 JENDL-3.2 9652 1451 29 COMPILED BY T.NAKAGAWA 9652 1451 30 95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9652 1451 31 T.NAKAGAWA AND T.LIU. 9652 1451 32 00-04 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA 9652 1451 33 9652 1451 34 ***** Modified parts from JENDL-3.2 ******************* 9652 1451 35 ALL DATA OF MF'S= 2, 3, 4 AND 5 9652 1451 36 ******************************************************* 9652 1451 37 9652 1451 38 9652 1451 39 MF=1 GENERAL INFORMATION 9652 1451 40 MT=451 COMMENTS AND DICTIONARY 9652 1451 41 MT=452 NUMBER OF NEUTRONS PER FISSION 9652 1451 42 SUM OF MT'S =455 AND 456. 9652 1451 43 MT=455 DELAYED NEUTRON DATA 9652 1451 44 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9652 1451 45 MT=456 Number of prompt neutrons per fission 9652 1451 46 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9652 1451 47 9652 1451 48 MF=2,MT=151 RESONANCE PARAMETERS 9652 1451 49 RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 EV TO 150 EV 9652 1451 50 HYPOTHETICAL RESONANCE LEVELS WERE GENERATED, AND THEIR 9652 1451 51 PARAMETERS WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS9652 1451 52 Level spacing = 20.0 eV, capture width = 0.04 eV, 9652 1451 53 S-0 = 1.0E-4, R = 9.23 FM. ratio of neutron and 9652 1451 54 fission width = 0.4 9652 1451 55 PARAMETERS OF THE FIRST POSITIVE LEVEL WERE ADJUSTED SO AS TO 9652 1451 56 REPRODUCE THE THERMAL CROSS SECTIONS. 9652 1451 57 Capture (Maxwell av.) = 1.6 b /4/ 9652 1451 58 Fission = about 10 b estimated from 9652 1451 59 systematics. 9652 1451 60 9652 1451 61 UNRESOLVED RESONANCES (150 EV TO 25 KEV) 9652 1451 62 D-0=20 EV, RADIATIVE WIDTH = 0.0400 EV, 9652 1451 63 Fission width = energy dependent parameters obtained with 9652 1451 64 ASREP code /5/ so as to reproduce estimated fission cross 9652 1451 65 section. 9652 1451 66 Neutron strength functions = adjusted with ASREP /5/ to 9652 1451 67 toatl and capture cross sections calculated with CASTHY 9652 1451 68 code /6/. 9652 1451 69 9652 1451 70 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9652 1451 71 2200 M/S VALUE RES. INT. 9652 1451 72 TOTAL 20.75 B - 9652 1451 73 ELASTIC 8.76 B - 9652 1451 74 FISSION 10.23 B 166 B 9652 1451 75 CAPTURE 1.76 B 62.2 B 9652 1451 76 9652 1451 77 MF=3 NEUTRON CROSS SECTIONS 9652 1451 78 MT=1 TOTAL CROSS SECTION 9652 1451 79 CALCULATED WITH CASTHY CODE /6/ BASED ON THE SHERICAL 9652 1451 80 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./7/ WERE 9652 1451 81 USED. 9652 1451 82 9652 1451 83 V = 45.036-0.3*EN (MEV) 9652 1451 84 WS= 4.115+0.4*EN (MEV) 9652 1451 85 WV= 0 , VSO = 7.5 (MEV) 9652 1451 86 R = RSO = 1.256 , RS = 1.260 (FM) 9652 1451 87 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9652 1451 88 9652 1451 89 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9652 1451 90 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9652 1451 91 OF GILBERT-CAMERON'S FORMULA /8/ WERE USED. 9652 1451 92 9652 1451 93 ISOTOPE CM-249 CM-250 9652 1451 94 A(1/MEV) 32.0 30.00 9652 1451 95 SPIN-CUTOFF PARA. 32.69 31.74 9652 1451 96 PAIRING E(MEV) 0.720 1.585 9652 1451 97 TEMP. (MEV) 0.370 0.400 9652 1451 98 C(1/MEV) 11.680 1.635 9652 1451 99 EX(MEV) 3.8937 5.0821 9652 1451 100 9652 1451 101 THE LEVEL SCHEME TAKEN FROM REF. /9/. 9652 1451 102 NO. ENERGY(KEV) SPIN-PARITY 9652 1451 103 G.S. 0.0 1/2 + 9652 1451 104 1. 26.234 3/2 + 9652 1451 105 2. 48.203 5/2 + 9652 1451 106 3. 48.743 7/2 + 9652 1451 107 4. 109.0 9/2 + 9652 1451 108 5. 110.16 7/2 + 9652 1451 109 6. 146.0 9/2 + 9652 1451 110 7. 207.99 3/2 + 9652 1451 111 8. 220.0 9/2 + 9652 1451 112 9. 242.01 5/2 + 9652 1451 113 10. 288.99 7/2 + 9652 1451 114 11. 300.0 11/2 + 9652 1451 115 12. 350.0 9/2 + 9652 1451 116 13. 470.21 3/2 - 9652 1451 117 14. 494.49 1/2 - 9652 1451 118 15. 498.0 7/2 - 9652 1451 119 16. 529.61 5/2 + 9652 1451 120 17. 546.86 5/2 - 9652 1451 121 18. 578.43 7/2 + 9652 1451 122 19. 634.0 9/2 + 9652 1451 123 CONTINUUM LEVELS ASSUMED ABOVE 688 KEV. 9652 1451 124 9652 1451 125 MT= 2 ELASTIC SCATTERING 9652 1451 126 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9652 1451 127 9652 1451 128 MT= 4 TOTAL INELASTIC SCATTERING 9652 1451 129 SUM OF MT=51 to 69 AND 91. 9652 1451 130 9652 1451 131 MT=16,17 (N,2N) and (N,3N) 9652 1451 132 STAPRE RESULTS CALCULATED BY KONSHIN /10/ were adopted. 9652 1451 133 9652 1451 134 MT=18 FISSION CROSS SECTION 9652 1451 135 Above 250 keV, Konshin's calculation/10/ was adopted. 9652 1451 136 Below 250 keV, roughly estimated to connect to the 9652 1451 137 average cross section the resolved resonance region. 9652 1451 138 9652 1451 139 MT=51, 52, 53, 54 Inelastic scattering 9652 1451 140 CALCULATED WITH ECIS /11/ AND CASTHY /6/ CODES. 9652 1451 141 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /12/ WERE9652 1451 142 USED for the ECIS calculation. 9652 1451 143 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9652 1451 144 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9652 1451 145 = 9.52 - 9*((N-Z)/A) (MEV) 10 =