JEFF-3.1.1 General purpose neutron file update release Jan. 2009 2311 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 1 0 10 319652 1451 3 0.000000+0 0.000000+0 0 0 198 609652 1451 4 96-Cm-249 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU 9652 1451 5 DIST-JAN09 20090105 9652 1451 6 ----JEFF-311 MATERIAL 9652 9652 1451 7 -----INCIDENT NEUTRON DATA 9652 1451 8 ------ENDF-6 FORMAT 9652 1451 9 *************************** JEFF-3.1.1 *************************9652 1451 10 ** **9652 1451 11 ** Original data taken from: JEFF-3.1 **9652 1451 12 ** **9652 1451 13 ******************************************************************9652 1451 14 ***************************** JEFF-3.1 *************************9652 1451 15 ** **9652 1451 16 ** Original data taken from: JENDL-3.3 **9652 1451 17 ** **9652 1451 18 ******************************************************************9652 1451 19 9652 1451 20 HISTORY 9652 1451 21 84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9652 1451 22 T.NAKAGAWA (JAERI) /1/. 9652 1451 23 92-09 JENDL-3.2 9652 1451 24 COMPILED BY T.NAKAGAWA 9652 1451 25 95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9652 1451 26 T.NAKAGAWA AND T.LIU. 9652 1451 27 00-04 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA 9652 1451 28 9652 1451 29 ***** Modified parts from JENDL-3.2 ******************* 9652 1451 30 ALL DATA OF MF'S= 2, 3, 4 AND 5 9652 1451 31 ******************************************************* 9652 1451 32 9652 1451 33 9652 1451 34 MF=1 GENERAL INFORMATION 9652 1451 35 MT=451 COMMENTS AND DICTIONARY 9652 1451 36 MT=452 NUMBER OF NEUTRONS PER FISSION 9652 1451 37 SUM OF MT'S =455 AND 456. 9652 1451 38 MT=455 DELAYED NEUTRON DATA 9652 1451 39 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9652 1451 40 MT=456 Number of prompt neutrons per fission 9652 1451 41 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9652 1451 42 9652 1451 43 MF=2,MT=151 RESONANCE PARAMETERS 9652 1451 44 RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 EV TO 150 EV 9652 1451 45 HYPOTHETICAL RESONANCE LEVELS WERE GENERATED, AND THEIR 9652 1451 46 PARAMETERS WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS9652 1451 47 Level spacing = 20.0 eV, capture width = 0.04 eV, 9652 1451 48 S-0 = 1.0E-4, R = 9.23 FM. ratio of neutron and 9652 1451 49 fission width = 0.4 9652 1451 50 PARAMETERS OF THE FIRST POSITIVE LEVEL WERE ADJUSTED SO AS TO 9652 1451 51 REPRODUCE THE THERMAL CROSS SECTIONS. 9652 1451 52 Capture (Maxwell av.) = 1.6 b /4/ 9652 1451 53 Fission = about 10 b estimated from 9652 1451 54 systematics. 9652 1451 55 9652 1451 56 UNRESOLVED RESONANCES (150 EV TO 25 KEV) 9652 1451 57 D-0=20 EV, RADIATIVE WIDTH = 0.0400 EV, 9652 1451 58 Fission width = energy dependent parameters obtained with 9652 1451 59 ASREP code /5/ so as to reproduce estimated fission cross 9652 1451 60 section. 9652 1451 61 Neutron strength functions = adjusted with ASREP /5/ to 9652 1451 62 toatl and capture cross sections calculated with CASTHY 9652 1451 63 code /6/. 9652 1451 64 9652 1451 65 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9652 1451 66 2200 M/S VALUE RES. INT. 9652 1451 67 TOTAL 20.75 B - 9652 1451 68 ELASTIC 8.76 B - 9652 1451 69 FISSION 10.23 B 166 B 9652 1451 70 CAPTURE 1.76 B 62.2 B 9652 1451 71 9652 1451 72 MF=3 NEUTRON CROSS SECTIONS 9652 1451 73 MT=1 TOTAL CROSS SECTION 9652 1451 74 CALCULATED WITH CASTHY CODE /6/ BASED ON THE SHERICAL 9652 1451 75 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./7/ WERE 9652 1451 76 USED. 9652 1451 77 9652 1451 78 V = 45.036-0.3*EN (MEV) 9652 1451 79 WS= 4.115+0.4*EN (MEV) 9652 1451 80 WV= 0 , VSO = 7.5 (MEV) 9652 1451 81 R = RSO = 1.256 , RS = 1.260 (FM) 9652 1451 82 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9652 1451 83 9652 1451 84 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9652 1451 85 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9652 1451 86 OF GILBERT-CAMERON'S FORMULA /8/ WERE USED. 9652 1451 87 9652 1451 88 ISOTOPE CM-249 CM-250 9652 1451 89 A(1/MEV) 32.0 30.00 9652 1451 90 SPIN-CUTOFF PARA. 32.69 31.74 9652 1451 91 PAIRING E(MEV) 0.720 1.585 9652 1451 92 TEMP. (MEV) 0.370 0.400 9652 1451 93 C(1/MEV) 11.680 1.635 9652 1451 94 EX(MEV) 3.8937 5.0821 9652 1451 95 9652 1451 96 THE LEVEL SCHEME TAKEN FROM REF. /9/. 9652 1451 97 NO. ENERGY(KEV) SPIN-PARITY 9652 1451 98 G.S. 0.0 1/2 + 9652 1451 99 1. 26.234 3/2 + 9652 1451 100 2. 48.203 5/2 + 9652 1451 101 3. 48.743 7/2 + 9652 1451 102 4. 109.0 9/2 + 9652 1451 103 5. 110.16 7/2 + 9652 1451 104 6. 146.0 9/2 + 9652 1451 105 7. 207.99 3/2 + 9652 1451 106 8. 220.0 9/2 + 9652 1451 107 9. 242.01 5/2 + 9652 1451 108 10. 288.99 7/2 + 9652 1451 109 11. 300.0 11/2 + 9652 1451 110 12. 350.0 9/2 + 9652 1451 111 13. 470.21 3/2 - 9652 1451 112 14. 494.49 1/2 - 9652 1451 113 15. 498.0 7/2 - 9652 1451 114 16. 529.61 5/2 + 9652 1451 115 17. 546.86 5/2 - 9652 1451 116 18. 578.43 7/2 + 9652 1451 117 19. 634.0 9/2 + 9652 1451 118 CONTINUUM LEVELS ASSUMED ABOVE 688 KEV. 9652 1451 119 9652 1451 120 MT= 2 ELASTIC SCATTERING 9652 1451 121 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9652 1451 122 9652 1451 123 MT= 4 TOTAL INELASTIC SCATTERING 9652 1451 124 SUM OF MT=51 to 69 AND 91. 9652 1451 125 9652 1451 126 MT=16,17 (N,2N) and (N,3N) 9652 1451 127 STAPRE RESULTS CALCULATED BY KONSHIN /10/ were adopted. 9652 1451 128 9652 1451 129 MT=18 FISSION CROSS SECTION 9652 1451 130 Above 250 keV, Konshin's calculation/10/ was adopted. 9652 1451 131 Below 250 keV, roughly estimated to connect to the 9652 1451 132 average cross section the resolved resonance region. 9652 1451 133 9652 1451 134 MT=51, 52, 53, 54 Inelastic scattering 9652 1451 135 CALCULATED WITH ECIS /11/ AND CASTHY /6/ CODES. 9652 1451 136 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /12/ WERE9652 1451 137 USED for the ECIS calculation. 9652 1451 138 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9652 1451 139 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9652 1451 140 = 9.52 - 9*((N-Z)/A) (MEV) 10 =