JENDL-3.3 Cm249 pointwise at 300K 0 0 9.624900+4 2.469360+2 2 1 0 39652 1451 1 0.000000+0 0.000000+0 0 0 0 69652 1451 2 1.000000+0 2.000000+7 0 0 10 39652 1451 3 3.000000+2 0.000000+0 1 0 198 609652 1451 4 96-CM-249 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU 9652 1451 5 DIST-MAR02 REV3-DEC00 20001213 9652 1451 6 ----JENDL-3.3 MATERIAL 9652 9652 1451 7 -----INCIDENT NEUTRON DATA 9652 1451 8 ------ENDF-6 FORMAT 9652 1451 9 9652 1451 10 HISTORY 9652 1451 11 84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9652 1451 12 T.NAKAGAWA (JAERI) /1/. 9652 1451 13 92-09 JENDL-3.2 9652 1451 14 COMPILED BY T.NAKAGAWA 9652 1451 15 95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9652 1451 16 T.NAKAGAWA AND T.LIU. 9652 1451 17 00-04 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA 9652 1451 18 9652 1451 19 ***** Modified parts from JENDL-3.2 ******************* 9652 1451 20 ALL DATA OF MF'S= 2, 3, 4 AND 5 9652 1451 21 ******************************************************* 9652 1451 22 9652 1451 23 9652 1451 24 MF=1 GENERAL INFORMATION 9652 1451 25 MT=451 COMMENTS AND DICTIONARY 9652 1451 26 MT=452 NUMBER OF NEUTRONS PER FISSION 9652 1451 27 SUM OF MT'S =455 AND 456. 9652 1451 28 MT=455 DELAYED NEUTRON DATA 9652 1451 29 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9652 1451 30 MT=456 Number of prompt neutrons per fission 9652 1451 31 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9652 1451 32 9652 1451 33 MF=2,MT=151 RESONANCE PARAMETERS 9652 1451 34 RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 EV TO 150 EV 9652 1451 35 HYPOTHETICAL RESONANCE LEVELS WERE GENERATED, AND THEIR 9652 1451 36 PARAMETERS WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS9652 1451 37 Level spacing = 20.0 eV, capture width = 0.04 eV, 9652 1451 38 S-0 = 1.0E-4, R = 9.23 FM. ratio of neutron and 9652 1451 39 fission width = 0.4 9652 1451 40 PARAMETERS OF THE FIRST POSITIVE LEVEL WERE ADJUSTED SO AS TO 9652 1451 41 REPRODUCE THE THERMAL CROSS SECTIONS. 9652 1451 42 Capture (Maxwell av.) = 1.6 b /4/ 9652 1451 43 Fission = about 10 b estimated from 9652 1451 44 systematics. 9652 1451 45 9652 1451 46 UNRESOLVED RESONANCES (150 EV TO 25 KEV) 9652 1451 47 D-0=20 EV, RADIATIVE WIDTH = 0.0400 EV, 9652 1451 48 Fission width = energy dependent parameters obtained with 9652 1451 49 ASREP code /5/ so as to reproduce estimated fission cross 9652 1451 50 section. 9652 1451 51 Neutron strength functions = adjusted with ASREP /5/ to 9652 1451 52 toatl and capture cross sections calculated with CASTHY 9652 1451 53 code /6/. 9652 1451 54 9652 1451 55 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9652 1451 56 2200 M/S VALUE RES. INT. 9652 1451 57 TOTAL 20.75 B - 9652 1451 58 ELASTIC 8.76 B - 9652 1451 59 FISSION 10.23 B 166 B 9652 1451 60 CAPTURE 1.76 B 62.2 B 9652 1451 61 9652 1451 62 MF=3 NEUTRON CROSS SECTIONS 9652 1451 63 MT=1 TOTAL CROSS SECTION 9652 1451 64 CALCULATED WITH CASTHY CODE /6/ BASED ON THE SHERICAL 9652 1451 65 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./7/ WERE 9652 1451 66 USED. 9652 1451 67 9652 1451 68 V = 45.036-0.3*EN (MEV) 9652 1451 69 WS= 4.115+0.4*EN (MEV) 9652 1451 70 WV= 0 , VSO = 7.5 (MEV) 9652 1451 71 R = RSO = 1.256 , RS = 1.260 (FM) 9652 1451 72 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9652 1451 73 9652 1451 74 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9652 1451 75 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9652 1451 76 OF GILBERT-CAMERON'S FORMULA /8/ WERE USED. 9652 1451 77 9652 1451 78 ISOTOPE CM-249 CM-250 9652 1451 79 A(1/MEV) 32.0 30.00 9652 1451 80 SPIN-CUTOFF PARA. 32.69 31.74 9652 1451 81 PAIRING E(MEV) 0.720 1.585 9652 1451 82 TEMP. (MEV) 0.370 0.400 9652 1451 83 C(1/MEV) 11.680 1.635 9652 1451 84 EX(MEV) 3.8937 5.0821 9652 1451 85 9652 1451 86 THE LEVEL SCHEME TAKEN FROM REF. /9/. 9652 1451 87 NO. ENERGY(KEV) SPIN-PARITY 9652 1451 88 G.S. 0.0 1/2 + 9652 1451 89 1. 26.234 3/2 + 9652 1451 90 2. 48.203 5/2 + 9652 1451 91 3. 48.743 7/2 + 9652 1451 92 4. 109.0 9/2 + 9652 1451 93 5. 110.16 7/2 + 9652 1451 94 6. 146.0 9/2 + 9652 1451 95 7. 207.99 3/2 + 9652 1451 96 8. 220.0 9/2 + 9652 1451 97 9. 242.01 5/2 + 9652 1451 98 10. 288.99 7/2 + 9652 1451 99 11. 300.0 11/2 + 9652 1451 100 12. 350.0 9/2 + 9652 1451 101 13. 470.21 3/2 - 9652 1451 102 14. 494.49 1/2 - 9652 1451 103 15. 498.0 7/2 - 9652 1451 104 16. 529.61 5/2 + 9652 1451 105 17. 546.86 5/2 - 9652 1451 106 18. 578.43 7/2 + 9652 1451 107 19. 634.0 9/2 + 9652 1451 108 CONTINUUM LEVELS ASSUMED ABOVE 688 KEV. 9652 1451 109 9652 1451 110 MT= 2 ELASTIC SCATTERING 9652 1451 111 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9652 1451 112 9652 1451 113 MT= 4 TOTAL INELASTIC SCATTERING 9652 1451 114 SUM OF MT=51 to 69 AND 91. 9652 1451 115 9652 1451 116 MT=16,17 (N,2N) and (N,3N) 9652 1451 117 STAPRE RESULTS CALCULATED BY KONSHIN /10/ were adopted. 9652 1451 118 9652 1451 119 MT=18 FISSION CROSS SECTION 9652 1451 120 Above 250 keV, Konshin's calculation/10/ was adopted. 9652 1451 121 Below 250 keV, roughly estimated to connect to the 9652 1451 122 average cross section the resolved resonance region. 9652 1451 123 9652 1451 124 MT=51, 52, 53, 54 Inelastic scattering 9652 1451 125 CALCULATED WITH ECIS /11/ AND CASTHY /6/ CODES. 9652 1451 126 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /12/ WERE9652 1451 127 USED for the ECIS calculation. 9652 1451 128 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9652 1451 129 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9652 1451 130 = 9.52 - 9*((N-Z)/A) (MEV) 10 =