Retrieved by E4-util: 2010/02/01,11:45:39 1 0 0 0 9.624900+4 2.469360+2 1 1 59 09649 1451 1 0.000000+0 0.000000+0 0 0 0 69649 1451 2 1.000000+0 2.000000+7 3 0 10 09649 1451 3 0.000000+0 0.000000+0 0 0 228 619649 1451 4 96-Cm-249 IPPE EVAL-SEP06 MANOKHIN V.N. 9649 1451 5 DIST-DEC06 9649 1451 6 ----RUSFOND MATERIAL 9649 9649 1451 7 -----INCIDENT NEUTRON DATA 9649 1451 8 ------ENDF-6 FORMAT 9649 1451 9 9649 1451 10 RUSFOND DESCRIPTION 9649 1451 11 (See RUSFOND manual for details) 9649 1451 12 9649 1451 13 Data are compiled by the next manner 9649 1451 14 9649 1451 15 1. Data from ENDF/B-VII are adopted. 9649 1451 16 2. MF1 Mt455 was added from JEFF-3.1 (8 groups of dn) 9649 1451 17 3. MF5 MT455 was added the same as for Cm-245 9649 1451 18 **************************************************************** 9649 1451 19 ENDF/B-VII description 9649 1451 20 **************************************************************** 9649 1451 21 9649 1451 22 Revision by R. Q. Wright, JANUARY 6, 2006 9649 1451 23 9649 1451 24 Levels in MF = 2, MT = 151 are changed. 9649 1451 25 9649 1451 26 2200-m/s cross sections and resonance integrals 9649 1451 27 2200 m/s value Res. Int. 9649 1451 28 Total 21.28 b - 9649 1451 29 Elastic 9.28 b - 9649 1451 30 Fission 10.25 b 134 b 9649 1451 31 Capture 1.75 b 59.1 b 9649 1451 32 9649 1451 33 ---------------------------------------------------------------- 9649 1451 34 9649 1451 35 The upper limit of the RRR = 150 eV. 9649 1451 36 Evaluation was MLBW but had illegal J values. 9649 1451 37 Cm249 has I = 1/2; for L = 0, J = 1 or 0 are allowed. 9649 1451 38 The original evaluation used J = 1/2 which is incorrect and is 9649 1451 39 not allowed for MLBW. 9649 1451 40 Values of J = 1 or 0 were assigned by RQW. 9649 1451 41 The energy of the bound level was changed from -3.0 eV to 9649 1451 42 -3.3 eV. In addition, the capture widths of the bound level 9649 1451 43 and the 15.0 eV level were increased. 9649 1451 44 The changes result in the 2200-m/s cross sections and resonance 9649 1451 45 integrals shown above, which are very close to the values in 9649 1451 46 the original evaluation. 9649 1451 47 9649 1451 48 **************************************************************** 9649 1451 49 9649 1451 50 HISTORY 9649 1451 51 84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9649 1451 52 T.NAKAGAWA (JAERI) /1/. 9649 1451 53 92-09 JENDL-3.2 9649 1451 54 COMPILED BY T.NAKAGAWA 9649 1451 55 95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9649 1451 56 T.NAKAGAWA AND T.LIU. 9649 1451 57 00-04 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA 9649 1451 58 9649 1451 59 ***** Modified parts from JENDL-3.2 ******************* 9649 1451 60 ALL DATA OF MF'S= 2, 3, 4 AND 5 9649 1451 61 ******************************************************* 9649 1451 62 9649 1451 63 9649 1451 64 MF=1 GENERAL INFORMATION 9649 1451 65 MT=451 COMMENTS AND DICTIONARY 9649 1451 66 MT=452 NUMBER OF NEUTRONS PER FISSION 9649 1451 67 SUM OF MT'S =455 AND 456. 9649 1451 68 MT=455 DELAYED NEUTRON DATA 9649 1451 69 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9649 1451 70 MT=456 Number of prompt neutrons per fission 9649 1451 71 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9649 1451 72 9649 1451 73 MF=2,MT=151 RESONANCE PARAMETERS 9649 1451 74 RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 EV TO 150 EV 9649 1451 75 HYPOTHETICAL RESONANCE LEVELS WERE GENERATED, AND THEIR 9649 1451 76 PARAMETERS WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS9649 1451 77 Level spacing = 20.0 eV, capture width = 0.04 eV, 9649 1451 78 S-0 = 1.0E-4, R = 9.23 FM. ratio of neutron and 9649 1451 79 fission width = 0.4 9649 1451 80 PARAMETERS OF THE FIRST POSITIVE LEVEL WERE ADJUSTED SO AS TO 9649 1451 81 REPRODUCE THE THERMAL CROSS SECTIONS. 9649 1451 82 Capture (Maxwell av.) = 1.6 b /4/ 9649 1451 83 Fission = about 10 b estimated from 9649 1451 84 systematics. 9649 1451 85 9649 1451 86 UNRESOLVED RESONANCES (150 EV TO 25 KEV) 9649 1451 87 D-0=20 EV, RADIATIVE WIDTH = 0.0400 EV, 9649 1451 88 Fission width = energy dependent parameters obtained with 9649 1451 89 ASREP code /5/ so as to reproduce estimated fission cross 9649 1451 90 section. 9649 1451 91 Neutron strength functions = adjusted with ASREP /5/ to 9649 1451 92 toatl and capture cross sections calculated with CASTHY 9649 1451 93 code /6/. 9649 1451 94 9649 1451 95 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9649 1451 96 2200 M/S VALUE RES. INT. 9649 1451 97 TOTAL 20.75 B - 9649 1451 98 ELASTIC 8.76 B - 9649 1451 99 FISSION 10.23 B 166 B 9649 1451 100 CAPTURE 1.76 B 62.2 B 9649 1451 101 9649 1451 102 MF=3 NEUTRON CROSS SECTIONS 9649 1451 103 MT=1 TOTAL CROSS SECTION 9649 1451 104 CALCULATED WITH CASTHY CODE /6/ BASED ON THE SHERICAL 9649 1451 105 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./7/ WERE 9649 1451 106 USED. 9649 1451 107 9649 1451 108 V = 45.036-0.3*EN (MEV) 9649 1451 109 WS= 4.115+0.4*EN (MEV) 9649 1451 110 WV= 0 , VSO = 7.5 (MEV) 9649 1451 111 R = RSO = 1.256 , RS = 1.260 (FM) 9649 1451 112 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9649 1451 113 9649 1451 114 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9649 1451 115 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9649 1451 116 OF GILBERT-CAMERON'S FORMULA /8/ WERE USED. 9649 1451 117 9649 1451 118 ISOTOPE CM-249 CM-250 9649 1451 119 A(1/MEV) 32.0 30.00 9649 1451 120 SPIN-CUTOFF PARA. 32.69 31.74 9649 1451 121 PAIRING E(MEV) 0.720 1.585 9649 1451 122 TEMP. (MEV) 0.370 0.400 9649 1451 123 C(1/MEV) 11.680 1.635 9649 1451 124 EX(MEV) 3.8937 5.0821 9649 1451 125 9649 1451 126 THE LEVEL SCHEME TAKEN FROM REF. /9/. 9649 1451 127 NO. ENERGY(KEV) SPIN-PARITY 9649 1451 128 G.S. 0.0 1/2 + 9649 1451 129 1. 26.234 3/2 + 9649 1451 130 2. 48.203 5/2 + 9649 1451 131 3. 48.743 7/2 + 9649 1451 132 4. 109.0 9/2 + 9649 1451 133 5. 110.16 7/2 + 9649 1451 134 6. 146.0 9/2 + 9649 1451 135 7. 207.99 3/2 + 9649 1451 136 8. 220.0 9/2 + 9649 1451 137 9. 242.01 5/2 + 9649 1451 138 10. 288.99 7/2 + 9649 1451 139 11. 300.0 11/2 + 9649 1451 140 12. 350.0 9/2 + 9649 1451 141 13. 470.21 3/2 - 9649 1451 142 14. 494.49 1/2 - 9649 1451 143 15. 498.0 7/2 - 9649 1451 144 16. 529.61 5/2 + 9649 1451 145 17. 546.86 5/2 - 9649 1451 146 18. 578.43 7/2 + 9649 1451 147 19. 634.0 9/2 + 9649 1451 148 CONTINUUM LEVELS ASSUMED ABOVE 688 KEV. 9649 1451 149 9649 1451 150 MT= 2 ELASTIC SCATTERING 9649 1451 151 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9649 1451 152 9649 1451 153 MT= 4 TOTAL INELASTIC SCATTERING 9649 1451 154 SUM OF MT=51 to 69 AND 91. 9649 1451 155 9649 1451 156 MT=16,17 (N,2N) and (N,3N) 9649 1451 157 STAPRE RESULTS CALCULATED BY KONSHIN /10/ were adopted. 9649 1451 158 9649 1451 159 MT=18 FISSION CROSS SECTION 9649 1451 160 Above 250 keV, Konshin's calculation/10/ was adopted. 9649 1451 161 Below 250 keV, roughly estimated to connect to the 9649 1451 162 average cross section the resolved resonance region. 9649 1451 163 9649 1451 164 MT=51, 52, 53, 54 Inelastic scattering 9649 1451 165 CALCULATED WITH ECIS /11/ AND CASTHY /6/ CODES. 9649 1451 166 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /12/ WERE9649 1451 167 USED for the ECIS calculation. 9649 1451 168 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9649 1451 169 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9649 1451 170 = 9.52 - 9*((N-Z)/A) (MEV) 10 =