96-Cm-247 ENDF/B-VII.0 Processed by Red Cullen using PREPRO2007. 1 0 0 0 96247.0000 244.948000 2 1 0 29646 1451 1 0.0 0.0 0 0 0 69646 1451 2 1.00000000 20000000.0 3 0 10 79646 1451 3 600.000000 0.0 1 0 261 359646 1451 4 96-Cm-247 JAERI-ORNL EVAL-OCT05 R.Q. Wright, T.Nakagawa, T.Liu 9646 1451 5 JAERI-ORNL DIST-DEC06 20051021 9646 1451 6 ----ENDF/B-VII MATERIAL 9646 9646 1451 7 -----INCIDENT NEUTRON DATA 9646 1451 8 ------ENDF-6 FORMAT 9646 1451 9 9646 1451 10 *************************************************************** 9646 1451 11 9646 1451 12 JENDL-3.3 Evaluation was revised for ENDF/B-VII, 10-21-2005 9646 1451 13 at ORNL by R. Q. Wright 9646 1451 14 The fission cross section, MF = 3, MT = 18 is revised between 9646 1451 15 30 keV and 20 MeV. The cross section is lower above 150 keV. 9646 1451 16 The revised cross section is in agreement with the measurements 9646 1451 17 of Ivanin[IV1997] and Fursov[FU1997]. The data of Fursov is 9646 1451 18 generally lower and has smaller error bars, compared to Ivanin. 9646 1451 19 The evaluation is closer to Fursov between 1 and 7 MeV and at 9646 1451 20 15 MeV. The elastic cross section was changed in order to keep 9646 1451 21 the total cross section unchanged from JENDL-3.3 9646 1451 22 9646 1451 23 REFERENCES: 9646 1451 24 IV1997 Ivanin, et al. Triest, 1, 664 (1997), EXFOR 41360 9646 1451 25 FU1997 Fursov, et al. Triest, 1, 488 (1997), EXFOR 41303 9646 1451 26 9646 1451 27 *************************************************************** 9646 1451 28 9646 1451 29 JENDL-3.3 comments follow- 9646 1451 30 HISTORY 9646 1451 31 83-03 EVALUATION WAS BY Y.KIKUCHI(JAERI)/1/. 9646 1451 32 89-03 RE-EVALUATION WAS MADE FOR JENDL-3 BY T.NAKAGAWA(JAERI)/2/ 9646 1451 33 95-10 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU/3/. 9646 1451 34 99-12 RECOMPILED BY T.NAKAGAWA. 9646 1451 35 THE FOLLOWING QUANTITIES ARE RE-EVALUATED AFTER JAERI- 9646 1451 36 RESEARCH 97-056: 9646 1451 37 MF=2 MT=151 9646 1451 38 MF=3 MT=102 DIRECT/SEMI-DIRECT MODIFIED. 9646 1451 39 MT=37 DELETED 9646 1451 40 MF=4 MT= 2 BELOW 600 KEV, REPLACED WITH CASTHY CALC. 9646 1451 41 MF=5 MT=16, 17, 18, 91 9646 1451 42 9646 1451 43 ***** Modified parts from JENDL-3.2 ******************* 9646 1451 44 MF=2 All data 9646 1451 45 MF=3 All data 9646 1451 46 MF=4 All data 9646 1451 47 MF=5 All data 9646 1451 48 ******************************************************* 9646 1451 49 9646 1451 50 9646 1451 51 MF=1 GENERAL INFORMATION 9646 1451 52 MT=451 COMMENTS AND DICTIONARY 9646 1451 53 MT=452 NUMBER OF NEUTRONS PER FISSION 9646 1451 54 SUM OF MT'S =455 AND 456. 9646 1451 55 MT=455 DELAYED NEUTRON DATA 9646 1451 56 SEMI-EMPIRICAL FORMULA BY TUTTLE /4/. 9646 1451 57 MT=456 PROMPT NEUTRON DATA 9646 1451 58 SEMI-EMPIRICAL FORMULA BY HOWERTON /5/. 9646 1451 59 9646 1451 60 MF=2,MT=151 RESONANCE PARAMETERS 9646 1451 61 RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 60 EV 9646 1451 62 EVALUATION WAS BASED ON THE EXPERIMENTAL DATA OF MOORE AND9646 1451 63 KEYWORTH/6/, BELANOVA ET AL./7/ AND DANON ET AL./8/ 9646 1451 64 PARAMETERS OF RESONANCES UP TO 21.2 EV WERE TAKEN FROM 9646 1451 65 DANON ET AL./8/ PARAMETERS OF -0.52-EV AND 1.23-EV 9646 1451 66 RESONANCES WERE ADJUSTED TO TO REPRODUCE THERMAL CROSS 9646 1451 67 SECTIONS AND RESONANCE INTEGRALS. 9646 1451 68 RADIATIVE WIDTHS = 0.040 EV WAS ASSUMED. 9646 1451 69 SCATTERING RADIUS = 9.14 FM. 9646 1451 70 9646 1451 71 UNRESOLVED RESONANCE REGION : 60 EV TO 30 KEV 9646 1451 72 PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/ 9646 1451 73 SO AS TO REPRODUCE THE FISSION CROSS SECTION OF DANON 9646 1451 74 ET AL./8/, AND THE TOTAL AND CAPTURE CROSS SECTIONS AT 9646 1451 75 30 KEV CALCULATED WITH OPTICAL AND STATISTICAL MODELS. 9646 1451 76 ENERGY INDEPENDENT PARAMETERS: 9646 1451 77 R=8.76 FM, WG=0.035 EV,. 9646 1451 78 SPIN DEPENDENT FISSION WIDTHS WERE ASSUMED. 9646 1451 79 9646 1451 80 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9646 1451 81 2200 M/SEC RES. INTEG. 9646 1451 82 TOTAL 176.1 B - 9646 1451 83 ELASTIC 7.95 B - 9646 1451 84 FISSION 111.3 B 1130 B 9646 1451 85 CAPTURE 56.9 B 574 B 9646 1451 86 9646 1451 87 THE THERMAL CROSS SECTION AND RESONANCE INTEGRAL OF FISSION 9646 1451 88 ARE IN GOOD AGREEMENT WITH 115+-8 B AND 1091+-80 B MEASURED 9646 1451 89 BY DANON ET AL./8/, RESPECTIVELY. 9646 1451 90 9646 1451 91 MF=3 NEUTRON CROSS SECTIONS 9646 1451 92 BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 9646 1451 93 PARAMETERS. 9646 1451 94 9646 1451 95 MT=1 TOTAL CROSS SECTION 9646 1451 96 CASTHY /10/ CALCULATION WAS ADOPTED. 9646 1451 97 9646 1451 98 CASTHY CALCULATION 9646 1451 99 ------------------ 9646 1451 100 9646 1451 101 SHERICAL OPTICAL POTENTIAL PARAMETERS /11/ 9646 1451 102 9646 1451 103 V = 45.036-0.3*EN (MEV) 9646 1451 104 WS= 4.115+0.4*EN (MEV) 9646 1451 105 WV= 0 , VSO = 7.5 (MEV) 9646 1451 106 R = RSO = 1.256 , RS = 1.260 (FM) 9646 1451 107 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9646 1451 108 9646 1451 109 STATISTICAL MODEL CALCULATION WITH CASTHY CODE WAS MADE 9646 1451 110 CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N), 9646 1451 111 (N,3N). 9646 1451 112 9646 1451 113 THE LEVEL DENSITY PARAMETERS OF GILBERT-CAMERON'S FORMULA 9646 1451 114 /12/ 9646 1451 115 ISOTOPE CM-247 CM-248 9646 1451 116 A(1/MEV) 29.3 31.0 9646 1451 117 SPIN-CUTOFF PARA. 31.11 32.09 9646 1451 118 PAIRING E(MEV) 0.72 1.623 9646 1451 119 TEMP. (MEV) 0.408 0.385 9646 1451 120 C(1/MEV) 13.967 1.2545 9646 1451 121 EX(MEV) 4.2678 4.9631 9646 1451 122 9646 1451 123 THE LEVEL SCHEME TAKEN FROM REF. /13/. 9646 1451 124 NO. ENERGY(KEV) SPIN-PARITY 9646 1451 125 G.S. 0.0 9/2 - 9646 1451 126 1 61.5 11/2 - 9646 1451 127 2 135.0 13/2 - 9646 1451 128 3 217.0 15/2 - 9646 1451 129 4 227.0 5/2 + 9646 1451 130 5 266.0 7/2 + 9646 1451 131 6 285.0 7/2 + 9646 1451 132 CONTINUUM LEVELS ASSUMED ABOVE 309 KEV. 9646 1451 133 9646 1451 134 MT=2 ELASTIC SCATTRING 9646 1451 135 CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS). 9646 1451 136 MT= 4 TOTAL INELASTIC SCATTERING 9646 1451 137 SUM OF MT=51-91. 9646 1451 138 MT=16,17 (N,2N),(N,3N) CROSS SECTION 9646 1451 139 STAPRE RESULTS CALCULATED BY KONSHIN /14/ WERE ADOPTED. 9646 1451 140 MT=18 FISSION CROSS SECTION 9646 1451 141 EVALUATED ON THE BASIS OF THE MEASURED DATA BY DANON ET 9646 1451 142 AL./15/ BELOW 80 KEV. ABOVE THIS ENERGY, THE DATA OF 9646 1451 143 FOMUSHKIN ET AL./16/ WERE ADOPTED. FROM 11 MEV TO 20 9646 1451 144 MEV, THE FISSION CROSS SECTION OF JENDL-3.2 WAS SLIGHTLY 9646 1451 145 ADJUSTED ACCORDING TO THE NEW EXPERIMENTAL DATA OF 9646 1451 146 FOMUSHKIN ET AL./17/. 9646 1451 147 MT=51, 52, 53 INELASTIC SCATTERING 9646 1451 148 CALCULATED WITH ECIS /18/ AND CASTHY /10/ CODES. 9646 1451 149 IN THE ECIS CALCULATION, CH.LAGRANGE'S DEFORMED OPTICAL 9646 1451 150 POTENTIAL PARAMETERS /19/ WERE USED. 9646 1451 151 9646 1451 152 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9646 1451 153 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) 0 =