JENDL-3.3 Cm247 pointwise at 0K 0 0 9.624700+4 2.449480+2 2 1 0 29646 1451 1 0.000000+0 0.000000+0 0 0 0 69646 1451 2 1.000000+0 2.000000+7 0 0 10 39646 1451 3 0.000000+0 0.000000+0 1 0 203 349646 1451 4 96-CM-247 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU 9646 1451 5 JAERI-RESEARCH 97-056 DIST-MAR02 REV2-OCT00 20001003 9646 1451 6 ----JENDL-3.3 MATERIAL 9646 9646 1451 7 -----INCIDENT NEUTRON DATA 9646 1451 8 ------ENDF-6 FORMAT 9646 1451 9 9646 1451 10 HISTORY 9646 1451 11 83-03 EVALUATION WAS BY Y.KIKUCHI(JAERI)/1/. 9646 1451 12 89-03 RE-EVALUATION WAS MADE FOR JENDL-3 BY T.NAKAGAWA(JAERI)/2/ 9646 1451 13 95-10 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU/3/. 9646 1451 14 99-12 RECOMPILED BY T.NAKAGAWA. 9646 1451 15 THE FOLLOWING QUANTITIES ARE RE-EVALUATED AFTER JAERI- 9646 1451 16 RESEARCH 97-056: 9646 1451 17 MF=2 MT=151 9646 1451 18 MF=3 MT=102 DIRECT/SEMI-DIRECT MODIFIED. 9646 1451 19 MT=37 DELETED 9646 1451 20 MF=4 MT= 2 BELOW 600 KEV, REPLACED WITH CASTHY CALC. 9646 1451 21 MF=5 MT=16, 17, 18, 91 9646 1451 22 9646 1451 23 ***** Modified parts from JENDL-3.2 ******************* 9646 1451 24 MF=2 All data 9646 1451 25 MF=3 All data 9646 1451 26 MF=4 All data 9646 1451 27 MF=5 All data 9646 1451 28 ******************************************************* 9646 1451 29 9646 1451 30 9646 1451 31 MF=1 GENERAL INFORMATION 9646 1451 32 MT=451 COMMENTS AND DICTIONARY 9646 1451 33 MT=452 NUMBER OF NEUTRONS PER FISSION 9646 1451 34 SUM OF MT'S =455 AND 456. 9646 1451 35 MT=455 DELAYED NEUTRON DATA 9646 1451 36 SEMI-EMPIRICAL FORMULA BY TUTTLE /4/. 9646 1451 37 MT=456 PROMPT NEUTRON DATA 9646 1451 38 SEMI-EMPIRICAL FORMULA BY HOWERTON /5/. 9646 1451 39 9646 1451 40 MF=2,MT=151 RESONANCE PARAMETERS 9646 1451 41 RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 60 EV 9646 1451 42 EVALUATION WAS BASED ON THE EXPERIMENTAL DATA OF MOORE AND9646 1451 43 KEYWORTH/6/, BELANOVA ET AL./7/ AND DANON ET AL./8/ 9646 1451 44 PARAMETERS OF RESONANCES UP TO 21.2 EV WERE TAKEN FROM 9646 1451 45 DANON ET AL./8/ PARAMETERS OF -0.52-EV AND 1.23-EV 9646 1451 46 RESONANCES WERE ADJUSTED TO TO REPRODUCE THERMAL CROSS 9646 1451 47 SECTIONS AND RESONANCE INTEGRALS. 9646 1451 48 RADIATIVE WIDTHS = 0.040 EV WAS ASSUMED. 9646 1451 49 SCATTERING RADIUS = 9.14 FM. 9646 1451 50 9646 1451 51 UNRESOLVED RESONANCE REGION : 60 EV TO 30 KEV 9646 1451 52 PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/ 9646 1451 53 SO AS TO REPRODUCE THE FISSION CROSS SECTION OF DANON 9646 1451 54 ET AL./8/, AND THE TOTAL AND CAPTURE CROSS SECTIONS AT 9646 1451 55 30 KEV CALCULATED WITH OPTICAL AND STATISTICAL MODELS. 9646 1451 56 ENERGY INDEPENDENT PARAMETERS: 9646 1451 57 R=8.76 FM, WG=0.035 EV,. 9646 1451 58 SPIN DEPENDENT FISSION WIDTHS WERE ASSUMED. 9646 1451 59 9646 1451 60 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9646 1451 61 2200 M/SEC RES. INTEG. 9646 1451 62 TOTAL 176.1 B - 9646 1451 63 ELASTIC 7.95 B - 9646 1451 64 FISSION 111.3 B 1130 B 9646 1451 65 CAPTURE 56.9 B 574 B 9646 1451 66 9646 1451 67 THE THERMAL CROSS SECTION AND RESONANCE INTEGRAL OF FISSION 9646 1451 68 ARE IN GOOD AGREEMENT WITH 115+-8 B AND 1091+-80 B MEASURED 9646 1451 69 BY DANON ET AL./8/, RESPECTIVELY. 9646 1451 70 9646 1451 71 MF=3 NEUTRON CROSS SECTIONS 9646 1451 72 BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 9646 1451 73 PARAMETERS. 9646 1451 74 9646 1451 75 MT=1 TOTAL CROSS SECTION 9646 1451 76 CASTHY /10/ CALCULATION WAS ADOPTED. 9646 1451 77 9646 1451 78 CASTHY CALCULATION 9646 1451 79 ------------------ 9646 1451 80 9646 1451 81 SHERICAL OPTICAL POTENTIAL PARAMETERS /11/ 9646 1451 82 9646 1451 83 V = 45.036-0.3*EN (MEV) 9646 1451 84 WS= 4.115+0.4*EN (MEV) 9646 1451 85 WV= 0 , VSO = 7.5 (MEV) 9646 1451 86 R = RSO = 1.256 , RS = 1.260 (FM) 9646 1451 87 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9646 1451 88 9646 1451 89 STATISTICAL MODEL CALCULATION WITH CASTHY CODE WAS MADE 9646 1451 90 CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N), 9646 1451 91 (N,3N). 9646 1451 92 9646 1451 93 THE LEVEL DENSITY PARAMETERS OF GILBERT-CAMERON'S FORMULA 9646 1451 94 /12/ 9646 1451 95 ISOTOPE CM-247 CM-248 9646 1451 96 A(1/MEV) 29.3 31.0 9646 1451 97 SPIN-CUTOFF PARA. 31.11 32.09 9646 1451 98 PAIRING E(MEV) 0.72 1.623 9646 1451 99 TEMP. (MEV) 0.408 0.385 9646 1451 100 C(1/MEV) 13.967 1.2545 9646 1451 101 EX(MEV) 4.2678 4.9631 9646 1451 102 9646 1451 103 THE LEVEL SCHEME TAKEN FROM REF. /13/. 9646 1451 104 NO. ENERGY(KEV) SPIN-PARITY 9646 1451 105 G.S. 0.0 9/2 - 9646 1451 106 1 61.5 11/2 - 9646 1451 107 2 135.0 13/2 - 9646 1451 108 3 217.0 15/2 - 9646 1451 109 4 227.0 5/2 + 9646 1451 110 5 266.0 7/2 + 9646 1451 111 6 285.0 7/2 + 9646 1451 112 CONTINUUM LEVELS ASSUMED ABOVE 309 KEV. 9646 1451 113 9646 1451 114 MT=2 ELASTIC SCATTRING 9646 1451 115 CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS). 9646 1451 116 MT= 4 TOTAL INELASTIC SCATTERING 9646 1451 117 SUM OF MT=51-91. 9646 1451 118 MT=16,17 (N,2N),(N,3N) CROSS SECTION 9646 1451 119 STAPRE RESULTS CALCULATED BY KONSHIN /14/ WERE ADOPTED. 9646 1451 120 MT=18 FISSION CROSS SECTION 9646 1451 121 EVALUATED ON THE BASIS OF THE MEASURED DATA BY DANON ET 9646 1451 122 AL./15/ BELOW 80 KEV. ABOVE THIS ENERGY, THE DATA OF 9646 1451 123 FOMUSHKIN ET AL./16/ WERE ADOPTED. FROM 11 MEV TO 20 9646 1451 124 MEV, THE FISSION CROSS SECTION OF JENDL-3.2 WAS SLIGHTLY 9646 1451 125 ADJUSTED ACCORDING TO THE NEW EXPERIMENTAL DATA OF 9646 1451 126 FOMUSHKIN ET AL./17/. 9646 1451 127 MT=51, 52, 53 INELASTIC SCATTERING 9646 1451 128 CALCULATED WITH ECIS /18/ AND CASTHY /10/ CODES. 9646 1451 129 IN THE ECIS CALCULATION, CH.LAGRANGE'S DEFORMED OPTICAL 9646 1451 130 POTENTIAL PARAMETERS /19/ WERE USED. 9646 1451 131 9646 1451 132 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9646 1451 133 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) 0 =