Retrieved by E4-util: 2010/02/01,11:45:38 1 0 0 0 9.624700+4 2.449480+2 1 1 59 09647 1451 1 0.000000+0 0.000000+0 0 0 0 69647 1451 2 1.000000+0 2.000000+7 3 0 10 09647 1451 3 0.000000+0 0.000000+0 0 0 224 359647 1451 4 96-Cm-247 IPPE EVAL-OCT05 MANOKHIN V.N. 9647 1451 5 DIST-DEC06 9647 1451 6 ----RUSFOND MATERIAL 9647 9647 1451 7 -----INCIDENT NEUTRON DATA 9647 1451 8 ------ENDF-6 FORMAT 9647 1451 9 9647 1451 10 RUSFOND DESCRIPTION 9647 1451 11 (See RUSFOND manual for details) 9647 1451 12 9647 1451 13 Data are compiled by the next manner 9647 1451 14 9647 1451 15 1. Data from ENDF/B-VII are adopted. 9647 1451 16 2. MF1 Mt455 was added from JEFF-3.1 (8 groups of dn) 9647 1451 17 3. MF4 MT455 was added the same as for Cm-245 9647 1451 18 *************************************************************** 9647 1451 19 ENDF/B-VII description 9647 1451 20 *************************************************************** 9647 1451 21 9647 1451 22 JENDL-3.3 Evaluation was revised for ENDF/B-VII, 10-21-2005 9647 1451 23 at ORNL by R. Q. Wright 9647 1451 24 The fission cross section, MF = 3, MT = 18 is revised between 9647 1451 25 30 keV and 20 MeV. The cross section is lower above 150 keV. 9647 1451 26 The revised cross section is in agreement with the measurements 9647 1451 27 of Ivanin[IV1997] and Fursov[FU1997]. The data of Fursov is 9647 1451 28 generally lower and has smaller error bars, compared to Ivanin. 9647 1451 29 The evaluation is closer to Fursov between 1 and 7 MeV and at 9647 1451 30 15 MeV. The elastic cross section was changed in order to keep 9647 1451 31 the total cross section unchanged from JENDL-3.3 9647 1451 32 9647 1451 33 REFERENCES: 9647 1451 34 IV1997 Ivanin, et al. Triest, 1, 664 (1997), EXFOR 41360 9647 1451 35 FU1997 Fursov, et al. Triest, 1, 488 (1997), EXFOR 41303 9647 1451 36 9647 1451 37 *************************************************************** 9647 1451 38 9647 1451 39 JENDL-3.3 comments follow- 9647 1451 40 HISTORY 9647 1451 41 83-03 EVALUATION WAS BY Y.KIKUCHI(JAERI)/1/. 9647 1451 42 89-03 RE-EVALUATION WAS MADE FOR JENDL-3 BY T.NAKAGAWA(JAERI)/2/ 9647 1451 43 95-10 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU/3/. 9647 1451 44 99-12 RECOMPILED BY T.NAKAGAWA. 9647 1451 45 THE FOLLOWING QUANTITIES ARE RE-EVALUATED AFTER JAERI- 9647 1451 46 RESEARCH 97-056: 9647 1451 47 MF=2 MT=151 9647 1451 48 MF=3 MT=102 DIRECT/SEMI-DIRECT MODIFIED. 9647 1451 49 MT=37 DELETED 9647 1451 50 MF=4 MT= 2 BELOW 600 KEV, REPLACED WITH CASTHY CALC. 9647 1451 51 MF=5 MT=16, 17, 18, 91 9647 1451 52 9647 1451 53 ***** Modified parts from JENDL-3.2 ******************* 9647 1451 54 MF=2 All data 9647 1451 55 MF=3 All data 9647 1451 56 MF=4 All data 9647 1451 57 MF=5 All data 9647 1451 58 ******************************************************* 9647 1451 59 9647 1451 60 9647 1451 61 MF=1 GENERAL INFORMATION 9647 1451 62 MT=451 COMMENTS AND DICTIONARY 9647 1451 63 MT=452 NUMBER OF NEUTRONS PER FISSION 9647 1451 64 SUM OF MT'S =455 AND 456. 9647 1451 65 MT=455 DELAYED NEUTRON DATA 9647 1451 66 SEMI-EMPIRICAL FORMULA BY TUTTLE /4/. 9647 1451 67 MT=456 PROMPT NEUTRON DATA 9647 1451 68 SEMI-EMPIRICAL FORMULA BY HOWERTON /5/. 9647 1451 69 9647 1451 70 MF=2,MT=151 RESONANCE PARAMETERS 9647 1451 71 RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 60 EV 9647 1451 72 EVALUATION WAS BASED ON THE EXPERIMENTAL DATA OF MOORE AND9647 1451 73 KEYWORTH/6/, BELANOVA ET AL./7/ AND DANON ET AL./8/ 9647 1451 74 PARAMETERS OF RESONANCES UP TO 21.2 EV WERE TAKEN FROM 9647 1451 75 DANON ET AL./8/ PARAMETERS OF -0.52-EV AND 1.23-EV 9647 1451 76 RESONANCES WERE ADJUSTED TO TO REPRODUCE THERMAL CROSS 9647 1451 77 SECTIONS AND RESONANCE INTEGRALS. 9647 1451 78 RADIATIVE WIDTHS = 0.040 EV WAS ASSUMED. 9647 1451 79 SCATTERING RADIUS = 9.14 FM. 9647 1451 80 9647 1451 81 UNRESOLVED RESONANCE REGION : 60 EV TO 30 KEV 9647 1451 82 PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/ 9647 1451 83 SO AS TO REPRODUCE THE FISSION CROSS SECTION OF DANON 9647 1451 84 ET AL./8/, AND THE TOTAL AND CAPTURE CROSS SECTIONS AT 9647 1451 85 30 KEV CALCULATED WITH OPTICAL AND STATISTICAL MODELS. 9647 1451 86 ENERGY INDEPENDENT PARAMETERS: 9647 1451 87 R=8.76 FM, WG=0.035 EV,. 9647 1451 88 SPIN DEPENDENT FISSION WIDTHS WERE ASSUMED. 9647 1451 89 9647 1451 90 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9647 1451 91 2200 M/SEC RES. INTEG. 9647 1451 92 TOTAL 176.1 B - 9647 1451 93 ELASTIC 7.95 B - 9647 1451 94 FISSION 111.3 B 1130 B 9647 1451 95 CAPTURE 56.9 B 574 B 9647 1451 96 9647 1451 97 THE THERMAL CROSS SECTION AND RESONANCE INTEGRAL OF FISSION 9647 1451 98 ARE IN GOOD AGREEMENT WITH 115+-8 B AND 1091+-80 B MEASURED 9647 1451 99 BY DANON ET AL./8/, RESPECTIVELY. 9647 1451 100 9647 1451 101 MF=3 NEUTRON CROSS SECTIONS 9647 1451 102 BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 9647 1451 103 PARAMETERS. 9647 1451 104 9647 1451 105 MT=1 TOTAL CROSS SECTION 9647 1451 106 CASTHY /10/ CALCULATION WAS ADOPTED. 9647 1451 107 9647 1451 108 CASTHY CALCULATION 9647 1451 109 ------------------ 9647 1451 110 9647 1451 111 SHERICAL OPTICAL POTENTIAL PARAMETERS /11/ 9647 1451 112 9647 1451 113 V = 45.036-0.3*EN (MEV) 9647 1451 114 WS= 4.115+0.4*EN (MEV) 9647 1451 115 WV= 0 , VSO = 7.5 (MEV) 9647 1451 116 R = RSO = 1.256 , RS = 1.260 (FM) 9647 1451 117 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9647 1451 118 9647 1451 119 STATISTICAL MODEL CALCULATION WITH CASTHY CODE WAS MADE 9647 1451 120 CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N), 9647 1451 121 (N,3N). 9647 1451 122 9647 1451 123 THE LEVEL DENSITY PARAMETERS OF GILBERT-CAMERON'S FORMULA 9647 1451 124 /12/ 9647 1451 125 ISOTOPE CM-247 CM-248 9647 1451 126 A(1/MEV) 29.3 31.0 9647 1451 127 SPIN-CUTOFF PARA. 31.11 32.09 9647 1451 128 PAIRING E(MEV) 0.72 1.623 9647 1451 129 TEMP. (MEV) 0.408 0.385 9647 1451 130 C(1/MEV) 13.967 1.2545 9647 1451 131 EX(MEV) 4.2678 4.9631 9647 1451 132 9647 1451 133 THE LEVEL SCHEME TAKEN FROM REF. /13/. 9647 1451 134 NO. ENERGY(KEV) SPIN-PARITY 9647 1451 135 G.S. 0.0 9/2 - 9647 1451 136 1 61.5 11/2 - 9647 1451 137 2 135.0 13/2 - 9647 1451 138 3 217.0 15/2 - 9647 1451 139 4 227.0 5/2 + 9647 1451 140 5 266.0 7/2 + 9647 1451 141 6 285.0 7/2 + 9647 1451 142 CONTINUUM LEVELS ASSUMED ABOVE 309 KEV. 9647 1451 143 9647 1451 144 MT=2 ELASTIC SCATTRING 9647 1451 145 CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS). 9647 1451 146 MT= 4 TOTAL INELASTIC SCATTERING 9647 1451 147 SUM OF MT=51-91. 9647 1451 148 MT=16,17 (N,2N),(N,3N) CROSS SECTION 9647 1451 149 STAPRE RESULTS CALCULATED BY KONSHIN /14/ WERE ADOPTED. 9647 1451 150 MT=18 FISSION CROSS SECTION 9647 1451 151 EVALUATED ON THE BASIS OF THE MEASURED DATA BY DANON ET 9647 1451 152 AL./15/ BELOW 80 KEV. ABOVE THIS ENERGY, THE DATA OF 9647 1451 153 FOMUSHKIN ET AL./16/ WERE ADOPTED. FROM 11 MEV TO 20 9647 1451 154 MEV, THE FISSION CROSS SECTION OF JENDL-3.2 WAS SLIGHTLY 9647 1451 155 ADJUSTED ACCORDING TO THE NEW EXPERIMENTAL DATA OF 9647 1451 156 FOMUSHKIN ET AL./17/. 9647 1451 157 MT=51, 52, 53 INELASTIC SCATTERING 9647 1451 158 CALCULATED WITH ECIS /18/ AND CASTHY /10/ CODES. 9647 1451 159 IN THE ECIS CALCULATION, CH.LAGRANGE'S DEFORMED OPTICAL 9647 1451 160 POTENTIAL PARAMETERS /19/ WERE USED. 9647 1451 161 9647 1451 162 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9647 1451 163 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) 0 =