Retrieved by E4-util: 2010/02/01,11:45:38 1 0 0 0 9.624800+4 2.459410+2 1 1 59 09648 1451 1 0.000000+0 0.000000+0 0 0 0 69648 1451 2 1.000000+0 2.000000+7 3 0 10 09648 1451 3 0.000000+0 0.000000+0 0 0 225 579648 1451 4 96-Cm-248 IPPE EVAL-SEP06 MANOKHIN V.N. 9648 1451 5 DIST-DEC06 9648 1451 6 ----RUSFOND MATERIAL 9648 9648 1451 7 -----INCIDENT NEUTRON DATA 9648 1451 8 ------ENDF-6 FORMAT 9648 1451 9 9648 1451 10 RUSFOND DESCRIPTION 9648 1451 11 (See RUSFOND manual for details) 9648 1451 12 9648 1451 13 Data are compiled by the next manner 9648 1451 14 9648 1451 15 1. Data from JENDL-3.3 are adopted. 9648 1451 16 2. GF for first resonance level was chanced as 7.E-4; 9648 1451 17 (RIF=13.6 B after PSYCHY(ver.6.13)). 9648 1451 18 3. Background was recalculated for fis=0.37 B. 9648 1451 19 4. MF1 Mt455 was added from JEFF-3.1 (8 groups of dn) 9648 1451 20 5. MF5 MT455 was included for 8 groups of dn with the same 9648 1451 21 spectra as for U-235 and ai from JEFF-3.1 9648 1451 22 6. MF8 MT454 and MT459 added using ENDF/B-VI data 9648 1451 23 JENDL-3.3 description 9648 1451 24 HISTORY 9648 1451 25 84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9648 1451 26 T.NAKAGAWA (JAERI). DETAILS ARE GIVEN IN REF. /1/. 9648 1451 27 95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9648 1451 28 T.NAKAGAWA AND T.LIU. 9648 1451 29 00-04 MODIFICATION WAS MADE BY T.NAKAGAWA. 9648 1451 30 9648 1451 31 ***** Modified parts from JENDL-3.2 ******************* 9648 1451 32 MF=2 9648 1451 33 MF=3 All data 9648 1451 34 MF=4 All data 9648 1451 35 MF=5 All data 9648 1451 36 ******************************************************* 9648 1451 37 9648 1451 38 9648 1451 39 MF=1 GENERAL INFORMATION 9648 1451 40 MT=451 COMMENTS AND DICTIONARY 9648 1451 41 MT=452 NUMBER OF NEUTRONS PER FISSION 9648 1451 42 SUM OF MT'S =455 AND 456. 9648 1451 43 MT=455 DELAYED NEUTRON DATA 9648 1451 44 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9648 1451 45 MT=456 PROMPT NEUTRON DATA 9648 1451 46 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9648 1451 47 9648 1451 48 MF=2,MT=151 RESONANCE PARAMETERS 9648 1451 49 (TAKEN FROM JENDL-3.2) 9648 1451 50 RESOLVED RESONANCE REGION (MLBW) : 1.0E-5 TO 1.5 KEV 9648 1451 51 RESONANCE ENERGIES, NEUTRON AND RADIATIVE WIDTHS WERE 9648 1451 52 TAKEN FROM THE EXPERIMENTAL DATA OF BENJAMIN ET AL./4/. 9648 1451 53 FOR RESONANCES WHOSE RADIATIVE WIDTH WAS UNKNOWN, THE 9648 1451 54 AVERAGE VALUE OF 0.026 EV /4/ WAS ADOPTED. THE FISSION 9648 1451 55 WIDTHS were adopted from Moore and Keyworth /5/ and 9648 1451 56 Maguire et al. /6/ THE AVERAGE FISSION WIDTH OF 0.0013 9648 1451 57 EV /5/ WAS USED FOR ALL RESONANCES OF WHICH FISSION 9648 1451 58 WIDTH HAD NOT BEEN MEASURED. Then the fission widths were9648 1451 59 roughly adjusted to the fission cross section measured by 9648 1451 60 Maguire et al. R=9.1 FM WAS ASSUMED TO REPRODUCE THE 9648 1451 61 POTENTIAL SCATTERING CROSS SECTION OF 10.4 BARNS ASSUMED 9648 1451 62 BY BENJAMIN ET AL./4/. THE NEUTRON WIDTH OF THE FIRST 9648 1451 63 RESONANCE WAS SLIGHTLY ADJUSTED TO REPRODUCE THE CAPTURE 9648 1451 64 CROSS SECTION OF 2.57 BARNS AT 0.0253 EV. BACKGROUND 9648 1451 65 CROSS SECTIONS WERE GIVEN ONLY FOR THE FISSION AND TOTAL 9648 1451 66 CROSS SECTIONS BY ASSUMING THE FORM OF 1/V. THE THERMAL 9648 1451 67 CROSS SECTIONS TO BE REPRODUCED WERE ESTIMATED FROM 9648 1451 68 AVAILABLE EXPERIMENTAL DATA. 9648 1451 69 9648 1451 70 UNRESOLVED RESONANCE REGION : 1.5 KEV TO 30 KEV 9648 1451 71 PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/7/ 9648 1451 72 OBTAINED FROM OPTICAL MODEL CALCULATION: 9648 1451 73 S1=3.32E-4, S2=0.844E-4. 9648 1451 74 ESTIMATED FROM RESOLVED RESONANCES: 9648 1451 75 D-OBS=40.0 EV, GAM-G=26 MILLI-EV, S0=1.2E-4 9648 1451 76 GAM-F OBTAINED BY FITTING THE DATA OF STOPA ET AL./6/ 9648 1451 77 Scattring radius R was adjusted so as to reproduce the 9648 1451 78 ealstic scattering cross section calculated with CASTHY 9648 1451 79 at 30 keV. 9648 1451 80 9648 1451 81 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9648 1451 82 2200 M/S VALUE RES. INT. 9648 1451 83 TOTAL 9.456 B - 9648 1451 84 ELASTIC 6.514 B - 9648 1451 85 FISSION 0.372 B 10.0 B 9648 1451 86 CAPTURE 2.570 B 267. B 9648 1451 87 9648 1451 88 MF=3 NEUTRON CROSS SECTIONS 9648 1451 89 BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 9648 1451 90 PARAMETERS. BACKGROUND CROSS SECTION WAS GIVEN TO FISSION. 9648 1451 91 9648 1451 92 MT=1 TOTAL CROSS SECTION 9648 1451 93 CALCULATED WITH CASTHY CODE /8/ BASED ON THE SHERICAL 9648 1451 94 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./9/ WERE 9648 1451 95 USED. 9648 1451 96 9648 1451 97 V = 45.036-0.3*EN (MEV) 9648 1451 98 WS= 4.115+0.4*EN (MEV) 9648 1451 99 WV= 0 , VSO = 7.5 (MEV) 9648 1451 100 R = RSO = 1.256 , RS = 1.260 (FM) 9648 1451 101 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9648 1451 102 9648 1451 103 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9648 1451 104 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9648 1451 105 OF GILBERT-CAMERON'S FORMULA /10/ WERE USED. 9648 1451 106 9648 1451 107 ISOTOPE CM-248 CM-249 9648 1451 108 A(1/MEV) 27.8 34.2 9648 1451 109 SPIN-CUTOFF PARA. 30.39 33.79 9648 1451 110 PAIRING E(MEV) 0.0 0.903 9648 1451 111 TEMP. (MEV) 0.326 0.366 9648 1451 112 C(1/MEV) 10.8 12.2 9648 1451 113 EX(MEV) 1.85 4.30 9648 1451 114 9648 1451 115 THE LEVEL SCHEME TAKEN FROM REF. /11/. 9648 1451 116 NO. ENERGY(KEV) SPIN-PARITY 9648 1451 117 G.S. 0.0 0 + 9648 1451 118 1. 43.4 2 + 9648 1451 119 2. 143.8 4 + 9648 1451 120 3. 298.8 6 + 9648 1451 121 4. 506.0 8 + 9648 1451 122 5. 761.9 10 + 9648 1451 123 6. 1049.0 2 + 9648 1451 124 7. 1049.0 1 - 9648 1451 125 8. 1062.8 12 + 9648 1451 126 9. 1084.0 0 + 9648 1451 127 10. 1094.0 3 - 9648 1451 128 11. 1126.0 2 + 9648 1451 129 12. 1143.0 4 + 9648 1451 130 13. 1172.0 5 - 9648 1451 131 14. 1222.0 4 + 9648 1451 132 15. 1235.0 3 - 9648 1451 133 16. 1302.0 3 - 9648 1451 134 CONTINUUM LEVELS ASSUMED ABOVE 1314 KEV. 9648 1451 135 9648 1451 136 MT= 2 ELASTIC SCATTERING 9648 1451 137 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9648 1451 138 9648 1451 139 MT= 4 TOTAL INELASTIC SCATTERING 9648 1451 140 SUM OF MT=51, 52, 53, 54 AND 91. 9648 1451 141 9648 1451 142 MT=16,17 (N,2N),(N,3N) CROSS SECTION 9648 1451 143 STAPRE RESULTS CALCULATED BY KONSHIN /12/ WERE ADOPTED. 9648 1451 144 9648 1451 145 MT=18 FISSION CROSS SECTION 9648 1451 146 BELOW 6 MEV TAKEN FROM JENDL-3.2 WHICH WAS EVALUATED ON 9648 1451 147 THE BASIS OF THE MEASURED DATA BY STOPA ET AL./6/ AND 9648 1451 148 FOMUSHKIN ET AL./13/. FROM 6 MEV TO 8 MEV, THE STAPRE 9648 1451 149 RESULT CALCULATED BY KONSHIN /12/ WERE USED. FROM 8 MEV 9648 1451 150 TO 20 MEV BY EYE GUIDE, BASED ON THE MEASURED DATA OF 9648 1451 151 FOMUSHKIN ET AL./14/ 9648 1451 152 9648 1451 153 MT=51, 52, 53, 54 Inelastic scattering 9648 1451 154 CALCULATED BY ECIS /15/ AND CASTHY /8/ CODES. 9648 1451 155 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /16/ WERE 9648 1451 156 USED. 9648 1451 157 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9648 1451 158 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV)