96 - Cm - 246 9643 0 0 0 9.62460+04 2.43953+02 1 1 0 19643 1451 1 0.00000+00 0.00000+00 0 0 0 69643 1451 2 1.00000+00 0.00000+00 0 0 10 69643 1451 3 0.00000+00 0.00000+00 0 0 175 719643 1451 4 96-Cm-246 MINSK BYEL EVAL-NOV 5 9643 1451 5 DIST-FEB96 9643 1451 6 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9643 1451 7 Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ, 9643 1451 8 G.B. MOROGOVSKIJ 9643 1451 9 STATUS 9643 1451 10 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9643 1451 11 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9643 1451 12 FINANCING PARTY OF THE CENTER FOR THE PROJECT IS JAPAN. 9643 1451 13 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI) 9643 1451 14 9643 1451 15 MF=1 GENERAL INFORMATION 9643 1451 16 9643 1451 17 MT=451 COMMENTS AND DICTIONARY 9643 1451 18 MT=452 NUMBER OF NEUTRONS PER FISSION 9643 1451 19 SUM OF MT=455 AND MT=456. 9643 1451 20 MT=455 DELAYED NEUTRON DATA 9643 1451 21 DECAY CONSTANTS FROM BRADY ET AL./1 / 9643 1451 22 NUMBER OF NEUTRONS PER FISSION FROM TUTTLE'S 9643 1451 23 SYSTEMATICS /2/. 9643 1451 24 MT=456 NUMBER OF NEUTRONS PER FISSION BASED ON 9643 1451 25 MADLAND-NIX MODEL CALCULATIONS /3/, ABOVE 9643 1451 26 EMISSIVE FISSION THRESHOLD A SUPERPOSITION OF 9643 1451 27 NEUTRON EMISSION IN (N,XNF) REACTIONS /4/ AND PROMPT 9643 1451 28 FISSION NEUTRONS 9643 1451 29 MF=2 RESONANCE PARAMETERS 9643 1451 30 9643 1451 31 MT=151 RESONANCE PARAMETERS (MLBW) 9643 1451 32 RESOLVED RESONANCE REGION : 1.0E-5 - 400 EV 9643 1451 33 PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED ON 9643 1451 34 THE DATA OF MOORE ET AL./5/ AND MAGUIRE ET AL./6/., 9643 1451 35 REVISED BY DANON ET AL./7/ 9643 1451 36 UNRESOLVED RESONANCE REGION : 0.4 - 43.0277 KEV. 9643 1451 37 ENERGY INDEPENDENT PARAMETERS: 9643 1451 38 R=9.0323 FM FROM OPTICAL MODEL CALCULATIONS 9643 1451 39 S1=2.769E-4 FROM OPTICAL MODEL CALCULATIONS 9643 1451 40 S2=1.023E-4 FROM OPTICAL MODEL CALCULATIONS 9643 1451 41 ENERGY DEPENDENT PARAMETERS: 9643 1451 42 S0 - DECREASES FROM 0.89E-4 (0.4KEV)TO 0.859E-4(43KEV) 9643 1451 43 D - SPIN DEPENDENT, NORMALIZED TO =17.5 EV 9643 1451 44 WITH ACCOUNT OF LEVEL MISSING /8/ 9643 1451 45 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9643 1451 46 SPECTRA AT INNER AND OUTER BARRIER HUMPS,NORMALIZED 9643 1451 47 TO =1.33E-03 EV TO FIT UNRESOLVED RESONANCE 9643 1451 48 REGION EXPERIMENTAL FISSION DATA /6,7/. 9643 1451 49 WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION 9643 1451 50 COMPETITION,SPIN DEPENDENT. NORMALIZED TO = 9643 1451 51 0.0347 EV. 9643 1451 52 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9643 1451 53 INTEGRALS. 9643 1451 54 2200 M/SEC RES.INTEG. 9643 1451 55 TOTAL 10.664 b - 9643 1451 56 ELASTIC 9.208 b - 9643 1451 57 FISSION 0.144 b 114.596 9643 1451 58 CAPTURE 1.311 b 10.281 9643 1451 59 9643 1451 60 MF=3 NEUTRON CROSS SECTIONS 9643 1451 61 9643 1451 62 MT=1,2,4,51-70,91,102. TOTAL, ELASTIC AND INELASTIC 9643 1451 63 SCATTERING, CAPTURE CROSS SECTION 9643 1451 64 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51- 9643 1451 65 54 AND OPTICAL TRANSMISSION COEFFICIENTS ARE FROM 9643 1451 66 COUPLED CHANNELS CALCULATIONS. 9643 1451 67 THE DEFORMED OPTICAL POTENTIAL USED: 9643 1451 68 VR=46.33-0.3*E(MEV) RR=1.26 FM AR=0.615 FM 9643 1451 69 WD= 3.68+0.4*E(MEV) E < 10 MEV RD=1.24 FM 9643 1451 70 WD= 7.68 E > 10 MEV AD=0.5 FM 9643 1451 71 VSO=6.4 RSO=1.12 ASO=0.47 B2=0.203 B4=0.009 9643 1451 72 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9643 1451 73 MODEL, SEE MT=18-21 9643 1451 74 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9643 1451 75 0.001 BARN AS PREDICTED BY DIRECT AND SEMI -DIRECT 9643 1451 76 CAPTURE CALCULATIONS 9643 1451 77 ADOPTED LEVEL SCHEME OF CM-246 FROM NUCLEAR DATA 9643 1451 78 SHEETS /9/ (19 LEVELS) PLUS 2 LEVELS ADDED/10/ FOR BAND9643 1451 79 K,P=0+, PLUS 1 LEVEL ADDED FOR BAND K,P=1- ACCORDING 9643 1451 80 TO EJK=E(BH)+A(J(J+1)-K(K+1)) 9643 1451 81 No ENERGY(MEV) SPIN-PARITY K 9643 1451 82 g.s. 0.0 0 + 0 9643 1451 83 1 0.04258 2 + 0 9643 1451 84 2 0.14201 4 + 0 9643 1451 85 3 0.29490 6 + 0 9643 1451 86 4 0.50040 8 + 0 9643 1451 87 5 0.78207 10 + 0 * 9643 1451 88 6 0.84167 2 - 2 9643 1451 89 7 0.87643 3 - 2 9643 1451 90 8 0.92331 4 - 2 9643 1451 91 9 0.98000 5 - 2 9643 1451 92 10 1.05170 6 - 2 9643 1451 93 11 1.07885 1 - 1 9643 1451 94 12 1.10485 2 - 1 9643 1451 95 13 1.10550 12 + 0 * 9643 1451 96 14 1.12427 2 + 2 9643 1451 97 15 1.12802 3 - 1 9643 1451 98 16 1.12940 7 - 2 9643 1451 99 17 1.16549 3 + 2 9643 1451 100 18 1.17474 0 + 0 9643 1451 101 19 1.17920 8 - 2 9643 1451 102 20 1.19580 4 - 1 * 9643 1451 103 21 1.21053 2 + 0 9643 1451 104 * - ADDED 9643 1451 105 9643 1451 106 OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.22 MEV 9643 1451 107 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9643 1451 108 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9643 1451 109 FROM STATISTICAL MODEL CALCULATIONS /11/ WITH THE 9643 1451 110 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219643 1451 111 MT=18,19,20,21. FISSION CROSS SECTION 9643 1451 112 BASED ON DATA OF FOMUSHKIN ET AL./12/,MAGUIRE ET AL./6/,9643 1451 113 REVISED BY DANON ET AL./7/. 9643 1451 114 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9643 1451 115 THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS: 9643 1451 116 9643 1451 117 TRANSITION SPECTRA BAND HEADS OF 247-CM 9643 1451 118 9643 1451 119 INNER SADDLE OUTER SADDLE 9643 1451 120 K,P EKP K,P EKP 9643 1451 121 1/2+ 0.0 1/2+ 0.0 9643 1451 122 5/2+ 0.08 1/2- 0.0 9643 1451 123 1/2- 0.05 3/2+ 0.08 9643 1451 124 3/2- 0.0 3/2- 0.08 9643 1451 125 5/2+ 0.0 9643 1451 126 5/2- 0.0 9643 1451 127 9643 1451 128 9643 1451 129 9643 1451 130 FISSION BARRIER PARAMETERS OF 247-CM 9643 1451 131 9643 1451 132 BARRIER BARRIER HEIGHT, MEV CURVATURE, MEV 9643 1451 133 INNER 6.17 0.7 9643 1451 134 OUTER 5.40 0.6 9643 1451 135 9643 1451 136 THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 9643 1451 137 CROSS SECTION IS CALCULATED ACCORDING TO /11,13/. 9643 1451 138 9643 1451 139 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9643 1451 140 9643 1451 141 FOR MT=2,51-54 FROM COUPLED CHANNELS CALCULATIONS 9643 1451 142 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9643 1451 143 MT=16,17,18-21,55-70,91 ISOTROPIC 9643 1451 144 9643 1451 145 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9643 1451 146 9643 1451 147 ENERGY DISTRIBUTIONS FOR MT=16,17,18,19,20,21 WERE 9643 1451 148 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9643 1451 149 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9643 1451 150 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9643 1451 151 THE FIRST NEUTRON /4/ 9643 1451 152 9643 1451 153 REFERENCES 9643 1451 154 9643 1451 155 1. 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