96 - CM - 243 0 0 0 0 9.62430+04 2.40973+02 1 1 0 19634 1451 1 0.00000+00 1.00000+00 0 0 0 69634 1451 2 1.00000+00 0.00000+00 0 0 10 69634 1451 3 0.00000+00 0.00000+00 0 0 177 769634 1451 4 96-Cm-243 MINSK BYEL EVAL-JUL95 9634 1451 5 DIST-AUG95 9634 1451 6 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9634 1451 7 Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ, 9634 1451 8 G.B. MOROGOVSKIJ 9634 1451 9 RADIATION PHYSICS AND CHEMISTRY PROBLEMS INSTITUTE, MINSK-SOSNY 9634 1451 10 STATUS 9634 1451 11 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9634 1451 12 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9634 1451 13 FINANCING PARTY OF THE CENTER FOR THE PROJECT IS JAPAN. 9634 1451 14 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI) 9634 1451 15 PROJECT MANAGER V.M. MASLOV (MINSK) 9634 1451 16 9634 1451 17 MF=1 GENERAL INFORMATION 9634 1451 18 9634 1451 19 MT=451 COMMENTS AND DICTIONARY 9634 1451 20 MT=452 NUMBER OF NEUTRONS PER FISSION 9634 1451 21 SUM OF MT=455 AND MT=456. 9634 1451 22 MT=455 DELAYED NEUTRON DATA 9634 1451 23 ESTIMATED FROM THE SYSTEMATICS BY TUTTLE /1/. 9634 1451 24 MT=456 NUMBER OF NEUTRONS PER FISSION 9634 1451 25 BASED ON THE EXPERIMENTAL DATA AT THERMAL ENERGY BY 9634 1451 26 JAFFEY AND LERNER /2/, ZHURAVLEV ET AL. /3/ 9634 1451 27 AND ON THE MADLAND-NIX MODEL CALCULATION /4/, ABOVE 9634 1451 28 EMISSIVE FISSION THRESHOLD A SUPERPOSITION OF 9634 1451 29 NEUTRON EMISSION IN (N,XNF) REACTIONS /5/ AND PROMPT 9634 1451 30 FISSION NEUTRONS 9634 1451 31 MF=2 RESONANCE PARAMETERS 9634 1451 32 9634 1451 33 MT=151 RESONANCE PARAMETERS (SLBW) 9634 1451 34 RESOLVED RESONANCE REGION : 1.0E-5 - 100 EV 9634 1451 35 PARAMETERS FOR BREIGT-WIGNER FORMULA ARE BASED ON 9634 1451 36 THE WORKS OF ANUFRIEV ET AL. /6/ AND SILBERT /7/. 9634 1451 37 UNRESOLVED RESONANCE REGION : 0.1 - 42.1743 KEV. 9634 1451 38 ENERGY INDEPENDENT PARAMETERS: 9634 1451 39 R=9.4757 FM FROM OPTICAL MODEL CALCULATIONS 9634 1451 40 S1=2.12E-4 FROM OPTICAL MODEL CALCULATIONS 9634 1451 41 S2=1.458-4 EQUEL S0 WITH ACCOUNT OF MISSING 9634 1451 42 ENERGY DEPENDENT PARAMETERS: 9634 1451 43 S0 - OBTAINED BY FITTING FISSION DATA OF REF./7/ 9634 1451 44 D - SPIN DEPENDENT, NORMALIZED TO =0.679 EV 9634 1451 45 WITH ACCOUNT OF LEVEL MISSING /8/ 9634 1451 46 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9634 1451 47 SPECTRA AT INNER AND OUTER BARRIER HUMPS,NORMALIZED 9634 1451 48 TO =0.355 EV FROM RESOLVED RESONANCE REGION. 9634 1451 49 WG - FROM CASCADE MODEL WITH THE ACCOUNT OF FISSION 9634 1451 50 COMPETITION,SPIN DEPENDENT. NORMALIZED TO = 9634 1451 51 0.0402 EV. 9634 1451 52 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9634 1451 53 INTEGRALS. 9634 1451 54 2200 M/SEC RES.INTEG. 9634 1451 55 TOTAL 752.419 b - 9634 1451 56 ELASTIC 8.577 b - 9634 1451 57 FISSION 613.319 b 1530.99 9634 1451 58 CAPTURE 130.523 b 211.66 9634 1451 59 9634 1451 60 MF=3 NEUTRON CROSS SECTIONS 9634 1451 61 9634 1451 62 MT=1,4,51-74,91,102. TOTAL, ELASTIC AND INELASTIC 9634 1451 63 SCATTERING, CAPTURE CROSS SECTION 9634 1451 64 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51, 9634 1451 65 53,57,60,64 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9634 1451 66 COUPLED CHANNELS CALCULATIONS. 9634 1451 67 THE DEFORMED OPTICAL POTENTIAL USED: 9634 1451 68 VR=46.49-0.3*E(MEV) RR=1.26 FM AR=0.615 FM 9634 1451 69 WD= 3.77+0.4*E(MEV) E < 10 MEV RD=1.24 FM 9634 1451 70 WD= 7.77 E => 10 MEV AD=0.5 FM 9634 1451 71 VSO=6.4 RSO=1.12 ASO=0.47 B2=0.233 B4=0.067 9634 1451 72 CAPTURE,COMPAUND ELASTIC AND INELACTIC BY STATISTICAL 9634 1451 73 MODEL, SEE MT=18-21 9634 1451 74 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASUMED TO BE 9634 1451 75 0.001 BARN AS PREDICTED BY DIRECT AND SEMY-DIRECT 9634 1451 76 CAPTURE CALCULATIONS 9634 1451 77 ADOPTED LEVEL SCHEME OF CM-243 FROM NUCLEAR DATA 9634 1451 78 SHEETS /9/ (11 LEVELS) PLUS 14 LEVELS ADDED FOR BANDS 9634 1451 79 K,P=1/2+, 3/2+, 5/2-, 5/2+ ACCORDING TO 9634 1451 80 SYSTEMATICS FOR U-235 AND PU-239 9634 1451 81 No ENERGY(MEV) SPIN-PARITY K 9634 1451 82 g.s. 0.0 5/2 + 5/2 9634 1451 83 1 0.042 7/2 + 5/2 9634 1451 84 2 0.0874 1/2 + 1/2 9634 1451 85 3 0.0939 9/2 + 5/2 9634 1451 86 4 0.0940 3/2 + 1/2 9634 1451 87 5 0.133 7/2 + 7/2 9634 1451 88 6 0.140 5/2 + 1/2 * 9634 1451 89 7 0.153 11/2 + 5/2 9634 1451 90 8 0.158 7/2 + 1/2 * 9634 1451 91 9 0.164 9/2 + 7/2 9634 1451 92 10 0.219 13/2 + 5/2 9634 1451 93 11 0.228 11/2 + 7/2 9634 1451 94 12 0.260 9/2 + 1/2 9634 1451 95 13 0.280 11/2 + 1/2 * 9634 1451 96 14 0.300 15/2 + 5/2 * 9634 1451 97 15 0.305 5/2 - 5/2 * 9634 1451 98 16 0.310 3/2 + 3/2 * 9634 1451 99 17 0.311 13/2 + 7/2 * 9634 1451 100 18 0.320 7/2 - 5/2 * 9634 1451 101 19 0.340 5/2 + 3/2 * 9634 1451 102 20 0.354 9/2 - 5/2 * 9634 1451 103 21 0.380 13/2 + 1/2 * 9634 1451 104 22 0.390 15/2 + 7/2 * 9634 1451 105 23 0.395 11/2 - 5/2 * 9634 1451 106 24 0.400 17/2 + 5/2 * 9634 1451 107 * - ADDED 9634 1451 108 9634 1451 109 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.4 MEV 9634 1451 110 LEVEL DENSITY PERAMETERS: SEE MT 18-21 9634 1451 111 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9634 1451 112 FROM STATISTICAL MODEL CALCULATIONS /10/ WITH THE 9634 1451 113 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219634 1451 114 MT=18,19,20,21. FISSION CROSS SECTION 9634 1451 115 THE FIRST CHANCE FISSION MT=19 WAS CALCULATED WITH 9634 1451 116 THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS: 9634 1451 117 9634 1451 118 TRANSITION SPECTRA BAND HEADS OF 244-CM 9634 1451 119 9634 1451 120 INNER SADDLE OUTER SADDLE 9634 1451 121 K,P EKP K,P EKP 9634 1451 122 0 + 0.0 0 + 0.0 9634 1451 123 2 + 0.1 2 + 0.3 9634 1451 124 0 - 0.4 0 - 0.0 9634 1451 125 1 - 0.4 1 - 0.1 9634 1451 126 2 + 0.3 2 + 0.3 9634 1451 127 2 - 0.4 2 - 0.1 9634 1451 128 0 + 0.8 0 + 0.8 9634 1451 129 0 + 0.8 0 + 0.8 9634 1451 130 9634 1451 131 FISSION BARRIER PARAMETERS OF 244-CM 9634 1451 132 9634 1451 133 BARRIER BARRIER HEIGHT, MEV CURVATURE, MEV 9634 1451 134 INNER 6.43 0.9 9634 1451 135 OUTER 5.10 0.6 9634 1451 136 9634 1451 137 THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 9634 1451 138 CROSS SECTION IS CALCULATED ACCORDING TO /11/. 9634 1451 139 9634 1451 140 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9634 1451 141 9634 1451 142 FOR MT=2,51,53,57 FROM COUPLED CHANNELS CALCULATIONS 9634 1451 143 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9634 1451 144 MT=16,17,18,52,54-56,58-74,91,16 ISOTROPIC 9634 1451 145 9634 1451 146 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9634 1451 147 9634 1451 148 ENERGY DISTRIBUTIONS FOR MT=16,17,18,19,20,21 WERE 9634 1451 149 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9634 1451 150 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9634 1451 151 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9634 1451 152 THE FIRST NEUTRON /5/ 9634 1451 153 9634 1451 154 REFERENCES 9634 1451 155 9634 1451 156 1. 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