95- AM-242G 9542 0 0 0 9.52420+ 4 2.39980+ 2 1 1 0 19542 1451 1 0.00000+ 0 1.00000+ 0 0 0 0 69542 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 39542 1451 3 0.00000+ 0 0.00000+ 0 0 0 176 819542 1451 4 95-Am-242G MINSK BYEL EVAL-FEB97 9542 1451 5 DIST-MAR97 9542 1451 6 9542 1451 7 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9542 1451 8 Yu.V. PORODZINSKIJ, G.B. MOROGOVSKIJ 9542 1451 9 9542 1451 10 STATUS 9542 1451 11 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9542 1451 12 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9542 1451 13 FINANCING PARTY OF THE ISTC FOR THE PROJECT IS JAPAN. 9542 1451 14 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI) 9542 1451 15 DOCUMENTED IN INDC(BLR)-008, 1997. 9542 1451 16 9542 1451 17 MF=1 GENERAL INFORMATION 9542 1451 18 9542 1451 19 MT=451 COMMENTS AND DICTIONARY 9542 1451 20 MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION 9542 1451 21 SUM OF MT=455 AND MT=456. 9542 1451 22 MT=455 DELAYED NEUTRON DATA 9542 1451 23 NUMBER OF DELAYED NEUTRONS AND 9542 1451 24 DECAY CONSTANTS FROM BRADY ET AL./1/ 9542 1451 25 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION ADOPTED TO BE 9542 1451 26 IDENTICAL TO THAT FOR AM-242M, WHICH WAS OBTAINED 9542 1451 27 WITH MADLAND-NIX MODEL CALCULATIONS /2/ FITTED TO 9542 1451 28 THE MEASURED DATA OF HOWE ET AL./3/ 9542 1451 29 ABOVE EMISSIVE FISSION THRESHOLD 9542 1451 30 SUPERPOSITION OF NEUTRON EMISSION 9542 1451 31 IN (N,XNF) REACTIONS /4/ AND PROMPT FISSION 9542 1451 32 NEUTRONS IS EMPLOYED. 9542 1451 33 9542 1451 34 MF=2 RESONANCE PARAMETERS 9542 1451 35 9542 1451 36 MT=151 RESONANCE PARAMETERS (MLBW) 9542 1451 37 RESOLVED RESONANCE REGION : 1.0E-5 - 100 EV 9542 1451 38 GENERATED FROM AVERAGE RESONANCE RAMETERS BASED ON 9542 1451 39 OPTICAL MODEL CALCULATIONS AND FISSION LEVEL DENSITY, 9542 1451 40 BARRIER PARAMETERS AND TRANSITION STATES STRUCTURE, 9542 1451 41 FIXED FOR AM-242M. 9542 1451 42 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9542 1451 43 INTEGRALS ARE: 9542 1451 44 2200 M/SEC RES.INTEG. 9542 1451 45 TOTAL 2319.73 b - 9542 1451 46 ELASTIC 7.66 b - 9542 1451 47 FISSION 2093.23 b 997.81 9542 1451 48 CAPTURE 218.83 b 187.01 9542 1451 49 9542 1451 50 UNRESOLVED RESONANCE REGION : 9542 1451 51 ENERGY INDEPENDENT PARAMETERS: 9542 1451 52 R=9.42 FM FROM OPTICAL MODEL CALCULATIONS 9542 1451 53 S1=2.046*10-4 FROM OPTICAL MODEL CALCULATIONS 9542 1451 54 S2=1.924*10-4 FROM OPTICAL MODEL CALCULATIONS 9542 1451 55 ENERGY DEPENDENT PARAMETERS: 9542 1451 56 S0-DECREASES FROM 1.363-4(0.10KEV) TO 1.267-4(44.2838 9542 1451 57 keV) 9542 1451 58 D - SPIN DEPENDENT, NORMALIZED TO =0.877 EV 9542 1451 59 CORRESPONDENT LEVEL DENSITY PARAMETER WAS FITTED TO 9542 1451 60 =0.271 EV FOR AM-242M, THEN GROUND STATE 9542 1451 61 DIFFERENCES ARE TAKEN INTO ACCOUNT. 9542 1451 62 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9542 1451 63 SPECTRA AT INNER AND OUTER BARRIER HUMPS, DETERMINED 9542 1451 64 FOR AM-242M 9542 1451 65 WG-WITH ACCOUNT OF FISSION COMPETITION =0.050 EV9542 1451 66 9542 1451 67 MF=3 NEUTRON CROSS SECTIONS 9542 1451 68 9542 1451 69 MT=1,4,51-75,91,102. TOTAL, ELASTIC AND INELASTIC 9542 1451 70 SCATTERING, CAPTURE CROSS SECTION 9542 1451 71 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=53,57,9542 1451 72 66 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9542 1451 73 COUPLED CHANNELS CALCULATIONS. 9542 1451 74 THE DEFORMED OPTICAL POTENTIAL USED: 9542 1451 75 VR=(46.10-0.3*E) MEV RR=1.26 FM AR=0.615 FM 9542 1451 76 WD=(3.53+0.4*E) MEV E < 10 MEV RD=1.24 FM 9542 1451 77 WD= 7.50 MEV E=> 10 MEV AD=0.5 FM 9542 1451 78 VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.206 B4=0.092 9542 1451 79 FOUR LEVELS OF GROUND STATE ROTATIONAL BAND 9542 1451 80 ARE COUPLED. 9542 1451 81 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9542 1451 82 MODEL, SEE MT=18-21. 9542 1451 83 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9542 1451 84 CONSTANT. 9542 1451 85 ADOPTED LEVEL SCHEME OF AM-242 FROM NUCLEAR DATA 9542 1451 86 SHEETS /7/. 9542 1451 87 9542 1451 88 No ENERGY(MEV) SPIN-PARITY K 9542 1451 89 9542 1451 90 g.s. 0.00000 1 - 0 9542 1451 91 1 0.04410 0 - 0 9542 1451 92 2 0.04863 5 - 5 9542 1451 93 3 0.05290 3 - 0 9542 1451 94 4 0.07580 2 - 0 9542 1451 95 5 0.11400 6 - 5 9542 1451 96 6 0.14000 6 - 6 9542 1451 97 7 0.14800 5 - 0 9542 1451 98 8 0.14990 4 - 0 9542 1451 99 9 0.19000 7 - 5 9542 1451 100 10 0.19760 3 - 9542 1451 101 11 0.21700 7 - 6 9542 1451 102 12 0.22000 1 - 1 9542 1451 103 13 0.23050 2 + 1 9542 1451 104 14 0.24200 2 - 1 9542 1451 105 15 0.24410 3 - 3 9542 1451 106 16 0.26300 6 - 0 9542 1451 107 17 0.26310 7 - 0 9542 1451 108 18 0.27010 2 + 9542 1451 109 19 0.27500 3 - 1 9542 1451 110 20 0.28330 3 + 9542 1451 111 21 0.28840 4 - 3 9542 1451 112 22 0.29180 2 - 2 9542 1451 113 23 0.30500 8 - 6 9542 1451 114 24 0.30690 3 - 9542 1451 115 25 0.31900 4 - 1 9542 1451 116 9542 1451 117 9542 1451 118 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.320 MEV 9542 1451 119 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9542 1451 120 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9542 1451 121 FROM STATISTICAL MODEL CALCULATIONS /8/ WITH THE 9542 1451 122 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219542 1451 123 MT=18,19,20,21. FISSION CROSS SECTION IS CALCULATED WITHIN 9542 1451 124 STATISTICAL MODEL /9,10/. THE FISSION BARRIER PARAMETERS9542 1451 125 ARE FIXED BY FITTING MEASURED DATA FOR AM-242M BY 9542 1451 126 BROWNE ET AL./5/ AND FURSOV ET AL./11/. 9542 1451 127 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9542 1451 128 THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION 9542 1451 129 CROSS SECTION ACCORDING TO /9,12/. 9542 1451 130 9542 1451 131 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9542 1451 132 9542 1451 133 FOR MT=2, 53, 57, 66 FROM COUPLED CHANNELS CALCULATIONS 9542 1451 134 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9542 1451 135 9542 1451 136 MT=16,17,18-21,51-52,54-56,58-65,67-75,91 - ISOTROPIC 9542 1451 137 9542 1451 138 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9542 1451 139 9542 1451 140 ENERGY DISTRIBUTIONS FOR MT=16,17 WERE 9542 1451 141 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9542 1451 142 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9542 1451 143 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9542 1451 144 THE FIRST NEUTRON /4/ 9542 1451 145 ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE ADOPTED TO 9542 1451 146 BE IDENTICAL TO THAT OF AM-242M, WHICH WERE CALCULATED 9542 1451 147 BY MADLAND-NIX MODEL /2/ WITH ACCOUNT OF COMPETITION 9542 1451 148 BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH 9542 1451 149 THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM9542 1451 150 EMISSION OF THE FIRST NEUTRON /4,8/ 9542 1451 151 9542 1451 152 REFERENCES 9542 1451 153 9542 1451 154 1. 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Nuclear Data 9542 1451 170 Evaluation Methodology, Brookhaven, USA, October 12-16, 1992, 9542 1451 171 p.440, World Scientific, 1993. 9542 1451 172 10. Maslov V.M. Sov. J. At. Energy 64, 478 (1988). 9542 1451 173 11. Fursov B.I., Samylin B.F., Smirenkin G.N., Polynov V.N., 9542 1451 174 Nuclear Data for Science and Technology, Proc. Int. Conf., 9542 1451 175 Gatlinburg, Tennessee, USA, May 9-13, 1994, v.1,p.269. 9542 1451 176 12. Maslov V.M., Kikuchi Y. 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