94 - Pu - 242 9446 0 0 0 9.42420+ 4 2.399790+2 1 1 0 19446 1451 1 0.000000+0 1.000000+0 0 0 0 69446 1451 2 1.000000+0 0.000000+0 0 0 10 69446 1451 3 0.000000+0 0.000000+0 0 0 183 719446 1451 4 94-Pu-242 MINSK BYEL EVAL-AUG97 9446 1451 5 DIST-SEP97 9446 1451 6 9446 1451 7 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9446 1451 8 Yu.V. PORODZINSKIJ, G.B. MOROGOVSKIJ 9446 1451 9 9446 1451 10 STATUS 9446 1451 11 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9446 1451 12 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9446 1451 13 FINANCING PARTY OF THE ISTC FOR THE PROJECT IS JAPAN. 9446 1451 14 EVALUATION WAS REQUESTED BY JAPAN NUCLEAR DATA CENTER (JAERI). 9446 1451 15 DOCUMENTED IN INDC(BLR)-010, 1997. 9446 1451 16 9446 1451 17 MF=1 GENERAL INFORMATION 9446 1451 18 9446 1451 19 MT=451 COMMENTS AND DICTIONARY 9446 1451 20 MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION 9446 1451 21 SUM OF MT=455 AND MT=456. 9446 1451 22 MT=455 DELAYED NEUTRON DATA 9446 1451 23 NUMBER OF DELAYED NEUTRONS AND 9446 1451 24 DECAY CONSTANTS FROM /1/ 9446 1451 25 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9446 1451 26 ABOVE EMISSIVE FISSION THRESHOLD IS A 9446 1451 27 SUPERPOSITION OF NEUTRON EMISSION 9446 1451 28 IN (N,XNF) REACTIONS AND PROMPT FISSION 9446 1451 29 NEUTRONS. 9446 1451 30 9446 1451 31 MF=2 RESONANCE PARAMETERS 9446 1451 32 9446 1451 33 MT=151 RESONANCE PARAMETERS (MLBW) 9446 1451 34 RESOLVED RESONANCE REGION : 1.0E-5 - 1300 EV 9446 1451 35 PARAMETERS OF BREIT-WIGNER FORMULA ARE BASED UPON 9446 1451 36 THE PARAMETERS BY POORTMANS /2/; 9446 1451 37 TOTAL CROSS SECTION MEASUREMENT BY YOUNG /3,4/ 9446 1451 38 AND AUCHAMPAUGH /5/; 9446 1451 39 FISSION CROSS SECTION MEASUREMENTS BY BERGEN /6/, 9446 1451 40 AUCHAMPAUGH /7/, THE FISSION AREA MEASUREMENTS BY 9446 1451 41 WEIGMANN/8/. 9446 1451 42 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9446 1451 43 INTEGRALS ARE: 9446 1451 44 2200 M/SEC RES.INTEG. 9446 1451 45 TOTAL 26.900 b - 9446 1451 46 ELASTIC 7.864 b - 9446 1451 47 FISSION 0.002 b 5.5270 9446 1451 48 CAPTURE 19.034 b 1123.73 9446 1451 49 9446 1451 50 UNRESOLVED RESONANCE REGION : 1.3 -44.7256 KEV 9446 1451 51 ENERGY INDEPENDENT PARAMETERS: 9446 1451 52 R=9.104 FM FROM OPTICAL MODEL CALCULATIONS 9446 1451 53 S1=2.59 *10-4 FROM 0PTICAL MODEL CALCULATIONS 9446 1451 54 S2=1.17 *10-4 FROM OPTICAL MODEL CALCULATIONS 9446 1451 55 ENERGY DEPENDENT PARAMETERS: 9446 1451 56 S0-DECREASES FROM 0.931-4(1.3KEV) TO 0.883-4(44.73KEV) 9446 1451 57 D - SPIN DEPENDENT, NORMALIZED TO =12.903 EV 9446 1451 58 WITH ACCOUNT OF LEVEL MISSING /9/. 9446 1451 59 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9446 1451 60 SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED 9446 1451 61 TO = 15 mEV TO FIT FISSION DATA OF AUCHAM- 9446 1451 62 PAUGH /7/ AND WEIGMANN/8/ IN UNRESOLVED RESONANCE 9446 1451 63 REGION. 9446 1451 64 FISSION WIDTH FOR J,PI=1/2+ VARIED TO FIT 9446 1451 65 FISSION SUBTHRESHOLD INTERMEDIATE STRUCTURE /5,8/, 9446 1451 66 WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND 9446 1451 67 NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA- 9446 1451 68 LIZED TO = 0.02272 EV. 9446 1451 69 9446 1451 70 MF=3 NEUTRON CROSS SECTIONS 9446 1451 71 9446 1451 72 MT=1,4,51-70,91,102. TOTAL, ELASTIC AND INELASTIC 9446 1451 73 SCATTERING, CAPTURE CROSS SECTION 9446 1451 74 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51, 9446 1451 75 52,53 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9446 1451 76 COUPLED CHANNEL CALCULATIONS. 9446 1451 77 THE DEFORMED OPTICAL POTENTIAL USED: ENERGY DEPENDENCE 9446 1451 78 OF VR AND WD VARIED TO FIT MEASURED TOTAL 9446 1451 79 DATA BY MOORE ET AL./10/ 9446 1451 80 VR=(46.23-0.24*E) MEV RR=1.26 FM AR=0.615 FM 9446 1451 81 WD=(3.61+0.406*E) MEV E < 10 MEV RD=1.24 FM 9446 1451 82 WD= 7.63 MEV E=> 10 MEV AD=0.5 FM 9446 1451 83 VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.194 B4=0.071 9446 1451 84 THREE LEVELS OF ROTATIONAL GROUND STATE BAND 9446 1451 85 ARE COUPLED. 9446 1451 86 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9446 1451 87 MODEL, SEE MT=18-21 9446 1451 88 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9446 1451 89 CONSTANT. 9446 1451 90 ADOPTED LEVEL SCHEME OF PU-242 FROM NUCLEAR DATA 9446 1451 91 SHEETS /11/. 9446 1451 92 9446 1451 93 No ENERGY(MEV) SPIN-PARITY K 9446 1451 94 9446 1451 95 g.s. 0.0 0 + 0 9446 1451 96 1 0.04454 2 + 0 9446 1451 97 2 0.14730 4 + 0 9446 1451 98 3 0.30640 6 + 0 9446 1451 99 4 0.51810 8 + 0 9446 1451 100 5 0.77870 10 + 0 9446 1451 101 6 0.78046 1 - 0 9446 1451 102 7 0.83230 3 - 0 9446 1451 103 8 0.92700 5 - 0 9446 1451 104 9 0.95600 0 + 0 9446 1451 105 10 0.99250 2 + 0 9446 1451 106 11 1.01940 3 - 3 9446 1451 107 12 1.03920 1 + 1 9446 1451 108 13 1.06400 4 - 3 9446 1451 109 14 1.08400 12 + 0 9446 1451 110 15 1.09210 6 + 9446 1451 111 16 1.10200 2 + 2 9446 1451 112 17 1.12200 5 - 3 9446 1451 113 18 1.15010 2 - 9446 1451 114 19 1.15460 3 - 9446 1451 115 20 1.18160 2 + 0 9446 1451 116 9446 1451 117 OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.14 MEV 9446 1451 118 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9446 1451 119 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9446 1451 120 FROM STATISTICAL MODEL CALCULATIONS /12/ WITH THE 9446 1451 121 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219446 1451 122 MT=18,19,20,21. FISSION CROSS SECTION IS CALCULATED WITHIN 9446 1451 123 STATISTICAL MODEL /12,13,14,15/. THE MEASURED DATA BY: 9446 1451 124 KUPRIYANOV ET. AL /16/, MEADOWS /17,18/, BEHRENS /19/, 9446 1451 125 IWASAKI ET AL./20/, KOVALENKO ET AL. /21/ AND FOMUSHKIN 9446 1451 126 ET AL./22/ ARE FITTED. 9446 1451 127 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9446 1451 128 THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION 9446 1451 129 CROSS SECTION ACCORDING TO /13/. 9446 1451 130 9446 1451 131 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9446 1451 132 9446 1451 133 FOR MT=2, 55, 59 FROM COUPLED CHANNELS CALCULATIONS 9446 1451 134 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9446 1451 135 9446 1451 136 MT=16,17,18-21,54-70,91 - ISOTROPIC 9446 1451 137 9446 1451 138 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9446 1451 139 9446 1451 140 ENERGY DISTRIBUTIONS FOR MT=16,17 WERE 9446 1451 141 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9446 1451 142 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9446 1451 143 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9446 1451 144 THE FIRST NEUTRON /23/ 9446 1451 145 ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED 9446 1451 146 WITH ACCOUNT OF COMPETITION 9446 1451 147 BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH 9446 1451 148 THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM9446 1451 149 EMISSION OF THE FIRST NEUTRON /23/. 9446 1451 150 9446 1451 151 REFERENCES 9446 1451 152 1. 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Conf.on Neutron Physics, Kiev, USSR, v.1,p.413 (1988) 9446 1451 186 9446 1451 187 1 451 228 09446 1451 188 1 452 5 09446 1451 189 1 455 7 09446 1451 190 1 456 5 09446 1451 191 2 151 203 09446 1451 192 3 1 27 09446 1451 193 3 2 27 09446 1451 194 3 4 26 09446 1451 195 3 16 10 09446 1451 196 3 17 7 09446 1451 197 3 18 27 09446 1451 198 3 19 27 09446 1451 199 3 20 11 09446 1451 200 3 21 7 09446 1451 201 3 51 26 09446 1451 202 3 52 24 09446 1451 203 3 53 17 09446 1451 204 3 54 16 09446 1451 205 3 55 14 09446 1451 206 3 56 14 09446 1451 207 3 57 14 09446 1451 208 3 58 13 09446 1451 209 3 59 13 09446 1451 210 3 60 12 09446 1451 211 3 61 12 09446 1451 212 3 62 11 09446 1451 213 3 63 11 09446 1451 214 3 64 8 09446 1451 215 3 65 10 09446 1451 216 3 66 10 09446 1451 217 3 67 10 09446 1451 218 3 68 9 09446 1451 219 3 69 9 09446 1451 220 3 70 9 09446 1451 221 3 91 15 09446 1451 222 3 102 21 09446 1451 223 4 2 83 09446 1451 224 4 16 2 09446 1451 225 4 17 2 09446 1451 226 4 18 2 09446 1451 227 4 19 2 09446 1451 228 4 20 2 09446 1451 229 4 21 2 09446 1451 230 4 51 83 09446 1451 231 4 52 77 09446 1451 232 4 53 2 09446 1451 233 4 54 2 09446 1451 234 4 55 2 09446 1451 235 4 56 2 09446 1451 236 4 57 2 09446 1451 237 4 58 2 09446 1451 238 4 59 2 09446 1451 239 4 60 2 09446 1451 240 4 61 2 09446 1451 241 4 62 2 09446 1451 242 4 63 2 09446 1451 243 4 64 2 09446 1451 244 4 65 2 09446 1451 245 4 66 2 09446 1451 246 4 67 2 09446 1451 247 4 68 2 09446 1451 248 4 69 2 09446 1451 249 4 70 2 09446 1451 250 4 91 2 09446 1451 251 5 16 526 09446 1451 252 5 17 252 09446 1451 253 5 18 723 09446 1451 254 5 19 273 09446 1451 255 5 20 230 09446 1451 256 5 21 93 09446 1451 257 5 91 281 09446 1451 258 9446 1 0 259