95 - Am - 243 9543 0 0 0 9.52430+ 4 2.409730+2 1 1 0 19543 1451 1 0.000000+0 0.000000+0 0 0 0 69543 1451 2 1.000000+0 0.000000+0 0 0 10 69543 1451 3 0.000000+0 0.000000+0 0 0 184 519543 1451 4 95-Am-243 MINSK BYEL EVAL-JUL96 9543 1451 5 DIST-SEPTEMBER96 9543 1451 6 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9543 1451 7 Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ, 9543 1451 8 G.B. MOROGOVSKIJ 9543 1451 9 STATUS 9543 1451 10 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9543 1451 11 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9543 1451 12 FINANCING PARTY OF THE CENTER FOR THE PROJECT IS JAPAN. 9543 1451 13 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI) 9543 1451 14 DOCUMENTED IN INDC(BLR)-006, 1996. 9543 1451 15 9543 1451 16 MF=1 GENERAL INFORMATION 9543 1451 17 9543 1451 18 MT=451 COMMENTS AND DICTIONARY 9543 1451 19 MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION 9543 1451 20 SUM OF MT=455 AND MT=456. 9543 1451 21 MT=455 DELAYED NEUTRON DATA 9543 1451 22 NUMBER OF DELAYED NEUTRONS AND 9543 1451 23 DECAY CONSTANTS FROM BRADY ET AL./1 / 9543 1451 24 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9543 1451 25 MADLAND-NIX MODEL CALCULATIONS /2/ FITTED TO 9543 1451 26 THE MEASURED DATA OF KHOKHLOV ET AL. /3/ AND 9543 1451 27 FREHAUT ET AL. /4/. ABOVE EMISSIVE FISSION 9543 1451 28 THRESHOLD A SUPERPOSITION OF NEUTRON EMISSION 9543 1451 29 IN (N,XNF) REACTIONS /5/ AND PROMPT FISSION 9543 1451 30 NEUTRONS IS EMPLOYED. 9543 1451 31 9543 1451 32 MF=2 RESONANCE PARAMETERS 9543 1451 33 9543 1451 34 MT=151 RESONANCE PARAMETERS (MLBW) 9543 1451 35 RESOLVED RESONANCE REGION : 1.0E-5 - 250 EV 9543 1451 36 PARAMETERS FOR BREIT -WIGNER FORMULA ARE BASED UPON 9543 1451 37 THE TOTAL CROSS SECTION MEASUREMENTS OF BERRETH ET AL. 9543 1451 38 /6/ AND SIMPSON ET AL./7/, FISSION CROSS SECTION 9543 1451 39 MEASUREMENTS OF KNITTER ET AL./8/ AND SEEGER/9/. 9543 1451 40 THE LATTER BEING NORMALIZED TO GIVE =0.228mEV 9543 1451 41 9543 1451 42 THERMAL TOTAL BASED ON BERRETH ET AL./6/. 9543 1451 43 THERMAL FISSION BASED ON DATA OF HULET ET AL./10/, 9543 1451 44 BELANOVA ET AL./11/, ASGHAR AT AL./12/ AND WAGEMANS 9543 1451 45 ET AL./13/. 9543 1451 46 THERMAL CAPTURE BASED ON BUTLER ET AL./14/, 9543 1451 47 BAK ET AL./15/ AND FOLGER ET AL./16/. 9543 1451 48 9543 1451 49 CALCULATED THERMAL CROSS SECTIONS AND RESONANCE 9543 1451 50 INTEGRALS ARE: 9543 1451 51 2200 M/SEC RES.INTEG. 9543 1451 52 TOTAL 84.2330 b - 9543 1451 53 ELASTIC 7.4642 b - 9543 1451 54 FISSION 0.0638 b 7.436 9543 1451 55 CAPTURE 76.7050 b 1788.150 9543 1451 56 UNRESOLVED RESONANCE REGION : 0.25 - 42.3751 KEV. 9543 1451 57 ENERGY INDEPENDENT PARAMETERS: 9543 1451 58 R=9.11891 FM FROM OPTICAL MODEL CALCULATIONS 9543 1451 59 S1=2.176*10-4 FROM OPTICAL MODEL CALCULATIONS 9543 1451 60 S2=1.059*10-4 FROM OPTICAL MODEL CALCULATIONS 9543 1451 61 ENERGY DEPENDENT PARAMETERS: 9543 1451 62 S0 -DECREASES FROM .873-4 (0.15KEV) TO .834-4 (42.4KEV)9543 1451 63 D - SPIN DEPENDENT, NORMALIZED TO =0.566 EV 9543 1451 64 WITH ACCOUNT OF LEVEL MISSING /17/ 9543 1451 65 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9543 1451 66 SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED 9543 1451 67 TO =0.228 mEV TO FIT UNRESOLVED RESONANCE REGION9543 1451 68 EXPERIMENTAL FISSION DATA /8,18/. 9543 1451 69 WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND 9543 1451 70 NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA- 9543 1451 71 LIZED TO = 0.043 EV.( FITTS /18,19/). 9543 1451 72 9543 1451 73 MF=3 NEUTRON CROSS SECTIONS 9543 1451 74 9543 1451 75 MT=1,4,51-60,91,102. TOTAL, ELASTIC AND INELASTIC 9543 1451 76 SCATTERING, CAPTURE CROSS SECTION 9543 1451 77 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51, 9543 1451 78 53,56 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9543 1451 79 COUPLED CHANNELS CALCULATIONS. 9543 1451 80 THE DEFORMED OPTICAL POTENTIAL USED: 9543 1451 81 VR=(46.04-0.3*E) MEV RR=1.26 FM AR=0.615 FM 9543 1451 82 WD=(3.50+0.4*E) MEV E < 10 MEV RD=1.24 FM 9543 1451 83 WD= 7.50 MEV E=> 10 MEV AD=0.5 FM 9543 1451 84 VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.180 B4=0.086 9543 1451 85 FOUR LOWER LEVELS OF GROUND STATE ROTATIONAL BAND 9543 1451 86 ARE COUPLED. 9543 1451 87 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9543 1451 88 MODEL, SEE MT=18-21 9543 1451 89 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9543 1451 90 0.001 BARN AS PREDICTED BY DIRECT AND SEMI-DIRECT 9543 1451 91 CAPTURE CALCULATIONS 9543 1451 92 ADOPTED LEVEL SCHEME OF AM-243 FROM NUCLEAR DATA 9543 1451 93 SHEETS /20/ 9543 1451 94 9543 1451 95 No ENERGY(MEV) SPIN-PARITY K 9543 1451 96 g.s. 0.0 5/2 - 5/2 9543 1451 97 1 0.0422 7/2 - 5/2 9543 1451 98 2 0.084 5/2 + 5/2 9543 1451 99 3 0.0964 9/2 - 5/2 9543 1451 100 4 0.1092 7/2 + 5/2 9543 1451 101 5 0.1435 9/2 + 5/2 9543 1451 102 6 0.1623 11/2 - 5/2 9543 1451 103 7 0.1893 11/2 + 5/2 9543 1451 104 8 0.238 13/2 - 5/2 9543 1451 105 9 0.244 13/2 + 5/2 9543 1451 106 10 0.266 3/2 - 5/2 9543 1451 107 9543 1451 108 9543 1451 109 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.267 MEV 9543 1451 110 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9543 1451 111 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9543 1451 112 FROM STATISTICAL MODEL CALCULATIONS /21/ WITH THE 9543 1451 113 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219543 1451 114 MT=18,19,20,21. FISSION CROSS SECTION IS CALCULATED WITHIN 9543 1451 115 STATISTICAL MODEL /22,23/, THE MEASURED DATA OF: 9543 1451 116 WISSHAK ET AL./18/, KNITTER ET AL. /8/, 9543 1451 117 FURSOV ET AL./24/ ARE FITTED. 9543 1451 118 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9543 1451 119 THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION 9543 1451 120 CROSS SECTION ACCORDING TO /22,25/. 9543 1451 121 9543 1451 122 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9543 1451 123 9543 1451 124 FOR MT=2,51,53,56 FROM COUPLED CHANNELS CALCULATIONS 9543 1451 125 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9543 1451 126 9543 1451 127 MT=16,17,18-21,52,54,55,57-60,91 - ISOTROPIC 9543 1451 128 9543 1451 129 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9543 1451 130 9543 1451 131 ENERGY DISTRIBUTIONS FOR MT=16,17 WERE 9543 1451 132 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9543 1451 133 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9543 1451 134 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9543 1451 135 THE FIRST NEUTRON /5/ 9543 1451 136 ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED 9543 1451 137 BY MADLAND-NIX MODEL /2/ WITH ACCOUNT OF COMPETITION 9543 1451 138 BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH 9543 1451 139 THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM9543 1451 140 EMISSION OF THE FIRST NEUTRON /5,21/ 9543 1451 141 9543 1451 142 REFERENCES 9543 1451 143 9543 1451 144 1. 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JAERI-Research 96-030, 1996. 9543 1451 187 9543 1451 188 1 451 239 19543 1451 189 1 452 8 19543 1451 190 1 455 7 19543 1451 191 1 456 8 19543 1451 192 2 151 586 19543 1451 193 3 1 22 19543 1451 194 3 2 22 19543 1451 195 3 4 21 19543 1451 196 3 16 9 19543 1451 197 3 17 7 19543 1451 198 3 18 22 19543 1451 199 3 19 22 19543 1451 200 3 20 10 19543 1451 201 3 21 6 19543 1451 202 3 51 21 19543 1451 203 3 52 14 19543 1451 204 3 53 19 19543 1451 205 3 54 13 19543 1451 206 3 55 13 19543 1451 207 3 56 18 19543 1451 208 3 57 12 19543 1451 209 3 58 12 19543 1451 210 3 59 11 19543 1451 211 3 60 11 19543 1451 212 3 91 16 19543 1451 213 3 102 17 19543 1451 214 4 2 85 19543 1451 215 4 16 2 19543 1451 216 4 17 2 19543 1451 217 4 18 2 19543 1451 218 4 19 2 19543 1451 219 4 20 2 19543 1451 220 4 21 2 19543 1451 221 4 51 85 19543 1451 222 4 52 2 19543 1451 223 4 53 81 19543 1451 224 4 54 2 19543 1451 225 4 55 2 19543 1451 226 4 56 76 19543 1451 227 4 57 2 19543 1451 228 4 58 2 19543 1451 229 4 59 2 19543 1451 230 4 60 2 19543 1451 231 4 91 2 19543 1451 232 5 16 230 19543 1451 233 5 17 81 19543 1451 234 5 18 610 19543 1451 235 5 19 522 19543 1451 236 5 20 414 19543 1451 237 5 21 206 19543 1451 238 5 91 260 19543 1451 239 9543 1 0 240