94- Pu-238 9434 0 0 0 9.42380+ 4 2.36005+02 1 1 0 19434 1451 1 0.00000+ 0 1.00000+ 0 0 0 0 69434 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 69434 1451 3 0.00000+ 0 0.00000+ 0 0 0 184 699434 1451 4 94-Pu-238 MINSK BYEL EVAL-MAY97 9434 1451 5 DIST-JULY97 9434 1451 6 9434 1451 7 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9434 1451 8 Yu.V. PORODZINSKIJ, G.B. MOROGOVSKIJ 9434 1451 9 9434 1451 10 STATUS 9434 1451 11 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9434 1451 12 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9434 1451 13 FINANCING PARTY OF THE ISTC FOR THE PROJECT IS JAPAN. 9434 1451 14 EVALUATION WAS REQUESTED BY JNDC (JAERI, TOKAI) 9434 1451 15 DOCUMENTED IN INDC(BLR)-009, 1997. 9434 1451 16 9434 1451 17 MF=1 GENERAL INFORMATION 9434 1451 18 9434 1451 19 MT=451 COMMENTS AND DICTIONARY 9434 1451 20 MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION 9434 1451 21 SUM OF MT=455 AND MT=456. 9434 1451 22 MT=455 DELAYED NEUTRON DATA 9434 1451 23 NUMBER OF DELAYED NEUTRONS AND 9434 1451 24 DECAY CONSTANTS FROM TUTTLE /1/ AND BRADY ET AL./2/ 9434 1451 25 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9434 1451 26 ABOVE EMISSIVE FISSION THRESHOLD IS A 9434 1451 27 SUPERPOSITION OF NEUTRON EMISSION 9434 1451 28 IN (N,XNF) REACTIONS AND PROMPT FISSION 9434 1451 29 NEUTRONS. 9434 1451 30 9434 1451 31 MF=2 RESONANCE PARAMETERS 9434 1451 32 9434 1451 33 MT=151 RESONANCE PARAMETERS (MLBW) 9434 1451 34 RESOLVED RESONANCE REGION : 1.0E-5 - 500 EV 9434 1451 35 PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED UPON 9434 1451 36 THE TOTAL CROSS SECTION MEASUREMENT BY YOUNG /3/; 9434 1451 37 THE FISSION CROSS SECTION MEASUREMENTS OF SILBERT 9434 1451 38 /4/, STUBBINS /5/, BUDTZ-JOERGENSEN /6/, ALAM /7/, 9434 1451 39 GERASIMOV /8/, DRAKE /9/; CAPTURE CROSS 9434 1451 40 SECTION MEASUREMENT SILBERT /10/. 9434 1451 41 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9434 1451 42 INTEGRALS ARE: 9434 1451 43 2200 M/SEC RES.INTEG. 9434 1451 44 TOTAL 579.544 b - 9434 1451 45 ELASTIC 21.965 b - 9434 1451 46 FISSION 16.601 b 28.4497 9434 1451 47 CAPTURE 540.978 b 141.765 9434 1451 48 9434 1451 49 UNRESOLVED RESONANCE REGION : 9434 1451 50 ENERGY INDEPENDENT PARAMETERS: 9434 1451 51 R=9.238 FM FROM OPTICAL MODEL CALCULATIONS 9434 1451 52 S1=2.399*10-4 FROM OPTICAL MODEL CALCULATIONS 9434 1451 53 S2=1.242*10-4 FROM OPTICAL MODEL CALCULATIONS 9434 1451 54 ENERGY DEPENDENT PARAMETERS: 9434 1451 55 S0-DECREASES FROM 1.036-4(0.50KEV) TO 0.968-4(44.27KEV)9434 1451 56 FISSION WIDTH FLUCTUATES TO FIT FISSION CROSS SECTION. 9434 1451 57 D - SPIN DEPENDENT, NORMALIZED TO =8.301 EV 9434 1451 58 WITH ACCOUNT OF LEVEL MISSING /11/. 9434 1451 59 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9434 1451 60 SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED 9434 1451 61 TO = 34 mEV TO FIT UNRESOLVED RESONANCE REGION 9434 1451 62 EXPERIMENTAL FISSION DATA. 9434 1451 63 WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND 9434 1451 64 NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA- 9434 1451 65 LIZED TO = 0.03485 EV. 9434 1451 66 9434 1451 67 MF=3 NEUTRON CROSS SECTIONS 9434 1451 68 9434 1451 69 MT=1,4,51-69,91,102. TOTAL, ELASTIC AND INELASTIC 9434 1451 70 SCATTERING, CAPTURE CROSS SECTION 9434 1451 71 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51, 9434 1451 72 52,53 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9434 1451 73 COUPLED CHANNELS CALCULATIONS. 9434 1451 74 THE DEFORMED OPTICAL POTENTIAL USED: 9434 1451 75 VR=(46.26-0.3*E) MEV RR=1.26 FM AR=0.615 FM 9434 1451 76 WD=(3.63+0.4*E) MEV E < 10 MEV RD=1.24 FM 9434 1451 77 WD= 7.63 MEV E=> 10 MEV AD=0.5 FM 9434 1451 78 VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.197 B4=0.061 9434 1451 79 FOUR LEVELS OF ROTATIONAL GROUND STATE BAND 9434 1451 80 ARE COUPLED. 9434 1451 81 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9434 1451 82 MODEL, SEE MT=18-21 9434 1451 83 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9434 1451 84 CONSTANT. 9434 1451 85 ADOPTED LEVEL SCHEME OF PU-238 FROM NUCLEAR DATA 9434 1451 86 SHEETS /12/. 9434 1451 87 9434 1451 88 No ENERGY(MEV) SPIN-PARITY K 9434 1451 89 9434 1451 90 g.s. 0.0 0 + ? 9434 1451 91 1 0.04408 2 + ? 9434 1451 92 2 0.14598 4 + ? 9434 1451 93 3 0.30340 6 + ? 9434 1451 94 4 0.51347 8 + ? 9434 1451 95 5 0.60518 1 - 5 9434 1451 96 6 0.66143 3 - 6 9434 1451 97 7 0.76320 5 - 0 9434 1451 98 8 0.77280 10 + 0 9434 1451 99 9 0.94150 0 + 5 9434 1451 100 10 0.96277 1 - 9434 1451 101 11 0.96810 2 - 6 9434 1451 102 12 0.98310 2 + 1 9434 1451 103 13 0.98546 2 - 1 9434 1451 104 14 1.02855 2 + 1 9434 1451 105 15 1.06995 3 + 3 9434 1451 106 16 1.07850 12 + 0 9434 1451 107 17 1.08257 4 - 0 9434 1451 108 18 1.12580 4 + 9434 1451 109 19 1.13400 0 + 1 9434 1451 110 9434 1451 111 9434 1451 112 OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.14 MEV 9434 1451 113 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9434 1451 114 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9434 1451 115 FROM STATISTICAL MODEL CALCULATIONS /13/ WITH THE 9434 1451 116 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219434 1451 117 MT=18,19,20,21. FISSION CROSS SECTION IS CALCULATED WITHIN 9434 1451 118 STATISTICAL MODEL /14,15,16/ THE MEASURED DATA BY: 9434 1451 119 BUDTZ-JORGENSEN /6/, ALAM ET AL. /7/, 9434 1451 120 ERMAGAMBETOV ET AL./17,18/, FOMUSHKIN ET AL./19,20/, 9434 1451 121 ARE FITTED. 9434 1451 122 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9434 1451 123 THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION 9434 1451 124 CROSS SECTION ACCORDING TO /14/. 9434 1451 125 9434 1451 126 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9434 1451 127 9434 1451 128 FOR MT=2, 55, 59 FROM COUPLED CHANNELS CALCULATIONS 9434 1451 129 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9434 1451 130 9434 1451 131 MT=16,17,18-21,54-69,91 - ISOTROPIC 9434 1451 132 9434 1451 133 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9434 1451 134 9434 1451 135 ENERGY DISTRIBUTIONS FOR MT=16,17 WERE 9434 1451 136 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9434 1451 137 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9434 1451 138 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9434 1451 139 THE FIRST NEUTRON /21/ 9434 1451 140 ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED 9434 1451 141 WITH ACCOUNT OF COMPETITION 9434 1451 142 BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH 9434 1451 143 THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM9434 1451 144 EMISSION OF THE FIRST NEUTRON /21 /. 9434 1451 145 9434 1451 146 REFERENCES 9434 1451 147 1. 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