9222 0 0 0 9.22330+ 4 2.31038+ 2 1 1 0 29222 1451 1 0.00000+ 0 1.00000+ 0 0 0 0 69222 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 69222 1451 3 0.00000+ 0 0.00000+ 0 0 0 271 829222 1451 4 92-U-233 EVAL-June2003 9222 1451 5 DIST-July2003 9222 1451 6 ----B-404-ISTC MATERIAL 9222 9222 1451 7 -----INCIDENT NEUTRON DATA 9222 1451 8 -----ENDF/B-VI FORMAT 9222 1451 9 *****************************************************************9222 1451 10 UNRESOLVED RESONANCE PARAMETERS FOR 0.6-40 KEV REGION, 9222 1451 11 TOTAL, ELASTIC SCATTERING, INELASTIC SCATTERING, FISSION, 9222 1451 12 CAPTURE,(N,2N) AND (N,3N) CROSS SECTIONS AS WELL AS 9222 1451 13 ANGULAR AND ENERGY DISTRIBUTIONS OF SECONDARY AND PROMPT 9222 1451 14 FISSION NEUTRONS WERE EVALUATED BY 9222 1451 15 V.M. MASLOV, Yu.V. PORODZINSKIJ, N.A. TETEREVA, 9222 1451 16 M. BABA, A. HASEGAWA, 9222 1451 17 N.V. KORNILOV, A.B. KAGALENKO /1/. 9222 1451 18 9222 1451 19 9222 1451 20 MF=1 GENERAL INFORMATION 9222 1451 21 MT=451 DESCRIPTIVE DATA AND DICTIONARY 9222 1451 22 MT=452 NUMBER OF NEUTRONS AND DICTIONARY 9222 1451 23 SUM OF MT=455 and 456. 9222 1451 24 MT=455 DELAYED NEUTRONS PER FISSION 9222 1451 25 ARE ADOPTED FROM JENDL-3.3, WHICH ARE BASED ON DATA BY 9222 1451 26 MASTERS /2/ AND EVANS /3/. 9222 1451 27 9222 1451 28 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9222 1451 29 CALCULATED WITH THE EMISSIVE FISSION MODEL TO FIT 9222 1451 30 MEASURED DATA /4-15/BUT BASICALLY DATA BY FREHAUT 99222 1451 31 ET AL./5/ AND HOWE /9/. FOR INCIDENT NEUTRON ENERGIES 9222 1451 32 HIGHER THAN(N,NF) REACTION THRESHOLD, NU-BAR WAS 9222 1451 33 CALCULATED TAKING INTO ACCOUNT PARTIAL CONTRIBUTIONS 9222 1451 34 OF (N,XNF) REACTIONS /1/. 9222 1451 35 9222 1451 36 MF=2 RESONANCE PARAMETERS 9222 1451 37 MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS 9222 1451 38 (RESOLVED RESONANCE REGION = 1.0E-5 EV TO 600 EV), 9222 1451 39 (UNRESOLVED RESONANCE REGION = 0.6 KEV TO 40.5 KEV) 9222 1451 40 9222 1451 41 RESOLVED R-MATRIX RESONANCE PARAMETERS BY 9222 1451 42 LEAL ET AL. /16/ WERE ADOPTED. 9222 1451 43 9222 1451 44 ENERGY-DEPENDENT UNRESOLVED RESONANCE PARAMETERS COVER 9222 1451 45 ENERGY RANGE FROM 0.6 TO 40.5 KEV. PARAMETERS WERE 9222 1451 46 OBTAINED TO REPRODUCE SMOOTH TOTAL /21/, FISSION /28-35/ 9222 1451 47 AND CAPTURE /46/ CROSS SECTIONS, CALCULATED WITH 9222 1451 48 STATISTICAL MODEL. 9222 1451 49 9222 1451 50 9222 1451 51 2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS. 9222 1451 52 2200 M/S(B) RES. INTEG.(B) 9222 1451 53 TOTAL 588.623 9222 1451 54 ELASTIC 12.1512 9222 1451 55 FISSION 531.232 9222 1451 56 CAPTURE 45.232 9222 1451 57 9222 1451 58 MF=3 NEUTRON CROSS SECTIONS 9222 1451 59 FROM 0.6 KEV UP TO 40.5 KEV EVALUATED CROSS SECTIONS 9222 1451 60 WERE REPRESENTED WITH THE UNRESOLVED RESONANCE 9222 1451 61 PARAMETERS. 9222 1451 62 9222 1451 63 MT= 1, 2, 4, 51-75, 91 - TOTAL, ELASTIC AND INELASTIC 9222 1451 64 SCATTERING CROSS SECTIONS. 9222 1451 65 TOTAL, ELASTIC AND DIRECT INELASTIC FOR ROTATIONAL GROUND 9222 1451 66 STATE BAND LEVELS MT=51,52,53, (COUPLED LEVELS) 9222 1451 67 AS WELL AS OPTICAL TRANSMISSION COEFFICIENTS ARE OBTAINED 9222 1451 68 IN A RIGID ROTATOR MODEL COUPLED CHANNELS CALCULATIONS. 9222 1451 69 DIRECT CONTRIBUTIONS WERE ADDED INCOHERENTLY TO 9222 1451 70 HAUSER-FESHBACH CALCULATIONS OF COMPOUND NUCLEUS INELASTIC9222 1451 71 SCATTERING CROSS SECTIONS. 9222 1451 72 TOTAL /21-26/ AND ELASTIC /27/ DATA WERE REPRODUCED, 9222 1451 73 INELASTIC SCATTERING DATA /27/ WERE ANALYZED. 9222 1451 74 9222 1451 75 THE DEFORMED OPTICAL POTENTIAL ADOPTED WAS THAT FOR 232Th,9222 1451 76 THEN EVALUATED VALUE OF S-WAVE STRENGTH FUNCTION 9222 1451 77 S0= 0.893x10-4(EV)-1/2 WAS FITTED: 9222 1451 78 9222 1451 79 VR=(45.722-0.334xE) MEV; RR =1.2668 FM; AR =.6468 FM; 9222 1451 80 WD=(3.145+0.455xE)MEV; E< 8 MEV RD =1.25 FM; 9222 1451 81 WD= 6.785 MEV; E>= 8 MEV AD =.5246 FM; 9222 1451 82 VSO= 6.2 MEV; RS0=1.12 FM; ASO=.47 FM; 9222 1451 83 B2= .190; B4=.072; 9222 1451 84 9222 1451 85 9222 1451 86 FISSION, CAPTURE AND COMPOUND INELASTIC SCATTERING CROSS 9222 1451 87 SECTIONS WERE CALCULATED WITH HAUSER-FESHBACH-MOLDAUER/17/9222 1451 88 APPROACH, AT INCIDENT NEUTRON ENERGIES HIGHER THAN 0.598 9222 1451 89 MEV (LEVEL OVERLAPPING ENERGY) TEPEL ET AL./18/ THEORY 9222 1451 90 WAS EMPLOYED. 9222 1451 91 9222 1451 92 9222 1451 93 LEVEL SCHEME OF U-233 FROM TABLE OF ISOTOPES /19/ IS 9222 1451 94 ADOPTED. 9222 1451 95 9222 1451 96 9222 1451 97 LEVEL SCHEME: 9222 1451 98 -------------------------------------------------------- 9222 1451 99 NO. ENERGY(MEV) SPIN-PARITY 9222 1451 100 -------------------------------------------------------- 9222 1451 101 .0000000+00 5/2+ 9222 1451 102 .4035000-01 7/2+ 9222 1451 103 .9219000-01 9/2+ 9222 1451 104 .1552700-00 11/2+ 9222 1451 105 .2294000+00 13/2+ 9222 1451 106 .2988500+00 5/2- 9222 1451 107 .3121700+00 3/2+ 9222 1451 108 .3147000+00 15/2+ 9222 1451 109 .3207000+00 7/2- 9222 1451 110 .3406800+00 5/2+ 9222 1451 111 .3538000+00 9/2- 9222 1451 112 .3790000+00 7/2+ 9222 1451 113 .3976000+00 11/2- 9222 1451 114 .3985000+00 1/2+ 9222 1451 115 .4111000+00 17/2+ 9222 1451 116 .4158000+00 3/2+ 9222 1451 117 .4320000+00 9/2+ 9222 1451 118 .4560000+00 5/2+ 9222 1451 119 .4970000+00 11/2+ 9222 1451 120 .5038000+00 7/2- 9222 1451 121 .5177000+00 19/2+ 9222 1451 122 .5222000+00 15/2- 9222 1451 123 .5466000+00 5/2+ 9222 1451 124 .5615000+00 9/2- 9222 1451 125 .5720000+00 1/2- 9222 1451 126 .5972000+00 7/2+ 9222 1451 127 9222 1451 128 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.598 MEV 9222 1451 129 9222 1451 130 9222 1451 131 MT=16,17,37. (N,2N) AND (N,3N) CROSS SECTION FROM 9222 1451 132 STATISTICAL MODEL CALCULATIONS /1/ WITH ACCOUNT OF 9222 1451 133 PRE-EQUILIBRIUM NEUTRON EMISSION (MODIFIED STAPRE CODE/20/ 9222 1451 134 WAS USED). PRE-EQUILIBRIUM NEUTRON EMISSION CONTRIBUTION WAS 9222 1451 135 FIXED ACCORDING TO CONSISTENT DESCRIPTION OF(N,F) AND (N,XN) 9222 1451 136 REACTION DATA FOR 238U AND 232Th TARGET NUCLIDES. 9222 1451 137 9222 1451 138 MT=18, 19, 20, 21,38. FISSION CROSS SECTION IS CALCULATED 9222 1451 139 WITHIN STATISTICAL MODEL /1/. MEASURED FISSION DATA /28-45/ 9222 1451 140 ANALYSIS WAS ACCOMPLISHED. CONTRIBUTION OF EMISSIVE (N,NF) 9222 1451 141 AND (N,2NF) FISSION TO THE TOTAL FISSION CROSS SECTION 9222 1451 142 WAS ESTIMATED USING FISSION BARRIER PARAMETERS OF 233-U AND 9222 1451 143 232-U, WHICH FIT 232-U(N,F) CROSS SECTION DATA 9222 1451 144 DATA. 9222 1451 145 MT=102 CAPTURE 9222 1451 146 CAPTURE CROSS SECTION IS CALCULATED WITHIN A STATISTICAL MO- 9222 1451 147 DEL. MEASURED DATA /46/ ARE REPRODUCED. ABOVE NEUTRON ENERGY 9222 1451 148 OF 5 MEV CAPTURE IS ASSUMED TO BE CONSTANT. COMPETITION OF 9222 1451 149 (N,GF) AND (N,GN') REACTIONS IS TAKEN INTO ACCOUNT. 9222 1451 150 9222 1451 151 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9222 1451 152 FOR MT=2,51,52 AND 53 FROM COUPLED CHANNEL CALCULATIONS 9222 1451 153 (RIGID ROTATOR MODEL), 9222 1451 154 9222 1451 155 MT=16, 17, 18-21, 38, 54-75 AND 91 ANGULAR DISTRIBUTIONS ARE 9222 1451 156 ISOTROPIC 9222 1451 157 9222 1451 158 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9222 1451 159 9222 1451 160 ENERGY DISTRIBUTIONS FOR MT=16,17,91 WERE CALCULATED WITH 9222 1451 161 A HAUSER-FESHBACH STATISTICAL MODEL OF CASCADE NEUTRON 9222 1451 162 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY WITH 9222 1451 163 THE ALLOWANCE OF PREEQUILIBRIUM EMISSION OF THE FIRST 9222 1451 164 NEUTRON, SIMULTANEOUSLY WITH (N,F) AND (N,XNF) REACTION 9222 1451 165 CROSS SECTIONS. 9222 1451 166 9222 1451 167 MT=18,19,20,21,38 9222 1451 168 PROMPT FISSION NEUTRON SPECTRA (PFNS)WERE CALCULATED WITH 9222 1451 169 SEMI-EMPIRICAL MODEL/1/, PRE-FISSION NEUTRON EMISSION IN 9222 1451 170 (N,XNF) REACTION, EITHER EQUILIBRIUM AND PRE-EQUILIBRIUM 9222 1451 171 MODES ARE INCLUDED. SPECTRA OF PRE-FISSION (N,XNF) NEUTRONS 9222 1451 172 ARE CALCULATED WITH HAUSER-FESHBACH STATISTICAL MODEL. 9222 1451 173 MEASURED DATA /47-51/ ARE ANALYZED. LOWERING OF THE AVERAGE 9222 1451 174 ENERGY OF PFNS ABOVE EMISSIVE FISSION THRESHOLD IS PREDICTED.9222 1451 175 BASICALLY PFNS FROM FISSION FRAGMENTS (FF) WERE CALCULATED 9222 1451 176 AS A SUPERPOSITION OF TWO WATT DISTRIBUTIONS FOR LIGHT AND 9222 1451 177 HEAVY FF WITH EQUAL CONTRIBUTIONS, BUT DIFFERENT TEMPERATURE 9222 1451 178 PARAMETERS. FF KINETIC ENERGY, ONE MORE MODEL PARAMETER, 9222 1451 179 MIGHT BE LOWER THAN TKE, WHICH REFLECTS IT'S DEPENDENS ON 9222 1451 180 THE MOMENT OF NEUTRON EMISSION. THIS EFFECTIVELY REDUCES 9222 1451 181 AVERAGE ENERGY OF PFNS FOR INCIDENT NEUTRON ENERGIES ABOVE 9222 1451 182 EMISSIVE FISSION THRESHOLD. 9222 1451 183 9222 1451 184 9222 1451 185 REFERENCES 9222 1451 186 1) Maslov V., Porodzinskij Yu., Baba M.,Hasegawa A., Kornilov 9222 1451 187 N., Kagalenko A., Tetereva N.A. 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