9219 0 0 0 9.22320+ 4 2.30044+ 2 1 1 0 29219 1451 1 0.00000+ 0 1.00000+ 0 0 0 0 69219 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 69219 1451 3 0.00000+ 0 0.00000+ 0 0 0 200 559219 1451 4 92-U-232 EVAL-January2002 9219 1451 5 DIST-February2002 9219 1451 6 ----B-404-ISTC MATERIAL 9219 9219 1451 7 -----INCIDENT NEUTRON DATA 9219 1451 8 -----ENDF/B-VI FORMAT 9219 1451 9 *****************************************************************9219 1451 10 REICH-MOORE RESOLVED RESONANCE PARAMETERS,RECOMMENDED IN 9219 1451 11 BNL-325 FROM 1.0E-5 UP TO 200 Ev WERE UPDATED, 9219 1451 12 UNRESOLVED RESONANCE PARAMETERS FOR .2-150 KEV REGION, 9219 1451 13 TOTAL, ELASTIC SCATTERING, INELASTIC SCATTERING, FISSION, 9219 1451 14 CAPTURE,(N,2N) AND (N,3N) CROSS SECTIONS AS WELL AS 9219 1451 15 ANGULAR AND ENERGY DISTRIBUTIONS OF SECONDARY AND PROMPT 9219 1451 16 FISSION NEUTRONS WERE EVALUATED BY 9219 1451 17 V.M. MASLOV, Yu.V. PORODZINSKIJ, N.A. TETEREVA, 9219 1451 18 M. BABA, A. HASEGAWA, 9219 1451 19 N.V. KORNILOV, A.B. KAGALENKO /1/. 9219 1451 20 9219 1451 21 9219 1451 22 MF=1 GENERAL INFORMATION 9219 1451 23 MT=451 DESCRIPTIVE DATA AND DIRECTORY RECORDS 9219 1451 24 MT=452 NUMBER OF NEUTRONS PER FISSION 9219 1451 25 SUM OF MT'S= 455 AND 456 9219 1451 26 MT=455 DELAYED NEUTRON DATA TAKEN FROM REF./2/. 9219 1451 27 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9219 1451 28 CALCULATED WITH THE EMISSIVE FISSION MODEL. BELOW EMIS- 9219 1451 29 FISSION THRESHOLD NU-BAR IS ESTIMATED WITH SYSTEMATICS. 9219 1451 30 9219 1451 31 MF=2 RESONANCE PARAMETERS 9219 1451 32 MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS 9219 1451 33 (RESOLVED RESONANCE REGION = 1.0E-5 EV TO 200 EV), 9219 1451 34 (UNRESOLVED RESONANCE REGION = .2 KEV TO 150 KEV) 9219 1451 35 1) RESOLVED REICH-MOORE RESONANCE PARAMETERS RECOMMENDED 9219 1451 36 IN BNL-325 /3/ WERE UPDATED TO DESCRIBE FISSION CROSS 9219 1451 37 SECTION DATA BY AUCHAMPAUGH ET AL./4/ AND TOTAL CROSS SEC-9219 1451 38 TION DATA BY SIMPSON ET AL. /5/. SIGNS ATTRIBUTED TO 9219 1451 39 FISSION WIDTHS WERE FIXED TO FIT CROSS SECTIONS FOR 9219 1451 40 VALLEIES BETWEEN RESONANCES. 9219 1451 41 2) ENERGY-DEPENDENT UNRESOLVED RESONANCE PARAMETERS COVER 9219 1451 42 ENERGY RANGE FROM 0.2 TO 150 KEV. PARAMETERS WERE OBTAINED9219 1451 43 TO REPRODUCE SMOOTH TOTAL AND CAPTURE CROSS SECTIONS, 9219 1451 44 CALCULATED WITH STATISTICAL MODEL. ENDF/B PROCESSING 9219 1451 45 CODES /6,7/ IGNORE DIRECT INELASTIC SCATTERING. 9219 1451 46 TO COMPENSATE THAT DEFICIENCY WE INCREASED AVERAGE 9219 1451 47 INELASTIC SCATTERING WIDTHS, CAPTURE WIDTHS ABOVE 50 KEV 9219 1451 48 ALSO WAS SLIGHTLY INCREASED TO KEEP CAPTURE CROSS SECTION 9219 1451 49 UNDISTORTED AS COMPARED WITH CALCULATED BY PHYSICALLY 9219 1451 50 CORRECT (PC) CODES. AS A RESULT, TOTAL,ELASTIC 9219 1451 51 SCATTERING AND CAPTURE CROSS SECTIONS, CALCULATED WITH 9219 1451 52 THESE PCC CODES,ARE REPRODUCED WITH CONVENTIONAL ENDF 9219 1451 53 PROCESSING CODES USING AVERAGE RESONANCE PARAMETERS GIVEN 9219 1451 54 IN MF=2 MT=151. 9219 1451 55 9219 1451 56 2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS. 9219 1451 57 2200 M/S(B) RES. INTEG.(B) 9219 1451 58 TOTAL 163.45 9219 1451 59 ELASTIC 10.37 9219 1451 60 FISSION 77.61 370.18 9219 1451 61 CAPTURE 75.47 184.44 9219 1451 62 9219 1451 63 MF=3 NEUTRON CROSS SECTIONS 9219 1451 64 FROM 0.2 KEV UP TO 150 KEV EVALUATED CROSS SECTIONS WERE 9219 1451 65 REPRESENTED WITH THE UNRESOLVED RESONANCE PARAMETERS. 9219 1451 66 9219 1451 67 MT= 1, 2, 4, 51-62, 91 - TOTAL, ELASTIC AND INELASTIC 9219 1451 68 SCATTERING CROSS SECTIONS. 9219 1451 69 TOTAL, ELASTIC AND DIRECT INELASTIC FOR ROTATIONAL GROUND 9219 1451 70 STATE BAND LEVELS MT=51,52,53,54 (COUPLED LEVELS) 9219 1451 71 AS WELL AS OPTICAL TRANSMISSION COEFFICIENTS ARE OBTAINED 9219 1451 72 IN A RIGID ROTATOR MODEL COUPLED CHANNELS CALCULATIONS. 9219 1451 73 DIRECT EXCITATION OF VIBRATIONAL,OCTUPOLE AND K=2+ QUADRUPOLE9219 1451 74 BAND LEVELS,MT=55,56,57,58,59,61,62 ARE OBTAINED IN A SOFT 9219 1451 75 ROTATOR MODEL COUPLED CHANNEL CALCULATIONS, FOR NORMALIZATION9219 1451 76 PURPOSES THESE DIRECT INELASTIC CROSS SECTIONS WERE SUBTRAC- 9219 1451 77 TED FROM MT=2 ELASTIC SCATTERING CROSS SECTION. DIRECT INE- 9219 1451 78 LASTIC CONTRIBUTIONS WERE ADDED INCOHERENTLY TO 9219 1451 79 HAUSER-FESHBACH CALCULATIONS OF COMPOUND NUCLEUS INELASTIC 9219 1451 80 SCATTERING CROSS SECTIONS. 9219 1451 81 9219 1451 82 THE DEFORMED OPTICAL POTENTIAL ADOPTED WAS THAT FOR 232Th, 9219 1451 83 THEN EVALUATED VALUE OF S-WAVE STRENGTH FUBCTION 9219 1451 84 S0= 1.18x10-4(EV)-1/2 WAS FITTED: 9219 1451 85 9219 1451 86 VR=(45.722-0.334xE) MEV; RR =1.2668 FM; AR =.6468 FM; 9219 1451 87 WD=(3.145+0.455xE)MEV; E< 8 MEV RD =1.25 FM; 9219 1451 88 WD= 6.785 MEV; E>= 8 MEV AD =.5246 FM; 9219 1451 89 VSO= 6.2 MEV; RS0=1.12 FM; ASO=.47 FM; 9219 1451 90 B2= .220; B4=.091; 9219 1451 91 9219 1451 92 9219 1451 93 FISSION, CAPTURE AND COMPOUND INELASTIC SCATTERING CROSS 9219 1451 94 SECTIONS WERE CALCULATED WITH HAUSER-FESHBACH-MOLDAUER/8/ 9219 1451 95 APPROACH, AT INCIDENT NEUTRON ENERGIES HIGHER THAN 0.868 MEV 9219 1451 96 (LEVEL OVERLAPPING ENERGY) TEPEL ET AL./9/ THEORY WAS 9219 1451 97 EMPLOYED. 9219 1451 98 9219 1451 99 ADOPTED LEVEL SCHEME OF Th-232 FROM NUCLEAR DATA SHEETS /10/.9219 1451 100 9219 1451 101 9219 1451 102 LEVEL SCHEME: 9219 1451 103 -------------------------------------------------------- 9219 1451 104 NO. ENERGY(MEV) SPIN-PARITY K-PARITY 9219 1451 105 -------------------------------------------------------- 9219 1451 106 9219 1451 107 G.S. 0000000+00 0 + 0+ 9219 1451 108 .4757200-01 2 + 0+ 9219 1451 109 .1565700-00 4 + 0+ 9219 1451 110 .3226000-00 6 + 0+ 9219 1451 111 .5410000+00 8 + 0+ 9219 1451 112 .5631940+00 1 1- 9219 1451 113 .6289670+00 3 - 1- 9219 1451 114 .6912100+00 0 + 0+ 9219 1451 115 .7345600+00 2 + 0+ 9219 1451 116 .7469000+00 5 - 1- 9219 1451 117 .8058000+00 10 + 0+ 9219 1451 118 .8330700+00 4 + 0+ 9219 1451 119 .8667920+00 2 + 2+ 9219 1451 120 9219 1451 121 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.868 MEV 9219 1451 122 9219 1451 123 9219 1451 124 MT=16,17,37. (N,2N) AND (N,3N) CROSS SECTION FROM 9219 1451 125 STATISTICAL MODEL CALCULATIONS /1/ WITH ACCOUNT OF 9219 1451 126 PRE-EQUILIBRIUM NEUTRON EMISSION (MODIFIED STAPRE CODE/11/ 9219 1451 127 WAS USED).PRE-EQUILIBRIUM NEUTRON EMISSION CONTRIBUTION WAS 9219 1451 128 FIXED ACCORDING TO CONSISTENT DESCRIPTION OF(N,F) AND (N,XN) 9219 1451 129 REACTION DATA FOR 238U AND 232Th TARGET NUCLIDES. 9219 1451 130 9219 1451 131 MT=18, 19, 20, 21. FISSION CROSS SECTION IS CALCULATED WITHIN 9219 1451 132 STATISTICAL MODEL /1/. MEASURED FISSION DATA /12,13,14/ 9219 1451 133 ANALYSIS WAS ACCOMPLISHED, CALCULATED FISSION CROSS SECTION 9219 1451 134 REPRODUCES DATA BY FURSOV ET AL. /14/. 9219 1451 135 THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 9219 1451 136 CROSS SECTION WAS ESTIMATED ACCORDING TO (3-He,df) AND 9219 1451 137 (3-He,tf) FISSION PROBABILITY DATA /15/. 9219 1451 138 9219 1451 139 MT=102 CAPTURE 9219 1451 140 CAPTURE CROSS SECTION IS CALCULATED WITHIN A STATISTICAL MO- 9219 1451 141 DEL. ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9219 1451 142 CONSTANT. COMPETITION OF (N,GF) AND (N,GN') REACTIONS IS 9219 1451 143 TAKEN INTO ACCOUNT. 9219 1451 144 9219 1451 145 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9219 1451 146 FOR MT=2,51,52,53 AND 54 FROM COUPLED CHANNEL CALCULATIONS 9219 1451 147 (RIGID ROTATOR MODEL), 9219 1451 148 FOR MT=55,56,57,58,59,61,62 FROM COUPLED CHANNEL MODEL 9219 1451 149 (SOFT ROTATOR MODEL) WITH ADDED ISOTROPIC STATISTICAL CONTRI-9219 1451 150 BUTION. 9219 1451 151 9219 1451 152 MT=16, 17, 18-21, 37,38, 6O AND 91 ARE ISOTROPIC IN THE 9219 1451 153 LAB SYSTEM. 9219 1451 154 9219 1451 155 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9219 1451 156 9219 1451 157 ENERGY DISTRIBUTIONS FOR MT=16,17,38,91 WERE CALCULATED WITH 9219 1451 158 A STATISTICAL MODEL OF CASCADE NEUTRON EMISSION TAKING INTO 9219 1451 159 ACCOUNT THE HISTORY OF THE DECAY WITH THE ALLOWANCE OF PRE- 9219 1451 160 EQUILIBRIUM EMISSION OF THE FIRST NEUTRON. 9219 1451 161 9219 1451 162 MT=18,19,20,21,37 9219 1451 163 PROMPT FISSION NEUTRON SPECTRA (PFNS)WERE CALCULATED WITH THE9219 1451 164 SEMI-EMPIRICAL MODEL/1/, PRE-FISSION NEUTRON EMISSION IN 9219 1451 165 (N,XNF) REACTION, EITHER EQUILIBRIUM AND PRE-EQUILIBRIUM 9219 1451 166 MODES ARE INCLUDED. BASICALLY PFNS FROM FISSION 9219 1451 167 FRAGMENTS (FF) WERE CALCULATED AS A SUPERPOSITION OF TWO 9219 1451 168 WATT DISTRIBUTIONS FOR LIGHT AND HEAVY FF WITH EQUAL 9219 1451 169 CONTRIBUTIONS, BUT DIFFERENT TEMPERATURE PARAMETERS. 9219 1451 170 FF KINETIC ENERGY, ONE MORE MODEL PARAMETER, MIGHT BE LOWER 9219 1451 171 THAN TKE, WHICH REFLECTS IT'S DEPENDENS ON THE MOMENT OF 9219 1451 172 NEUTRON EMISSION. THIS EFFECTIVELY REDUCES AVERAGE 9219 1451 173 ENERGY OF PFNS FOR INCIDENT NEUTRON ENERGIES ABOVE EMISSIVE 9219 1451 174 FISSION THRESHOLD. 9219 1451 175 9219 1451 176 REFERENCES 9219 1451 177 1) Maslov V., Porodzinskij Yu., Baba M.,Hasegawa A., Kornilov 9219 1451 178 N., Kagalenko A.JAERI-Research 01-0XX, 2002. 9219 1451 179 2) Brady M.C. and England T.R., Nucl.Sci. Eng. 103,129 (1989). 9219 1451 180 3) Mughabghab S.F.and Garber D.I., BNL-325, VOL. 1, Brookhaven 9219 1451 181 National Laboratory (2973) 9219 1451 182 4) Auchampaugh G.F., Bowman C.D., Evans J.E., Nucl. 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