9237 0 0 0 9.223800+4 2.360060+2 1 1 6 39237 1451 1 0.000000+0 1.000000+0 0 0 0 69237 1451 2 1.000000+0 2.000000+7 0 0 10 39237 1451 3 0.000000+0 0.000000+0 0 0 357 929237 1451 4 92-U -238 EVAL-MARCH2001 9237 1451 5 DIST-MARCH2001 9237 1451 6 ----JENDL-3 MATERIAL 9237 9237 1451 7 -----INCIDENT NEUTRON DATA 9237 1451 8 ------ENDF-6 FORMAT 9237 1451 9 ----B-404-ISTC MATERIAL 9237 9237 1451 10 -----INCIDENT NEUTRON DATA 9237 1451 11 -----ENDF/B-VI FORMAT 9237 1451 12 *****************************************************************9237 1451 13 UNRESOLVED RESONANCE PARAMETERS FOR 10-150 KEV REGION, 9237 1451 14 TOTAL, ELASTIC SCATTERING, INELASTIC SCATTERING, FISSION, 9237 1451 15 CAPTURE,(N,2N), (N,3N) AND (N,4N) CROSS SECTIONS AS WELL AS 9237 1451 16 ANGULAR AND ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE 9237 1451 17 EVALUATED BY V.M. MASLOV, Y.V. PORODZINSKIJ, M. BABA, 9237 1451 18 A. HASEGAWA, N.V. KORNILOV, A.B. KAGALENKO AND 9237 1451 19 N.A. TETEREVA/1/. 9237 1451 20 9237 1451 21 MF=1 GENERAL INFORMATION 9237 1451 22 MT=451 DESCRIPTIVE DATA AND DIRECTORY RECORDS 9237 1451 23 MT=452 NUMBER OF NEUTRONS PER FISSION 9237 1451 24 SUM OF MT'S= 455 AND 456 9237 1451 25 MT=455 DELAYED NEUTRON DATA 9237 1451 26 TAKEN FROM REF./2/. 9237 1451 27 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9237 1451 28 TAKEN FROM EVALUATION BY FREHAUT /3/. 9237 1451 29 9237 1451 30 MF=2 RESONANCE PARAMETERS 9237 1451 31 MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS 9237 1451 32 (RESOLVED RESONANCE REGION = 1.0E-5 EV TO 10 KEV), 9237 1451 33 (UNRESOLVED RESONANCE REGION = 10 KEV TO 150 KEV) 9237 1451 34 1) RESOLVED RESONANCE PARAMETERS (REICH-MOORE)WERE ADOPTED 9237 1451 35 FROM JENDL-3.2 AS ORIGINALLY WERE 9237 1451 36 MODIFIED BY T.NAKAGAWA(JAERI)FOR JENDL-3.2. PREVIOUSLY 9237 1451 37 WERE ADOPTED FROM JEF-2 EVALUATION /4/,THE 9237 1451 38 ENERGY RANGE WAS DIVIDED INTO 10 INTERVALS BY ASSUMING 9237 1451 39 HYPOTHETICAL RESONANCES OUTSIDE EACH INTERVAL. PARAMETERS 9237 1451 40 OF THE HYPOTETICAL RESONANCES WERE DETERMINED BY MEANS OF 9237 1451 41 SAMMY/5/. 9237 1451 42 2) ENERGY-DEPENDENT UNRESOLVED RESONACE PARAMETERS COVER THE 9237 1451 43 ENERGY RANGE 10.0 TO 150 KEV. PARAMETERS WERE OBTAINED SO 9237 1451 44 AS TO REPRODUCE SMOOTH TOTAL AND CAPTURE CROSS SECTIONS AND 9237 1451 45 BROAD STRUCTURE IN FISSION CROSS SECTION DATA BY DIFILIPPO 9237 1451 46 ET AL. /6/. PROCESSING CODES IGNORE DIRECT INELASTIC SCAT- 9237 1451 47 TERING. TO COMPENSATE THAT DEFICIENCY WE INCREASED AVERAGE 9237 1451 48 INELASTIC SCATTERING WIDTHS ABOVE 45 KEV. CAPTURE WIDTHS 9237 1451 49 ABOVE 45 KEV WAS SLIGHTLY INCREASED TO KEEP CAPTURE CROSS 9237 1451 50 SECTION UNDISTORTED AS COMPARED WITH PHYSICALLY CORRECT 9237 1451 51 CODES (PCC). CALCULATED WITH PCC CODES CROSS SECTIONS FIT 9237 1451 52 MEASURED DATA ON TOTAL, CAPTURE AND INELASTIC SCATTERING. 9237 1451 53 FISSION DATA WERE FITTED BY FISSION WIDTH FOR L=0 NEUTRONS. 9237 1451 54 AS A RESULT, TOTAL, ELASTIC SCATTERING,CAPTURE AND FISSION 9237 1451 55 CROSS SECTIONS, CALCULATED WITH THESE PCC CODES, ARE REPRO- 9237 1451 56 DUCED WITH CONVENTIONAL ENDF PROCESSING CODES USING AVERAGE 9237 1451 57 RESONANCE PARAMETERS GIVEN IN MF=2 MT=151. 9237 1451 58 9237 1451 59 2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS. 9237 1451 60 2200 M/S(B) RES. INTEG.(B) 9237 1451 61 TOTAL 12.077 9237 1451 62 ELASTIC 9.360 9237 1451 63 FISSION 11.8E-06 1.72 9237 1451 64 CAPTURE 2.717 277 9237 1451 65 9237 1451 66 MF=3 NEUTRON CROSS SECTIONS 9237 1451 67 BELOW 10 KEV, NO BACKGROUND CROSS SECTIONS WERE GIVEN. 9237 1451 68 ABOVE 10 KEV UP TO 150 KEV CROSS SECTIONS WERE EVALUATED 9237 1451 69 AS FOLLOWS, AND THEY WERE REPRESENTED WITH THE UNRESOLVED 9237 1451 70 RESONANCE PARAMETERS EXCEPT THE FISSION CROSS SECTION. 9237 1451 71 9237 1451 72 MT=1, 2, 4, 51-77, 91 - TOTAL, ELASTIC AND INELASTIC 9237 1451 73 SCATTERING CROSS SECTIONS. 9237 1451 74 TOTAL, ELASTIC AND DIRECT INELASTIC FOR ROTATIONAL GROUND 9237 1451 75 STATE BAND LEVELS MT=51,52,53,54 (COUPLED LEVELS) 9237 1451 76 AND OPTICAL TRANSMISSION COEFFICIENTS ARE OBTAINED 9237 1451 77 IN A RIGID ROTATOR MODEL FROM COUPLED CHANNELS CALCULATIONS. 9237 1451 78 DIRECT EXCITATION OF VIBRATIONAL OCTUPOLE AND K=2+ QUADRUPOLE9237 1451 79 BAND LEVELS,MT=55,56,58,59,62,63,64,66,67,69,71,73, 9237 1451 80 75,76, ARE OBTAINED IN A SOFT ROTATOR MODEL FROM COUPLED 9237 1451 81 CHANNEL CALCULATIONS,FOR NORMALIZATION PURPOSES THESE DIRECT 9237 1451 82 INELASTIC CROSS SECTIONS WERE SUBTRACTED FROM MT=2 ELASTIC 9237 1451 83 SCATTERING CROSS SECTION. 9237 1451 84 DIRECT INELASTIC CONTRIBUTIONS WERE ADDED 9237 1451 85 INCOHERENTLY TO HAUSER-FESHBACH CALCULATIONS OF 9237 1451 86 COMPOUND NUCLEUS INELASTIC SCATTERING CROSS SECTIONS. 9237 1451 87 9237 1451 88 THE DEFORMED OPTICAL POTENTIAL USED: ENERGY DEPENDENCE 9237 1451 89 OF VR AND WD VARIED TO FIT MEASURED TOTAL DATA /7-20/ 9237 1451 90 AND EVALUATED VALUE OF S0=(1.023+-0.02)x10-4(EV)-1/2 9237 1451 91 9237 1451 92 VR=(45.93-0.28xE) MEV; RR =1.26 FM; AR =0.63 FM; 9237 1451 93 WD=( 3.14+0.436xE)MEV; E< 8 MEV RD =1.26 FM; 9237 1451 94 WD= 6.628 MEV; E>= 8 MEV AD =0.52 FM; 9237 1451 95 VSO= 6.2 MEV; RS0=1.12 FM; ASO=0.47 FM; 9237 1451 96 B2= 0.195; B4=0.078; 9237 1451 97 9237 1451 98 9237 1451 99 FISSION, CAPTURE AND COMPOUND INELASTIC SCATTERING CROSS 9237 1451 100 SECTIONS WERE CALCULATED WITH HAUSER-FESHBACH-MOLDAUER/21/ 9237 1451 101 APPROACH, AT INCIDENT NEUTRON ENERGIES HIGHER THAN 1.18 MEV 9237 1451 102 (LEVEL OVERLAPPING ENERGY) TEPEL ET AL./22/ THEORY WAS 9237 1451 103 EMPLOYED. 9237 1451 104 MEASURED DATA ON DISCRETE LEVEL EXCITATION CROSS SECTIONS 9237 1451 105 /23-35/, GROUPS OF LEVELS OF OCTUPOLE AND K=2+ BAND LEVELS 9237 1451 106 /36/ AS WELL AS TOTAL INELASTIC CROSS SECTION /37-39/ WERE 9237 1451 107 TAKEN INTO ACCOUNT. SPECIAL ATTENTION WAS PAID TO 9237 1451 108 DESCRIPTION OF FIRST EXCITED LEVEL MEASURED DATA BY 9237 1451 109 BABA ET AL. /40/ AND MOXON ET AL./41/. 9237 1451 110 9237 1451 111 ADOPTED LEVEL SCHEME OF U-238 FROM NUCLEAR DATA SHEETS /42/. 9237 1451 112 9237 1451 113 9237 1451 114 LEVEL SCHEME: 9237 1451 115 -------------------------------------------------------- 9237 1451 116 NO. ENERGY(MEV) SPIN-PARITY K 9237 1451 117 -------------------------------------------------------- 9237 1451 118 G.S. 0.0 0 + 0 9237 1451 119 1 0.044910 2 + 0 9237 1451 120 2 0.14841 4 + 0 9237 1451 121 3 0.30721 6 + 0 9237 1451 122 4 0.5183 8 + 0 9237 1451 123 5 0.6801 1 - 0 9237 1451 124 6 0.7319 3 - 0 9237 1451 125 7 0.7757 10 + 0 9237 1451 126 8 0.8267 5 - 0 9237 1451 127 9 0.9257 0 + 0 9237 1451 128 10 0.9308 1 - 1 9237 1451 129 11 0.9502 2 - 1 9237 1451 130 12 0.9663 7 - 0 9237 1451 131 13 0.9673 2 + 2 9237 1451 132 14 0.993 0 + 0 9237 1451 133 15 0.9975 3 - 1 9237 1451 134 16 1.0373 2 + 0 9237 1451 135 17 1.0566 4 + 2 9237 1451 136 18 1.0595 3 + 2 9237 1451 137 19 1.0603 2 + 2 9237 1451 138 20 1.0765 12 + 0 9237 1451 139 21 1.1057 3 + 2 9237 1451 140 22 1.1126 1 - 1 9237 1451 141 23 1.1270 4 + 2 9237 1451 142 24 1.1287 2 - 1 9237 1451 143 25 1.1503 9 - 0 9237 1451 144 26 1.1680 4 + 2 9237 1451 145 27 1.1704 3 - 1 9237 1451 146 OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.18 MEV 9237 1451 147 9237 1451 148 9237 1451 149 MT=16,17,37. (N,2N), (N,3N) AND (N,4N) CROSS SECTION FROM 9237 1451 150 STATISTICAL MODEL CALCULATIONS /1/ WITH THE ACCOUNT OF 9237 1451 151 PRE-EQUILIBRIUM NEUTRON EMISSION (MODIFIED STAPRE CODE/43/ 9237 1451 152 WAS USED). MEASURED (N,2N) DATA BY /44-53/, 9237 1451 153 ESPECIALYL DATA BY KORNILOV ET AL./44/ AS WELL AS (N,3N) 9237 1451 154 DATA BY VEESER ET AL. /50/ AND FREHAUT ET AL. /45/ WERE 9237 1451 155 CONSISTENTLY REPRODUCED, WHILE CALCULATED FISSION CROSS SEC- 9237 1451 156 TION, WHICH DESCRIBES MEASURED DATA BASE, WAS USED AS MAJOR 9237 1451 157 CONSTRAINT. 9237 1451 158 9237 1451 159 MT=18, 19, 20, 21. FISSION CROSS SECTION IS CALCULATED WITHIN 9237 1451 160 STATISTICAL MODEL /1/. FOR FISSION DATA ANALYSIS 9237 1451 161 MEASURED DATA /54-62/ WERE USED. 9237 1451 162 THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 9237 1451 163 CROSS SECTION IS FIXED ACCORDING TO CONSISTENT DESCRIPTION OF9237 1451 164 (N,F) AND (N,XN) REACTION DATA. 9237 1451 165 9237 1451 166 MT=102 CAPTURE 9237 1451 167 CAPTURE CROSS SECTION DATA /63-75/ ARE DESCRIBED WITHIN A 9237 1451 168 STATISTICAL MODEL. ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS 9237 1451 169 ASSUMED TO BE CONSTANT. COMPETITION OF (N,GF) AND (N,GN') 9237 1451 170 REACTIONS IS TAKEN INTO ACCOUNT. 9237 1451 171 RADIATIVE STRENGTH FUNCTION SGO = 0.XXX WAS ADJUSTED 9237 1451 172 TO FIT CAPTURE CROSS SECTION DATA BELOW 10 KEV, EVALUATED 9237 1451 173 BY MOXON ET AL./4/. CAPTURE CROSS SECTION DATA AT HIGHER 9237 1451 174 ENERGIES WERE DESCRIBED WITHOUT ANY OTHER FITTING 9237 1451 175 PARAMETERS. 9237 1451 176 9237 1451 177 9237 1451 178 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9237 1451 179 FOR MT=2,51,52,53 AND 54 FROM COUPLED CHANNEL CALCULATIONS 9237 1451 180 (RIGID ROTATOR MODEL), 9237 1451 181 FOR MT=55,56,58,59,62,63,64,66,67,69,71,73,75,76 FROM 9237 1451 182 COUPLED CHANNEL MODEL (SOFT ROTATOR MODEL) 9237 1451 183 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9237 1451 184 9237 1451 185 MT=16, 17, 18-21, 37,38, 57-61,65,68,70,72,74,77, 91 ARE 9237 1451 186 ISOTROPIC IN THE LAB SYSTEM. 9237 1451 187 9237 1451 188 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9237 1451 189 9237 1451 190 ENERGY DISTRIBUTIONS FOR MT=16,17,38,91 WERE CALCULATED BY 9237 1451 191 STATISTICAL MODEL OF CASCADE NEUTRON EMISSION TAKING INTO 9237 1451 192 ACCOUNT THE HISTORY OF THE DECAY WITH THE ALLOWANCE OF PRE- 9237 1451 193 EQUILIBRIUM EMISSION OF THE FIRST NEUTRON. MEASURED NEUTRON 9237 1451 194 EMISSION SPECTRA DATA BY BABA ET AL./76,77/ AND KORNILOV 9237 1451 195 ET AL /78/ WERE REPRODUCED. 9237 1451 196 MT=18,19,20,21,37 9237 1451 197 PROMPT FISSION NEUTRON SPECTRA WERE CALCULATED AS DESCRIBED 9237 1451 198 IN MASLOV E.A. PHYS. REV. C68, 034607 (2004),MASLOV E.A.EURO-9237 1451 199 PHYS JOURN. A18, 93 (2003), PRE-FISSION NEUTRON EMISSION IN 9237 1451 200 (N,XNF) REACTION, EITHER EQUILIBRIUM AND PRE-EQUILIBRIUM 9237 1451 201 MODES ARE INCLUDED. BASICALLY PFNS FROM FISSION 9237 1451 202 FRAGMENTS (FF) WERE CALCULATED AS A SUPERPOSITION OF TWO 9237 1451 203 WATT DISTRIBUTIONS FOR LIGHT AND HEAVY FF WITH EQUAL 9237 1451 204 CONTRIBUTIONS, BUT DIFFERENT TEMPERATURE PARAMETERS. 9237 1451 205 FF KINETIC ENERGY, ONE MORE MODEL PARAMETER, MIGHT BE LOWER 9237 1451 206 THAN TKE, WHICH REFLECTS IT'S DEPENDENS ON THE MOMENT OF 9237 1451 207 NEUTRON EMISSION. 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