9040 0 0 0 9.02320+04 2.30045+02 1 1 6 39040 1451 1 0.00000+ 0 1.00000+ 0 0 0 0 69040 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 39040 1451 3 0.00000+ 0 0.00000+ 0 0 0 303 999040 1451 4 90-Th-232 EVAL-June2001 9040 1451 5 DIST-July2001 9040 1451 6 ----B-404-ISTC MATERIAL 9040 9040 1451 7 -----INCIDENT NEUTRON DATA 9040 1451 8 -----ENDF/B-VI FORMAT 9040 1451 9 *****************************************************************9040 1451 10 UNRESOLVED RESONANCE PARAMETERS FOR 4-150 KEV REGION, 9040 1451 11 TOTAL, ELASTIC SCATTERING, INELASTIC SCATTERING, FISSION, 9040 1451 12 CAPTURE,(N,2N), (N,3N) AND (N,4N) CROSS SECTIONS AS WELL AS 9040 1451 13 ANGULAR AND ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE 9040 1451 14 EVALUATED BY V.M. MASLOV, Yu.V. PORODZINSKIJ, M. BABA, 9040 1451 15 A. HASEGAWA, N.V. KORNILOV, A.B. KAGALENKO AND 9040 1451 16 N.A. TETEREVA/1/. 9040 1451 17 9040 1451 18 MF=1 GENERAL INFORMATION 9040 1451 19 MT=451 DESCRIPTIVE DATA AND DIRECTORY RECORDS 9040 1451 20 MT=452 NUMBER OF NEUTRONS PER FISSION 9040 1451 21 SUM OF MT'S= 455 AND 456 9040 1451 22 MT=455 DELAYED NEUTRON DATA TAKEN FROM REF./2/. 9040 1451 23 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9040 1451 24 CALCULATED WITH THE EMISSIVE FISSION MODEL TO FIT 9040 1451 25 MEASURED DATA /3-9/, BUT BASICALLY DATA BY FREHAUT 9040 1451 26 ET AL./5/ AND HOWE /9/, IRREGULARITY AROUND(n,nf) 9040 1451 27 REACTION THRESHOLD IS REPRODUCED. 9040 1451 28 9040 1451 29 MF=2 RESONANCE PARAMETERS 9040 1451 30 MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS 9040 1451 31 (RESOLVED RESONANCE REGION = 1.0E-5 EV TO 4 KEV), 9040 1451 32 (UNRESOLVED RESONANCE REGION = 4 KEV TO 150 KEV) 9040 1451 33 1) RESOLVED RESONANCE PARAMETERS (Breit-Wigner)WERE ADOPT9040 1451 34 FROM ENDF/B-VI AS EVALUATED BY OLSEN /10/. 9040 1451 35 2) ENERGY-DEPENDENT UNRESOLVED RESONANCE PARAMETERS COVER9040 1451 36 ENERGY RANGE FROM 4.0 TO 150 KEV. PARAMETERS WERE OBTAINE9040 1451 37 TO REPRODUCE SMOOTH TOTAL AND CAPTURE CROSS SECTIONS, 9040 1451 38 CALCULATED WITH STATISTICAL MODEL. ENDF/B PROCESSING 9040 1451 39 CODES /11,12/ IGNORE DIRECT INELASTIC SCATTERING. 9040 1451 40 TO COMPENSATE THAT DEFICIENCY WE INCREASED AVERAGE 9040 1451 41 INELASTIC SCATTERING WIDTHS, CAPTURE WIDTHS ABOVE 50 KEV 9040 1451 42 ALSO WAS SLIGHTLY INCREASED TO KEEP CAPTURE CROSS SECTION9040 1451 43 UNDISTORTED AS COMPARED WITH CALCULATED BY PHYSICALLY 9040 1451 44 CORRECT CODES (PCC). CALCULATED WITH PCC CODES CROSS 9040 1451 45 SECTIONS FIT MEASURED DATA ON TOTAL, CAPTURE AND INELASTI9040 1451 46 SCATTERING. AS A RESULT, TOTAL,ELASTIC SCATTERING AND 9040 1451 47 CAPTURE CROSS SECTIONS, CALCULATED WITH THESE PCC CODES, 9040 1451 48 ARE REPRODUCED WITH CONVENTIONAL ENDF PROCESSING CODES 9040 1451 49 USING AVERAGE RESONANCE PARAMETERS GIVEN IN MF=2 MT=151. 9040 1451 50 9040 1451 51 2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS. 9040 1451 52 2200 M/S(B) RES. INTEG.(B) 9040 1451 53 TOTAL 12.077 9040 1451 54 ELASTIC 9.360 9040 1451 55 FISSION 11.8E-06 1.72 9040 1451 56 CAPTURE 2.717 277 9040 1451 57 9040 1451 58 MF=3 NEUTRON CROSS SECTIONS 9040 1451 59 BELOW 4 KEV, BACKGROUND CROSS SECTIONS WERE GIVEN FOR TOTAL 9040 1451 60 CROSS SECTION ONLY. 9040 1451 61 ABOVE 4 KEV UP TO 150 KEV EVALUATED CROSS SECTIONS WERE 9040 1451 62 REPRESENTED WITH THE UNRESOLVED RESONANCE PARAMETERS. 9040 1451 63 9040 1451 64 MT= 1, 2, 4, 51-81, 91 - TOTAL, ELASTIC AND INELASTIC 9040 1451 65 SCATTERING CROSS SECTIONS. 9040 1451 66 TOTAL, ELASTIC AND DIRECT INELASTIC FOR ROTATIONAL GROUND 9040 1451 67 STATE BAND LEVELS MT=51,52,53,54 (COUPLED LEVELS) 9040 1451 68 AS WELL AS OPTICAL TRANSMISSION COEFFICIENTS ARE OBTAINED 9040 1451 69 IN A RIGID ROTATOR MODEL COUPLED CHANNELS CALCULATIONS. 9040 1451 70 DIRECT EXCITATION OF VIBRATIONAL, OCTUPOLE AND K=2+ QUADRUPOL9040 1451 71 BAND LEVELS,MT=55,56,57,58,59,61,62,63,64,65,66,67,68,72,75, 9040 1451 72 78,79, ARE OBTAINED IN A SOFT ROTATOR MODEL COUPLED 9040 1451 73 CHANNEL CALCULATIONS, FOR NORMALIZATION PURPOSES THESE DIRECT9040 1451 74 INELASTIC CROSS SECTIONS WERE SUBTRACTED FROM MT=2 ELASTIC 9040 1451 75 SCATTERING CROSS SECTION. DIRECT INELASTIC CONTRIBUTIONS 9040 1451 76 WERE ADDED INCOHERENTLY TO HAUSER-FESHBACH CALCULATIONS 9040 1451 77 OF COMPOUND NUCLEUS INELASTIC SCATTERING CROSS SECTIONS. 9040 1451 78 9040 1451 79 THE DEFORMED OPTICAL POTENTIAL USED: ENERGY DEPENDENCE 9040 1451 80 OF VR AND WD VARIED TO FIT MEASURED TOTAL DATA /13-19/, 9040 1451 81 ELASTIC SCATTERING DATA /20-22/ AND EVALUATED VALUE OF 9040 1451 82 S0=(.94+-.02)x10-4(EV)-1/2 9040 1451 83 9040 1451 84 VR=(45.722-0.334xE) MEV; RR =1.2668 FM; AR =.6468 FM; 9040 1451 85 WD=(3.145+0.455xE)MEV; E< 8 MEV RD =1.25 FM; 9040 1451 86 WD= 6.785 MEV; E>= 8 MEV AD =.5246 FM; 9040 1451 87 VSO= 6.2 MEV; RS0=1.12 FM; ASO=.47 FM; 9040 1451 88 B2= .188; B4=.071; 9040 1451 89 9040 1451 90 9040 1451 91 FISSION, CAPTURE AND COMPOUND INELASTIC SCATTERING CROSS 9040 1451 92 SECTIONS WERE CALCULATED WITH HAUSER-FESHBACH-MOLDAUER/23/ 9040 1451 93 APPROACH, AT INCIDENT NEUTRON ENERGIES HIGHER THAN 1.21 MEV 9040 1451 94 (LEVEL OVERLAPPING ENERGY) TEPEL ET AL./24/ THEORY WAS 9040 1451 95 EMPLOYED. 9040 1451 96 MEASURED DATA ON DISCRETE LEVEL EXCITATION CROSS SECTIONS 9040 1451 97 /25-31/, GROUPS OF LEVELS OF VIBRATIONAL, OCTUPOLE AND K=2+ 9040 1451 98 BAND LEVELS /27/ AS WELL AS TOTAL INELASTIC CROSS SECTION 9040 1451 99 /29-31/ WERE TAKEN INTO ACCOUNT. 9040 1451 100 9040 1451 101 ADOPTED LEVEL SCHEME OF Th-232 FROM NUCLEAR DATA SHEETS /32/.9040 1451 102 9040 1451 103 9040 1451 104 LEVEL SCHEME: 9040 1451 105 -------------------------------------------------------- 9040 1451 106 NO. ENERGY(MEV) SPIN-PARITY K-PARITY 9040 1451 107 -------------------------------------------------------- 9040 1451 108 9040 1451 109 G.S. 0.0 0 + 0+ 9040 1451 110 0.4936900-01 2 + 0+ 9040 1451 111 0.1621200+00 4 + 0+ 9040 1451 112 0.3332000+00 6 + 0+ 9040 1451 113 0.5569000+00 8 + 0+ 9040 1451 114 0.7142500+00 1 - 0- 9040 1451 115 0.7303500+00 0 + 0+ 9040 1451 116 0.7741000+00 2 + 0+ 9040 1451 117 0.7744000+00 3 - 0- 9040 1451 118 0.7853000+00 2 + 2+ 9040 1451 119 0.8270000+00 10 + 0+ 9040 1451 120 0.8296000+00 3 + 2+ 9040 1451 121 0.8730000+00 4 + 2+ 9040 1451 122 0.8836000+00 5 - 0- 9040 1451 123 0.8901000+00 4 + 0+ 9040 1451 124 0.9604000+00 5 + 2+ 9040 1451 125 0.1023100+01 6 + 2+ 9040 1451 126 0.1042900+01 7 - 0- 9040 1451 127 0.1049900+01 6 + 0+ 9040 1451 128 0.1053600+01 2 + 9040 1451 129 0.1072900+01 2 + 9040 1451 130 0.1077500+01 1 - 9040 1451 131 0.1078700+01 0 + 0+ 9040 1451 132 0.1094400+01 3 + 9040 1451 133 0.1105700+01 3 - 9040 1451 134 0.1121800+01 2 + 0+ 9040 1451 135 0.1137100+01 12 + 9040 1451 136 0.1143300+01 4 - 9040 1451 137 0.1146000+01 7 + 9040 1451 138 0.1148300+01 4 + 0+ 9040 1451 139 0.1182500+01 3 - 9040 1451 140 0.1208900+01 5 - 9040 1451 141 9040 1451 142 OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.21 MEV 9040 1451 143 9040 1451 144 9040 1451 145 MT=16,17,37. (N,2N), (N,3N) AND (N,4N) CROSS SECTION FROM 9040 1451 146 STATISTICAL MODEL CALCULATIONS /1/ WITH THE ACCOUNT OF 9040 1451 147 PRE-EQUILIBRIUM NEUTRON EMISSION (MODIFIED STAPRE CODE/33/ 9040 1451 148 WAS USED). MEASURED (N,2N) DATA /34-46/ WERE CONSISTENTLY 9040 1451 149 REPRODUCED, WHILE CALCULATED FISSION CROSS SECTION, WHICH 9040 1451 150 DESCRIBES MEASURED DATA BASE, WAS USED AS MAJOR CONSTRAINT. 9040 1451 151 9040 1451 152 MT=18, 19, 20, 21. FISSION CROSS SECTION IS CALCULATED WITHIN 9040 1451 153 STATISTICAL MODEL /1/. FOR FISSION DATA ANALYSIS MEASURED 9040 1451 154 DATA /47-51/ WERE USED. 9040 1451 155 THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 9040 1451 156 CROSS SECTION IS FIXED ACCORDING TO CONSISTENT DESCRIPTION 9040 1451 157 OF(N,F) AND (N,XN) REACTION DATA 9040 1451 158 MT=102 CAPTURE 9040 1451 159 CAPTURE CROSS SECTION DATA /52-55/ ARE DESCRIBED WITHIN A 9040 1451 160 STATISTICAL MODEL. ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS 9040 1451 161 ASSUMED TO BE CONSTANT. COMPETITION OF (N,GF) AND (N,GN') 9040 1451 162 REACTIONS IS TAKEN INTO ACCOUNT. 9040 1451 163 RADIATIVE STRENGTH FUNCTION SGO = 0.XXX WAS ADJUSTED 9040 1451 164 TO FIT CAPTURE CROSS SECTION DATA ABOVE 4 KEV. CAPTURE CROSS 9040 1451 165 SECTION DATA AT HIGHER ENERGIES WERE DESCRIBED VARYING 9040 1451 166 LEVEL DENSITY OF 233-Th COMPOUND NUCLIDE. 9040 1451 167 9040 1451 168 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9040 1451 169 FOR MT=2,51,52,53 AND 54 FROM COUPLED CHANNEL CALCULATIONS 9040 1451 170 (RIGID ROTATOR MODEL), 9040 1451 171 FOR MT=55,56,57,58,59,61,62,63,64,65,66,67,68,72,75, 9040 1451 172 78,79, FROM COUPLED CHANNEL MODEL (SOFT ROTATOR MODEL) 9040 1451 173 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9040 1451 174 9040 1451 175 MT=16, 17, 18-21, 37,38, 60, 69-71,73,76,77,80,81 AND 91 ARE 9040 1451 176 ISOTROPIC IN THE LAB SYSTEM. 9040 1451 177 9040 1451 178 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9040 1451 179 9040 1451 180 ENERGY DISTRIBUTIONS FOR MT=16,17,38,91 WERE CALCULATED BY 9040 1451 181 STATISTICAL MODEL OF CASCADE NEUTRON EMISSION TAKING INTO 9040 1451 182 ACCOUNT THE HISTORY OF THE DECAY WITH THE ALLOWANCE OF PRE- 9040 1451 183 EQUILIBRIUM EMISSION OF THE FIRST NEUTRON. MEASURED NEUTRON 9040 1451 184 EMISSION SPECTRA DATA BY BABA ET AL./56,57/ ARE REPRODUCED. 9040 1451 185 9040 1451 186 MT=18,19,20,21,37 9040 1451 187 PROMPT FISSION NEUTRON SPECTRA (PFNS)WERE CALCULATED WITH THE9040 1451 188 SEMI-EMPIRICAL MODEL/1/, PRE-FISSION NEUTRON EMISSION IN 9040 1451 189 (N,XNF) REACTION, EITHER EQUILIBRIUM AND PRE-EQUILIBRIUM 9040 1451 190 MODES ARE INCLUDED. BASICALLY PFNS FROM FISSION 9040 1451 191 FRAGMENTS (FF) WERE CALCULATED AS A SUPERPOSITION OF TWO 9040 1451 192 WATT DISTRIBUTIONS FOR LIGHT AND HEAVY FF WITH EQUAL 9040 1451 193 CONTRIBUTIONS, BUT DIFFERENT TEMPERATURE PARAMETERS. 9040 1451 194 FF KINETIC ENERGY, ONE MORE MODEL PARAMETER, MIGHT BE LOWER 9040 1451 195 THAN TKE, WHICH REFLECTS IT'S DEPENDENS ON THE MOMENT OF 9040 1451 196 NEUTRON EMISSION. THIS EFFECTIVELY REDUCES AVERAGE 9040 1451 197 ENERGY OF PFNS FOR INCIDENT NEUTRON ENERGIES ABOVE EMISSIVE 9040 1451 198 FISSION THRESHOLD. DATA ON PFNS OF /58-62/ ARE FITTED. 9040 1451 199 REFERENCES 9040 1451 200 1) Maslov V., Porodzinskij Yu., Baba M.,Hasegawa A., Kornilov 9040 1451 201 N.V., Kagalenko A.B. JAERI-Research 01-0XX, 2001. 9040 1451 202 2) M.C.Brady and T.R.England Nucl.Sci. Eng. 103,129(1989). 9040 1451 203 3) Glendenin L.E., Gindler J.E ., Ahmad I. et. al., Phys. Rev. C9040 1451 204 152 (1980). 9040 1451 205 4) Conde H., Holmberg M., AF, 29, 4, 33 (1965). 9040 1451 206 5) Frehaut J., Bois R., Bertin A., Int. Conf. on Nuclear Data 9040 1451 207 for Science and Technology, Antwerp., Belgium, 6-10 Sep. 9040 1451 208 1982, 78(1982). 9040 1451 209 6) Prokhorova L.I., Smirenkin G.N., Yad. Fizika, 7, 961 (1968). 9040 1451 210 7) Malinovskij V.V.,Vorob'jova V.G., Kuz'minov B.D. et al., 9040 1451 211 Atomnaya Energ.,54, (3), 209 (1983). 9040 1451 212 8) Caruana J., Boldeman J.W.,Walsh R.L., Nuclear Physics A, 285,9040 1451 213 217 (1977). 9040 1451 214 9) Howe R.E., Nucl. Sci. Eng., 86, 157 (1984). 9040 1451 215 10) Olsen K.D. ORNL/TM-8056 (1982), ENDF-319. 9040 1451 216 11) Cullen D. PREPRO2000: 2000 ENDF/B Pre-Processing Codes. 9040 1451 217 12) NJOY 94.10 Code System for Producing Pointwise and Multigroup9040 1451 218 Neutron and Photon Cross Sections from ENDF/B Data, RSIC 9040 1451 219 Peripheral Shielding Routine Collection, ORNL, PSR-355, LANL,9040 1451 220 Los Alamos, New Mexico (1995). 9040 1451 221 13) Hibdon C.T., Langsdorf A. jr.,ANL-5175, 7 (1954). 9040 1451 222 14) Kobayashi K., Fujita Y., Oosaki T. et al., Nucl. Sci. Eng., 9040 1451 223 65, (2), 347 (1978). 9040 1451 224 15) Vertebnyj V.P., Kirilyuk A.L.,Gnidak N.L. et al., 3rd All-Uni9040 1451 225 Conf. on Neutron Physics, 9-13 Jun, Kiev, 3, 151 (1975). 9040 1451 226 16) Vertebnyj V.P., Murzin A.V.,. Pshenichnyj V.A. et al., IAEA-49040 1451 227 257 (1987). 9040 1451 228 17) Poenitz W.P., Whalen J.F., Smith A.B., Nucl. Sci. Eng., 9040 1451 229 78, 333 (1981). 9040 1451 230 18) Poenitz W.P., Whalen J.F., ANL-NDM-80 (1983). 9040 1451 231 19) Uttley C.A., Newstead C.M., Diment K.M., 66PARIS, 1, 165 9040 1451 232 (1966). 9040 1451 233 20) Haouat G., Lachkar J., Lagrange Ch. et al., Nucl. Sci. and 9040 1451 234 Eng. 81, 491 (1982). 9040 1451 235 21) Haouat et al., NEANDC(E)-196 (1978). 9040 1451 236 22) Miura T., Baba M., Ibaraki M. et al. Proc. of the 1998 Symp. 9040 1451 237 Nuclear Data, November 19-20, 1998, JAERI, Tokai, Japan, 9040 1451 238 JAERI-Conf., 99-002, p. 101. 9040 1451 239 23) Moldauer P.A., Phys. Rev., C11, 426 (1975). 9040 1451 240 24) Tepel J.W., Hoffman H.M., Weidenmuller H.A. Phys. Lett. 49, 9040 1451 241 1 (1974). 9040 1451 242 25) Ciarcia C.A., Couchell G.P., Egan J.J. et al., Nucl. Sci. and9040 1451 243 Eng. 91, 428 (1985). 9040 1451 244 26) Dave J.H., Egan J.J., Couchell G.P. et al., Nucl. Sci. and 9040 1451 245 Eng. 91, 187 (1985). 9040 1451 246 27) Sheldon E., Alliyar A., Beghian L.E., et al., Proc. Int. Conf9040 1451 247 Nucl. Data for Sci. and Technol., Julich, 1991,p.989. 9040 1451 248 28) Goswani G.C., Egan J.J., Kegel G.H.R. et al., Nucl. Sci. and 9040 1451 249 Eng. 100,48 (1988). 9040 1451 250 29) Glazkov N.P., Atomnaya Energ. 14, (4), 400, (1963). 9040 1451 251 30) Smith W., Phys. Rev, 126, 718 (1962). 9040 1451 252 31) Fujita Y., Ohsawa T., Bugger R.M. et al.,J. of Nucl. Sci. and9040 1451 253 Tech., 20, 983 (1983). 9040 1451 254 32) Shurshikov E.N., Nucl. Data Sheets, 53, 601 (1988). 9040 1451 255 33) Uhl M., Strohmaier B., IRK-76/01, IRK, Vienna (1976). 9040 1451 256 34) Tewes H.A., Caretto A.A., Miller A.E., Nethaway D.R., 9040 1451 257 UCRL-6028-T,1960. 9040 1451 258 35) Butler J.P., Santry D.C. Canadian Journal of Chemistry, 39, 9040 1451 259 89(1961). 9040 1451 260 36) Cochran D.R.F., Henkel R.L. Preprint WASH-1013, 34 (1958). 9040 1451 261 37) Raics P., Daroczy S., Csikai J., Kornilov N.V. et al.,Phys. 9040 1451 262 Rev.C 32,87, (1985); Report INDC(HUN)-029/L, IAEA, 1990. 9040 1451 263 38) Prestwood R.J., Bayhurst B.P. Phys. Rev., 121, 1438 (1961). 9040 1451 264 39) Smith, B. Am.Phy.Soc.2, 196 (1957). 9040 1451 265 40) Karius H., Ackermann A., Scobel W. Journ. Physics part G , 5,9040 1451 266 715 (1979). 9040 1451 267 41) Perkin J.L., Coleman R.F. Journal of Nuclear Energy, 14, 9040 1451 268 69 (1961). 9040 1451 269 42) Phillips J.A. Report of AERE-NP/R-2033, 1956. 9040 1451 270 43) Chatani H., Kimura I. Annals of Nuclear Energy, 19,477 (1992)9040 1451 271 44) Zysin Yu.A., et al., Journal of Atomic Energy, 8, 360, (1960)9040 1451 272 45) Filatenkov A.A. et al.,INDC(CCP)-402, (1997); RI- 252, (1999)9040 1451 273 46) Batchelor R.,Gilboy W.B.,Towle J.H. Nuclear Physics, 65, 236 9040 1451 274 (1965). 9040 1451 275 47) Behrens J.W., Browne J.C., Ables E., Nucl. Sci. Eng., 81, 5129040 1451 276 (1982). 9040 1451 277 48) Meadows J.W., Int.Conf. on Nuclear Cross Sections for 9040 1451 278 Technology,Knoxville, Tennessee, 22-26 Oct 1979, 479 (1979). 9040 1451 279 49) Goverdovskij A.A. et al., Atomnaya Energ.60, (6), 416 (1986).9040 1451 280 50) Goverdovskij A.A. et. al., Atomnaya Energ.61, 380 (1986). 9040 1451 281 51) Fursov B.I., Baranov E.Yu., Klemyshev M.P. et.al., Atomnaya 9040 1451 282 Energ. 71,(4), 320 (1991). 9040 1451 283 52) Kobayashi K., Fujita Y., Yamamuro N. Nucl. Sci. Techn., 9040 1451 284 18, 823 (1981). 9040 1451 285 53) Wissak K., Voss F., Kaeppeler F.Nucl. Sci. Eng.,137, 183(20009040 1451 286 54) Grigor'ev Yu.V., Kitaev V.Ya. et al. ISINN-8, 68 Dubna, 9040 1451 287 2000. 9040 1451 288 55) Lindner M., Nagle R.J., Landrum J.H. Nucl. Sci. and Eng., 59,9040 1451 289 381 (1976). 9040 1451 290 56) Baba M.,Wakabayashi H.,Ito N. et al.,INDC(NDS)-220,1989,R, 9040 1451 291 INDC(JAP)-129/L,(1989). 9040 1451 292 57) Miura T., Baba M., Ibaraki M. et al. Ann. Nucl.Energy, 28, 9040 1451 293 937 (2001). 9040 1451 294 58) Sukhikh S.E., Lovchikova G.N.,Vinogradov V.A. et al., 9040 1451 295 Yadernye Konstanty,(3),34 (1986). 9040 1451 296 59) Boykov G.S.,Dmitriev V.D.,Kudyaev G.A. et al., 9040 1451 297 Yadernaya Fizika,53,(3),628 (1993). 9040 1451 298 60) Miura T.,T. Win, Baba M. et al., Proc. of the 1999 Symp. on 9040 1451 299 Nuclear Data, November 18-19, 1999, JAERI, Tokai, Japan, 9040 1451 300 JAERI-Conf., 2000-005, 137 (1999). 9040 1451 301 61) Lovchikova G.N. et al., Proc. of Meeting on PFNS properties, 9040 1451 302 Mito, Japan,. 9040 1451 303 62) Lovchikova G.N., Trufanov A.M.,Svirin M.I. et al., Proc. Int.9040 1451 304 Workshop on Nuclear Fission Physics, Obninsk, 2000,72 (2000)9040 1451 305 9040 1451 306 9040 1451 307 1 451 406 09040 1451 308 1 452 10 09040 1451 309 1 455 7 09040 1451 310 1 456 10 09040 1451 311 2 151 746 09040 1451 312 3 1 124 09040 1451 313 3 2 121 09040 1451 314 3 4 31 09040 1451 315 3 16 9 09040 1451 316 3 17 7 09040 1451 317 3 18 29 09040 1451 318 3 19 29 09040 1451 319 3 20 10 09040 1451 320 3 21 7 09040 1451 321 3 37 4 09040 1451 322 3 38 5 09040 1451 323 3 51 31 09040 1451 324 3 52 27 09040 1451 325 3 53 26 09040 1451 326 3 54 25 09040 1451 327 3 55 24 09040 1451 328 3 56 23 09040 1451 329 3 57 23 09040 1451 330 3 58 23 09040 1451 331 3 59 22 09040 1451 332 3 60 15 09040 1451 333 3 61 21 09040 1451 334 3 62 21 09040 1451 335 3 63 21 09040 1451 336 3 64 20 09040 1451 337 3 65 20 09040 1451 338 3 66 19 09040 1451 339 3 67 19 09040 1451 340 3 68 18 09040 1451 341 3 69 12 09040 1451 342 3 70 12 09040 1451 343 3 71 12 09040 1451 344 3 72 17 09040 1451 345 3 73 11 09040 1451 346 3 74 11 09040 1451 347 3 75 16 09040 1451 348 3 76 8 09040 1451 349 3 77 10 09040 1451 350 3 78 15 09040 1451 351 3 79 15 09040 1451 352 3 80 9 09040 1451 353 3 81 8 09040 1451 354 3 91 13 09040 1451 355 3 102 115 09040 1451 356 4 2 108 09040 1451 357 4 16 2 09040 1451 358 4 17 2 09040 1451 359 4 18 2 09040 1451 360 4 19 2 09040 1451 361 4 20 2 09040 1451 362 4 21 2 09040 1451 363 4 37 2 09040 1451 364 4 38 2 09040 1451 365 4 51 108 09040 1451 366 4 52 100 09040 1451 367 4 53 97 09040 1451 368 4 54 94 09040 1451 369 4 55 91 09040 1451 370 4 56 91 09040 1451 371 4 57 91 09040 1451 372 4 58 91 09040 1451 373 4 59 91 09040 1451 374 4 60 2 09040 1451 375 4 61 88 09040 1451 376 4 62 88 09040 1451 377 4 63 88 09040 1451 378 4 64 89 09040 1451 379 4 65 88 09040 1451 380 4 66 85 09040 1451 381 4 67 85 09040 1451 382 4 68 86 09040 1451 383 4 69 2 09040 1451 384 4 70 2 09040 1451 385 4 71 2 09040 1451 386 4 72 86 09040 1451 387 4 73 2 09040 1451 388 4 74 2 09040 1451 389 4 75 86 09040 1451 390 4 76 2 09040 1451 391 4 77 2 09040 1451 392 4 78 85 09040 1451 393 4 79 86 09040 1451 394 4 80 2 09040 1451 395 4 81 2 09040 1451 396 4 91 2 09040 1451 397 5 16 171 09040 1451 398 5 17 81 09040 1451 399 5 18 2559 09040 1451 400 5 19 2559 09040 1451 401 5 20 1896 09040 1451 402 5 21 1230 09040 1451 403 5 37 18 09040 1451 404 5 38 564 09040 1451 405 5 91 345 09040 1451 406 9040 1 0 407