9131 0 0 0 9.123100+4 2.290500+2 1 1 0 29131 1451 1 0.000000+0 1.000000+0 0 0 0 69131 1451 2 1.000000+0 2.000000+7 0 0 10 69131 1451 3 0.000000+0 0.000000+0 0 0 219 779131 1451 4 91-Pa-231 EVAL-September 2003 9131 1451 5 DIST-October 2003 9131 1451 6 ----ENDF/B-VI MATERIAL 9131 9131 1451 7 -----INCIDENT NEUTRON DATA 9131 1451 8 ------ENDF-6 FORMAT 9131 1451 9 ----B-404-ISTC MATERIAL 9131 9131 1451 10 -----INCIDENT NEUTRON DATA 9131 1451 11 -----ENDF/B-VI FORMAT 9131 1451 12 *****************************************************************9131 1451 13 UNRESOLVED RESONANCE PARAMETERS FOR 115 EV-78 KEV REGION, 9131 1451 14 TOTAL, ELASTIC SCATTERING, INELASTIC SCATTERING, FISSION, 9131 1451 15 CAPTURE,(N,2N) AND (N,3N) CROSS SECTIONS AS WELL AS 9131 1451 16 ANGULAR AND ENERGY DISTRIBUTIONS OF SECONDARY AND PROMPT 9131 1451 17 FISSION NEUTRONS WERE EVALUATED BY 9131 1451 18 V.M. MASLOV,N.A. TETEREVA, 9131 1451 19 M. BABA, A. HASEGAWA, 9131 1451 20 N.V. KORNILOV, A.B. KAGALENKO /1/. 9131 1451 21 9131 1451 22 9131 1451 23 MF=1 GENERAL INFORMATION 9131 1451 24 MT=451 DESCRIPTIVE DATA AND DICTIONARY 9131 1451 25 MT=452 NUMBER OF NEUTRONS 9131 1451 26 SUM OF MT=455 and 456. 9131 1451 27 MT=455 DELAYED NEUTRONS PER FISSION ARE ADOPTED FROM JENL-3.3, 9131 1451 28 WHICH ARE BASED ON TUTTLE' RECOMENDATIONS /2/. 9131 1451 29 MT=456 PROMPT NEUTRONS NUMBER 9131 1451 30 ESTIMATED WITH SYSTEMATICS /3/. FOR INCIDENT NEUTRON 9131 1451 31 ENERGIES HIGHER THAN (N,NF) REACTION THRESHOLD, NU-BAR 9131 1451 32 WAS CALCULATED TAKING INTO ACCOUNT PARTIAL CONTRIBUTIONS 9131 1451 33 OF (N,XNF) REACTIONS /1/. 9131 1451 34 9131 1451 35 MF=2 RESONANCE PARAMETERS 9131 1451 36 MT=151 RESOLVED RESONANCE PARAMETERS WERE ADOPTED FROM 9131 1451 37 JENDL-3.3 /5/. IN JENDL-3.3 RESOLVED RESONANCES FOR SLBW 9131 1451 38 FORMULA: 1.0-5 - 115 EV. 9131 1451 39 NEUTRON AND RADIATIVE WIDTHS WERE MAINLY ADOPTED FROM 9131 1451 40 HUSSEIN ET AL./6/, AND FISSION WIDTH ESTIMATED FROM THE 9131 1451 41 DATA OF FISSION AREA MEASURED BY PLATTARD ET AL. /7/. 9131 1451 42 FOR THE RESONANCES WHOSE FISSION AREA WAS NOT MEASURED, 9131 1451 43 AN AVERAGE VALUE OF 40 MICRO-EV WAS ASSUMED. A NEGATIVE 9131 1451 44 RESONANCE WAS GIVEN ON THE BASIS OF RECOMMENDATION BY 9131 1451 45 MUGHABGHAB /8/ TO REPRODUCE RECOMMENDED THERMAL CROSS 9131 1451 46 SECTIONS. 9131 1451 47 9131 1451 48 ENERGY-DEPENDENT UNRESOLVED RESONANCE PARAMETERS COVER 9131 1451 49 ENERGY RANGE FROM 115 EV TO 78 KEV. PARAMETERS WERE 9131 1451 50 9131 1451 51 2200-M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS. 9131 1451 52 2200 M/S(B) RES. INTEG.(B) 9131 1451 53 TOTAL 210.69 - 9131 1451 54 ELASTIC 9.95 - 9131 1451 55 FISSION 0.0197 4.55 9131 1451 56 CAPTURE 200.72 587.38 9131 1451 57 9131 1451 58 MF=3 NEUTRON CROSS SECTIONS 9131 1451 59 FROM 115 EV UP TO 78 KEV EVALUATED CROSS SECTIONS WERE 9131 1451 60 REPRESENTED WITH THE UNRESOLVED RESONANCE PARAMETERS. 9131 1451 61 ENERGY-DEPENDENT UNRESOLVED RESONANCE PARAMETERS WERE 9131 1451 62 OBTAINED TO REPRODUCE FISSION CROSS SECTION, CALCULATED 9131 1451 63 WITH STATISTICAL MODEL, FITTED TO DATA BY 9131 1451 64 KOBAYASHI ET AL./9/. 9131 1451 65 9131 1451 66 MT= 1, 2, 4, 51-86, 91 - TOTAL, ELASTIC AND INELASTIC 9131 1451 67 SCATTERING CROSS SECTIONS. 9131 1451 68 TOTAL, ELASTIC AND DIRECT INELASTIC FOR ROTATIONAL 9131 1451 69 GROUND STATE BAND LEVELS MT=51,52,53(COUPLED LEVELS) 9131 1451 70 AS WELL AS OPTICAL TRANSMISSION COEFFICIENTS ARE OBTAINED9131 1451 71 IN A RIGID ROTATOR MODEL COUPLED CHANNELS CALCULATIONS. 9131 1451 72 DIRECT INELASTIC CONTRIBUTIONS WERE ADDED INCOHERENTLY 9131 1451 73 TO HAUSER-FESHBACH CALCULATIONS OF COMPOUND NUCLEUS 9131 1451 74 INELASTIC SCATTERING CROSS SECTIONS. 9131 1451 75 9131 1451 76 THE DEFORMED OPTICAL POTENTIAL ADOPTED WAS THAT FOR 9131 1451 77 232Th, /10/ THEN EVALUATED VALUE OF S-WAVE STRENGTH 9131 1451 78 FUNCTION S0= 0.78x10-4(EV)-1/2 WAS FITTED: 9131 1451 79 9131 1451 80 VR=(45.722-0.334xE) MEV; RR =1.2668 FM; AR =.6468 FM; 9131 1451 81 WD=(3.145+0.455xE) MEV; E< 8 MEV RD =1.25 FM; 9131 1451 82 WD= 6.785 MEV; E>= 8 MEV AD =.5246 FM; 9131 1451 83 VSO= 6.2 MEV; RS0=1.12 FM; ASO=.47 FM; 9131 1451 84 B2= .165; B4=.072; 9131 1451 85 9131 1451 86 9131 1451 87 FISSION, CAPTURE AND COMPOUND INELASTIC SCATTERING CROSS 9131 1451 88 SECTIONS WERE CALCULATED WITH HAUSER-FESHBACH-MOLDAUER/11/ 9131 1451 89 APPROACH, AT INCIDENT NEUTRON ENERGIES HIGHER THAN 0.354 MEV 9131 1451 90 LEVEL OVERLAPPING ENERGY) TEPEL ET AL./12/ THEORY WAS 9131 1451 91 EMPLOYED. 9131 1451 92 9131 1451 93 THE LEVEL SCHEME WAS TAKEN FROM NUCLEAR DATA SHEETS/13/. 9131 1451 94 NO. ENERGY(MEV) SPIN-PARITY 9131 1451 95 GS 0.0 3/2- 9131 1451 96 1 0.00921 1/2- 9131 1451 97 2 0.05857 7/2- 9131 1451 98 3 0.077685 5/2- 9131 1451 99 4 0.084216 5/2+ 9131 1451 100 5 0.101408 7/2+ 9131 1451 101 6 0.102268 3/2+ 9131 1451 102 7 0.111653 9/2+ 9131 1451 103 8 0.1340 11/2+ 9131 1451 104 9 0.169 11/2- 9131 1451 105 10 0.17416 5/2- 9131 1451 106 11 0.183495 5/2+ 9131 1451 107 12 0.189 13/2+ 9131 1451 108 13 0.1932 9/2- 9131 1451 109 14 0.21824 7/2- 9131 1451 110 15 0.24732 7/2+ 9131 1451 111 16 0.2720 9/2- 9131 1451 112 17 0.287 1/2+ 9131 1451 113 18 0.304 9/2+ 9131 1451 114 19 0.3179 3/2+ 9131 1451 115 20 0.320209 3/2- 9131 1451 116 21 0.3291 15/2- 9131 1451 117 22 0.340 11/2- 9131 1451 118 23 0.35184 5/2- 9131 1451 119 24 0.353 13/2- 9131 1451 120 9131 1451 121 CONTINUUM LEVELS WERE ASSUMED ABOVE 0.354 MEV. 9131 1451 122 9131 1451 123 MT=16,17,37. (N,2N) AND (N,3N) CROSS SECTION FROM 9131 1451 124 STATISTICAL MODEL CALCULATIONS /1/ WITH ACCOUNT OF 9131 1451 125 PRE-EQUILIBRIUM NEUTRON EMISSION (MODIFIED STAPRE CODE/14/ 9131 1451 126 WAS USED). PRE-EQUILIBRIUM NEUTRON EMISSION CONTRIBUTION WAS 9131 1451 127 FIXED ACCORDING TO CONSISTENT DESCRIPTION OF(N,F) AND (N,XN) 9131 1451 128 REACTION DATA FOR 238U AND 232Th TARGET NUCLIDES. 9131 1451 129 9131 1451 130 MT=18, 19, 20, 21,38. FISSION CROSS SECTION IS CALCULATED 9131 1451 131 WITHIN STATISTICAL MODEL /10,15/. 9131 1451 132 MEASURED FISSION DATA /16-23/ ANALYSIS WAS ACCOMPLISHED. 9131 1451 133 THE CONTRIBUTION OF EMISSIVE (N,NF) AND (N,2NF) FISSION TO 9131 1451 134 THE TOTAL FISSION CROSS SECTION WAS ESTIMATED USING FISSION 9131 1451 135 BARRIER PARAMETERS OF 231-PA AND 230-PA, WHICH DESCRIBE 9131 1451 136 INDIRECT 230-PA(N,F) AND 229-PA(N,F)CROSS SECTION DATA BY 9131 1451 137 BRITT AND WILHEMY /24/. 9131 1451 138 MT=102 CAPTURE 9131 1451 139 CAPTURE CROSS SECTION IS CALCULATED WITHIN A STATISTICAL MO- 9131 1451 140 DEL. ABOVE NEUTRON ENERGY 5.5 MEV CAPTURE IS ASSUMED TO BE 9131 1451 141 CONSTANT. COMPETITION OF (N,GF) AND (N,GN') REACTIONS IS 9131 1451 142 TAKEN INTO ACCOUNT. 9131 1451 143 9131 1451 144 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9131 1451 145 FOR MT=2,53,64 FROM COUPLED CHANNEL CALCULATIONS 9131 1451 146 (RIGID ROTATOR MODEL), WITH ADDED ISOTROPIC COMPOUND 9131 1451 147 CONTRIBUTION. 9131 1451 148 9131 1451 149 MT=16, 17, 18-21, 38, 51-52,54-63, 65-74 AND 91 ARE ISOTROPIC 9131 1451 150 IN THE LAB SYSTEM. 9131 1451 151 9131 1451 152 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9131 1451 153 9131 1451 154 ENERGY DISTRIBUTIONS FOR MT=16,17,91 WERE CALCULATED WITH 9131 1451 155 A HAUSER-FESHBACH STATISTICAL MODEL OF CASCADE NEUTRON 9131 1451 156 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY WITH 9131 1451 157 THE ALLOWANCE OF PREEQUILIBRIUM EMISSION OF THE FIRST 9131 1451 158 NEUTRON, SIMULTANEOUSLY WITH (N,F) AND (N,XNF) REACTION CROSS9131 1451 159 SECTIONS. 9131 1451 160 9131 1451 161 MT=18,19,20,21,38 9131 1451 162 PROMPT FISSION NEUTRON SPECTRA (PFNS)WERE CALCULATED WITH THE9131 1451 163 SEMI-EMPIRICAL MODEL/1,4,25/, PRE-FISSION NEUTRON EMISSION 9131 1451 164 IN(N,XNF) REACTION, EITHER EQUILIBRIUM AND PRE-EQUILIBRIUM 9131 1451 165 MODES ARE INCLUDED. SPECTRA OF PRE-FISSION (N,XNF) NEUTRONS 9131 1451 166 ARE CALCULATED WITH HAUSER-FESHBACH STATISTICAL MODEL. 9131 1451 167 BASICALLY PFNS FROM FISSION FRAGMENTS (FF) WERE CALCULATED AS9131 1451 168 A SUPERPOSITION OF TWO WATT DISTRIBUTIONS FOR LIGHT AND HEAVY9131 1451 169 FF WITH EQUAL CONTRIBUTIONS, BUT DIFFERENT TEMPERATURE 9131 1451 170 PARAMETERS. FF KINETIC ENERGY, ONE MORE MODEL PARAMETER, 9131 1451 171 MIGHT BE LOWER THAN TKE, WHICH REFLECTS IT'S DEPENDENS ON THE9131 1451 172 MOMENT OF NEUTRON EMISSION. THIS EFFECTIVELY REDUCES AVERAGE 9131 1451 173 ENERGY OF PFNS FOR INCIDENT NEUTRON ENERGIES ABOVE EMISSIVE 9131 1451 174 FISSION THRESHOLD. 9131 1451 175 9131 1451 176 REFERENCES 9131 1451 177 1) Maslov V.M., Baba M., Hasegawa A., Kornilov N.V, 9131 1451 178 Kagalenko A.B, Tetereva N.A. INDC(BLR)-19,IAEA, Vienna,2003 9131 1451 179 2) Tuttle R.J., INDC(NDS)-107/G (1979). 9131 1451 180 3) Malinovskij V.V., Yadernye constanty, V.2, 25 (1987. 9131 1451 181 4) Maslov V.M., Porodzinskij Yu.V., Baba M., Hasegawa A., 9131 1451 182 Kornilov N.V., Kagalenko A.B. European Phisical Journal A 9131 1451 183 (in print), 2003. 9131 1451 184 5) JENDL-3.3, Japan Evaluated Nuclear Data Library (2003). 9131 1451 185 6) Hussein A.-R.Z., Harvey J.A., Hill N.W., and J.R.Patterson. 9131 1451 186 Nucl. Sci.Eng., 78, 370 (1981). 9131 1451 187 7) Plattard S., Auchampaugh G.F., Hill H.W. et al. Phys. Rev. 9131 1451 188 Lett., 46, 633 (1981). 9131 1451 189 8) Mughabghab S.F. Neutron Cross Sections, V. 1, Part B, (1984).9131 1451 190 9) Kobayashi : Kobayashi K., Yamamoto S., Lee S. et all, Nucl. 9131 1451 191 Sci.Eng., 139, 273 (2001). 9131 1451 192 10) Maslov V.M.,Porodzinskij Yu.V.,Baba M.,Hasegawa A., 9131 1451 193 Kornilov N.V., Kagalenko A.B., Tetereva N.A. INDC(BLR)-16, 9131 1451 194 IAEA, Vienna (2003). 9131 1451 195 11) Moldauer P.A., Phys. Rev., C11, 426 (1975). 9131 1451 196 12) Tepel J.W., Hoffman H.M., Weidenmuller H.A. Phys. Lett. 49, 9131 1451 197 1 (1974). 9131 1451 198 13) Schmorak M.R. Nucl. Data Sheets 21, 91 (1977). 9131 1451 199 14) Uhl M., Strohmaier B., IRK-76/01, IRK, Vienna (1976). 9131 1451 200 15) Maslov V.M., Porodzinskij Yu.V., Baba M., Hasegawa A., 9131 1451 201 Kornilov N.V., Kagalenko A.B., Tetereva N.A. INDC(BLR)-14, 9131 1451 202 IAEA, Vienna (2003). 9131 1451 203 16) Wagemans C. , D'Hondt P., Deruytter A.J., Asghar M., 9131 1451 204 Emsallem A. J. Nucl. Physics A285, 32 (1977). 9131 1451 205 17) Iyer R.H., Sampathkumar R., Chaudhuri N.K. P, BARC-872, 106 9131 1451 206 (1976). 9131 1451 207 18) Dubrovina S.M., Shigin V.A. J., DOK, 157, (3), 561(1964). 9131 1451 208 19) Fursov B.I.,.Baranov E.JU, Klemyshev M.P. et al., Atomnaya 9131 1451 209 Energiya, 59 (4), 339 (1985). 9131 1451 210 20) Birgul O., Lyle S.J. J., Radiochimica Acta, 11, 108 (1969). 9131 1451 211 21) Muir D.W., Vesser L.R. Proc. conf. on Nucl. Cross Sections 9131 1451 212 and Technology, March 1971, Knoxville. Washington, v. 1,292, 9131 1451 213 (1975). 9131 1451 214 22) Leonard B.R., Odegaarden R.H. Bulletin of American Physical 9131 1451 215 Society, 6, 8 (A8) (1961). 9131 1451 216 23) Williams, J.H., Report LA-150 (1944). 9131 1451 217 24) Britt H.C. and Wilhelmy J.B., Nucl. Sci. Eng. 72, 222 (1979).9131 1451 218 25) Maslov V.M., Porodzinskij Yu.V., Baba M., Hasegawa A., 9131 1451 219 Kornilov N.V., Kagalenko A.B., Proc. of the 10th Internatio- 9131 1451 220 nal Seminar on Interaction of Neutrons with Nuclei, 9131 1451 221 May 22-25, 2002,Dubna, E3-2003-10, Russia, 222 (2003). 9131 1451 222 9131 1451 223 1 451 300 09131 1451 224 1 452 11 09131 1451 225 1 455 7 09131 1451 226 1 456 11 09131 1451 227 2 151 819 09131 1451 228 3 1 31 09131 1451 229 3 2 28 09131 1451 230 3 4 30 09131 1451 231 3 16 9 09131 1451 232 3 17 7 09131 1451 233 3 18 28 09131 1451 234 3 19 28 09131 1451 235 3 20 11 09131 1451 236 3 21 8 09131 1451 237 3 38 5 09131 1451 238 3 51 24 09131 1451 239 3 52 22 09131 1451 240 3 53 27 09131 1451 241 3 54 20 09131 1451 242 3 55 19 09131 1451 243 3 56 19 09131 1451 244 3 57 19 09131 1451 245 3 58 18 09131 1451 246 3 59 17 09131 1451 247 3 60 17 09131 1451 248 3 61 16 09131 1451 249 3 62 16 09131 1451 250 3 63 16 09131 1451 251 3 64 21 09131 1451 252 3 65 15 09131 1451 253 3 66 14 09131 1451 254 3 67 14 09131 1451 255 3 68 13 09131 1451 256 3 69 13 09131 1451 257 3 70 12 09131 1451 258 3 71 12 09131 1451 259 3 72 12 09131 1451 260 3 73 11 09131 1451 261 3 74 11 09131 1451 262 3 91 17 09131 1451 263 3 102 22 09131 1451 264 4 2 196 09131 1451 265 4 16 2 09131 1451 266 4 17 2 09131 1451 267 4 51 2 09131 1451 268 4 52 2 09131 1451 269 4 53 196 09131 1451 270 4 54 2 09131 1451 271 4 55 2 09131 1451 272 4 56 2 09131 1451 273 4 57 2 09131 1451 274 4 58 2 09131 1451 275 4 59 2 09131 1451 276 4 60 2 09131 1451 277 4 61 2 09131 1451 278 4 62 2 09131 1451 279 4 63 2 09131 1451 280 4 64 175 09131 1451 281 4 65 2 09131 1451 282 4 66 2 09131 1451 283 4 67 2 09131 1451 284 4 68 2 09131 1451 285 4 69 2 09131 1451 286 4 70 2 09131 1451 287 4 71 2 09131 1451 288 4 72 2 09131 1451 289 4 73 2 09131 1451 290 4 74 2 09131 1451 291 4 91 2 09131 1451 292 5 16 1126 09131 1451 293 5 17 610 09131 1451 294 5 18 2448 09131 1451 295 5 19 2448 09131 1451 296 5 20 2007 09131 1451 297 5 21 1119 09131 1451 298 5 38 453 09131 1451 299 5 91 1183 09131 1451 300