96 - Cm - 245 9645 0 0 0 9.62450+04 2.42960+02 1 1 0 19645 1451 1 0.00000+00 0.00000+00 0 0 0 69645 1451 2 1.00000+00 0.00000+00 0 0 10 69645 1451 3 0.00000+00 0.00000+00 0 0 174 629645 1451 4 96-Cm-245 MINSK BYEL EVAL-NOV 5 9645 1451 5 DIST-NOV95 9645 1451 6 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9645 1451 7 Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ, 9645 1451 8 G.B. MOROGOVSKIJ 9645 1451 9 STATUS 9645 1451 10 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9645 1451 11 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9645 1451 12 FINANCING PARTY OF THE CENTER FOR THE PROJECT IS JAPAN. 9645 1451 13 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI) 9645 1451 14 9645 1451 15 MF=1 GENERAL INFORMATION 9645 1451 16 9645 1451 17 MT=451 COMMENTS AND DICTIONARY 9645 1451 18 MT=452 NUMBER OF NEUTRONS PER FISSION 9645 1451 19 SUM OF MT=455 AND MT=456. 9645 1451 20 MT=455 DELAYED NEUTRON DATA 9645 1451 21 DECAY CONSTANTS FROM BRADY ET AL./1 /AND TUTTLE'S 9645 1451 22 SYSTEMATICS /2/. 9645 1451 23 MT=456 NUMBER OF NEUTRONS PER FISSION 9645 1451 24 BASED ON THE EXPERIMENTAL DATA OF KHOKHLOV ET AL. /3/ 9645 1451 25 AND MADLAND-NIX MODEL CALCULATIONS /4/, ABOVE 9645 1451 26 EMISSIVE FISSION THRESHOLD A SUPERPOSITION OF 9645 1451 27 NEUTRON EMISSION IN (N,XNF) REACTIONS /5/ AND PROMPT 9645 1451 28 FISSION NEUTRONS 9645 1451 29 MF=2 RESONANCE PARAMETERS 9645 1451 30 9645 1451 31 MT=151 RESONANCE PARAMETERS (SLBW) 9645 1451 32 RESOLVED RESONANCE REGION : 1.0E-5 - 100 EV 9645 1451 33 PARAMETERS FOR BREIT -WIGNER FORMULA ARE BASED ON 9645 1451 34 THE DATA OF MOORE ET AL. /6/ AND BROWNE ET AL./7/. 9645 1451 35 UNRESOLVED RESONANCE REGION : 0.1 - 54.9553 KEV. 9645 1451 36 ENERGY INDEPENDENT PARAMETERS: 9645 1451 37 R=9.52044 FM FROM OPTICAL MODEL CALCULATIONS 9645 1451 38 S1=2.10E-4 FROM OPTICAL MODEL CALCULATIONS 9645 1451 39 S2=1.256-4 EQUALS S0 WITH ACCOUNT OF MISSING 9645 1451 40 ENERGY DEPENDENT PARAMETERS: 9645 1451 41 S0 - DECREASES FROM 1.256-4 (0.1KEV)TO 1.172-4 (55KEV) 9645 1451 42 D - SPIN DEPENDENT, NORMALIZED TO =0.698 EV 9645 1451 43 WITH ACCOUNT OF LEVEL MISSING /8/ 9645 1451 44 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9645 1451 45 SPECTRA AT INNER AND OUTER BARRIER HUMPS,NORMALIZED 9645 1451 46 TO =0.345 EV TO FIT UNRESOLVED RESONANCE REGION9645 1451 47 EXPERIMENTAL FISSION DATA /6,9,10/. 9645 1451 48 WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION 9645 1451 49 COMPETITION,SPIN DEPENDENT. NORMALIZED TO = 9645 1451 50 0.0378 EV. 9645 1451 51 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9645 1451 52 INTEGRALS. 9645 1451 53 2200 M/SEC RES.INTEG. 9645 1451 54 TOTAL 2512.500 b - 9645 1451 55 ELASTIC 10.973 b - 9645 1451 56 FISSION 2142.382 b 793.927 9645 1451 57 CAPTURE 359.145 b 105.404 9645 1451 58 9645 1451 59 MF=3 NEUTRON CROSS SECTIONS 9645 1451 60 9645 1451 61 MT=1,4,51-67,91,102. TOTAL, ELASTIC AND INELASTIC 9645 1451 62 SCATTERING, CAPTURE CROSS SECTION 9645 1451 63 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51, 9645 1451 64 52,53,55,61 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9645 1451 65 COUPLED CHANNELS CALCULATIONS. 9645 1451 66 THE DEFORMED OPTICAL POTENTIAL USED: 9645 1451 67 VR=46.38-0.3*E(MEV) RR=1.26 FM AR=0.615 FM 9645 1451 68 WD= 3.71+0.4*E(MEV) E < 10 MEV RD=1.24 FM 9645 1451 69 WD= 7.77 E => 10 MEV AD=0.5 FM 9645 1451 70 VSO=6.4 RSO=1.12 ASO=0.47 B2=0.233 B4=0.076 9645 1451 71 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9645 1451 72 MODEL, SEE MT=18-21 9645 1451 73 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9645 1451 74 0.0001 BARN AS PREDICTED BY DIRECT AND SEMI-DIRECT 9645 1451 75 CAPTURE CALCULATIONS 9645 1451 76 ADOPTED LEVEL SCHEME OF CM-245 FROM NUCLEAR DATA 9645 1451 77 SHEETS /11/ (15 LEVELS) PLUS 2 LEVELS ADDED FOR BAND 9645 1451 78 K,P=7/2+ ACCORDING TO EJ=A(J(J+1)-K(K+1)) 9645 1451 79 No ENERGY(MEV) SPIN-PARITY K 9645 1451 80 g.s. 0.0 7/2 + 7/2 9645 1451 81 1 0.05473 9/2 + 7/2 9645 1451 82 2 0.1214 11/2 + 7/2 9645 1451 83 3 0.1971 13/2 + 7/2 9645 1451 84 4 0.25285 5/2 + 5/2 9645 1451 85 5 0.2923 15/2 + 7/2 * 9645 1451 86 6 0.29584 7/2 + 5/2 9645 1451 87 7 0.3505 9/2 + 5/2 9645 1451 88 8 0.35595 1/2 + 1/2 9645 1451 89 9 0.3615 3/2 + 1/2 9645 1451 90 10 0.38795 9/2 - 9/2 9645 1451 91 11 0.3957 17/2 + 7/2 * 9645 1451 92 12 0.417 11/2 + 5/2 9645 1451 93 13 0.4188 5/2 + 1/2 9645 1451 94 14 0.431 7/2 + 1/2 9645 1451 95 15 0.4428 11/2 - 9/2 9645 1451 96 16 0.4980 13/2 + 5/2 9645 1451 97 17 0.5087 13/2 - 9/2 9645 1451 98 * - ADDED 9645 1451 99 9645 1451 100 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.50874 MEV 9645 1451 101 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9645 1451 102 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9645 1451 103 FROM STATISTICAL MODEL CALCULATIONS /12/ WITH THE 9645 1451 104 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219645 1451 105 MT=18,19,20,21. FISSION CROSS SECTION 9645 1451 106 BASED ON DATA OF fOMUSHKIN ET AL./12/, WHITE ET AL./10/ 9645 1451 107 AND FURSOV ET AL./13/. 9645 1451 108 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9645 1451 109 THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS: 9645 1451 110 9645 1451 111 TRANSITION SPECTRA BAND HEADS OF 246-CM 9645 1451 112 9645 1451 113 INNER SADDLE OUTER SADDLE 9645 1451 114 K,P EKP K,P EKP 9645 1451 115 0 + 0.0 0 + 0.0 9645 1451 116 2 + 0.1 2 + 0.3 9645 1451 117 0 - 0.4 0 - 0.0 9645 1451 118 1 - 0.4 1 - 0.1 9645 1451 119 2 + 0.5 2 + 0.5 9645 1451 120 2 - 0.4 2 - 0.1 9645 1451 121 0 + 0.8 0 + 0.8 9645 1451 122 0 + 0.8 0 + 0.8 9645 1451 123 9645 1451 124 FISSION BARRIER PARAMETERS OF 246-CM 9645 1451 125 9645 1451 126 BARRIER BARRIER HEIGHT, MEV CURVATURE, MEV 9645 1451 127 INNER 6.00 0.9 9645 1451 128 OUTER 4.80 0.6 9645 1451 129 9645 1451 130 THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 9645 1451 131 CROSS SECTION IS CALCULATED ACCORDING TO /14,15/. 9645 1451 132 9645 1451 133 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9645 1451 134 9645 1451 135 FOR MT=2,51,53,57 FROM COUPLED CHANNELS CALCULATIONS 9645 1451 136 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9645 1451 137 MT=16,17,18,52,54-56,58-74,91,16 ISOTROPIC 9645 1451 138 9645 1451 139 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9645 1451 140 9645 1451 141 ENERGY DISTRIBUTIONS FOR MT=16,17,18,19,20,21 WERE 9645 1451 142 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9645 1451 143 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9645 1451 144 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9645 1451 145 THE FIRST NEUTRON /5/ 9645 1451 146 9645 1451 147 REFERENCES 9645 1451 148 9645 1451 149 1. Brady M.C.and England T.R., Nucl.Sci.Eng., 145,129 (1989). 9645 1451 150 2. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron 9645 1451 151 Properties, 1979, Vienna, INDC(NDS)-107/G, p.29. 9645 1451 152 3. Khokhlov Yu.A., Ivanin I.A., In'kov V.I., et al., Proc of 9645 1451 153 Int. Conf. on Nucl. Data for Sci. and Tech., 9-13 May, 9645 1451 154 Gatlinburg, v.1, p.272, 1994. 9645 1451 155 4. Madland D.G., Nix J.R., Nucl. Sci. Eng., 81, 213, (1982). 9645 1451 156 5. Maslov V.M., Porodzinskij Yu.V.,Sukhovitskij E.Sh., Proc. 9645 1451 157 Int. Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR, 9645 1451 158 v.1, p.413, 1988. 9645 1451 159 6. M.S. Moore, G.A. Keyworth: Phys. Rev. C, v3 (1971) 1656. 9645 1451 160 7. J.C. Browne, R.W. Benjamin, D.G. Karraker: Nucl. Sci. Eng., 9645 1451 161 65(1978) 166. 9645 1451 162 8. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants, 4, 9645 1451 163 p.27, 1987 (in Russian) 9645 1451 164 9. Gerasimov V.F., Danitchev V.V., Dementiev V.N., Proc of Int. 9645 1451 165 Conf.on Neutron Physics., 14-18 Sept., Kiev, USSR, v.3, 9645 1451 166 p.84, 1987 9645 1451 167 10. WhitE R.M., BROWNE J.C., Proc of Int. Conf. on Nucl. Data for 9645 1451 168 Sci. and Tech., Antwerpen, p.218, 1983 9645 1451 169 11. Ellis-Akovali Y.A., Nucl. Data Sheets, 33, 119, 1981 9645 1451 170 12. Fomushkin E.F., G.F. Novoselov, Y.I. Vinogradov 9645 1451 171 et al., Atomnaya Energiya, 69, 258 (1990). 9645 1451 172 13. FURSOV B.I., SAMYLIN B.F., SMIRENKIN G.N. ET AL. Nuclear Data 9645 1451 173 for Science and Technology, Gatlinburg, 1994, p.269, ANS. 9645 1451 174 14 Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl. 9645 1451 175 Phys. 47, 224 (1988). 9645 1451 176 15. Maslov V.M. Ann. Nucl. Energy, 20, 163, 1993. 9645 1451 177 9645 1451 178 1 451 240 09645 1451 179 1 452 9 09645 1451 180 1 455 7 09645 1451 181 1 456 9 09645 1451 182 2 151 425 09645 1451 183 3 1 25 09645 1451 184 3 2 25 09645 1451 185 3 4 24 09645 1451 186 3 16 9 09645 1451 187 3 17 7 09645 1451 188 3 18 25 09645 1451 189 3 19 25 09645 1451 190 3 20 10 09645 1451 191 3 21 7 09645 1451 192 3 51 24 09645 1451 193 3 52 23 09645 1451 194 3 53 22 09645 1451 195 3 54 15 09645 1451 196 3 55 21 09645 1451 197 3 56 15 09645 1451 198 3 57 14 09645 1451 199 3 58 13 09645 1451 200 3 59 13 09645 1451 201 3 60 13 09645 1451 202 3 61 18 09645 1451 203 3 62 12 09645 1451 204 3 63 11 09645 1451 205 3 64 11 09645 1451 206 3 65 11 09645 1451 207 3 66 10 09645 1451 208 3 67 9 09645 1451 209 3 91 15 09645 1451 210 3 102 19 09645 1451 211 4 2 94 09645 1451 212 4 16 2 09645 1451 213 4 17 2 09645 1451 214 4 18 2 09645 1451 215 4 51 94 09645 1451 216 4 52 85 09645 1451 217 4 53 84 09645 1451 218 4 54 2 09645 1451 219 4 55 2 09645 1451 220 4 56 2 09645 1451 221 4 57 2 09645 1451 222 4 58 2 09645 1451 223 4 59 2 09645 1451 224 4 60 2 09645 1451 225 4 61 2 09645 1451 226 4 62 2 09645 1451 227 4 63 2 09645 1451 228 4 64 2 09645 1451 229 4 65 2 09645 1451 230 4 66 2 09645 1451 231 4 67 2 09645 1451 232 4 91 2 09645 1451 233 5 16 223 09645 1451 234 5 17 66 09645 1451 235 5 18 918 09645 1451 236 5 19 928 09645 1451 237 5 20 578 09645 1451 238 5 21 316 09645 1451 239 5 91 246 09645 1451 240 9645 1 0 241