95 - Am - 242m 9542 0 0 0 9.52420+04 2.39980+02 1 1 0 19542 1451 1 4.86300+04 1.00000+00 3 1 0 69542 1451 2 1.00000+00 0.00000+00 0 0 10 69542 1451 3 0.00000+00 0.00000+00 0 0 172 819542 1451 4 95-Am-242M MINSK BYEL EVAL-DEC96 9542 1451 5 DIST-DEC96 9542 1451 6 9542 1451 7 V.M. MASLOV, E.Sh. SUKHOVITSKIJ, 9542 1451 8 Yu.V. PORODZINSKIJ, G.B. MOROGOVSKIJ 9542 1451 9 9542 1451 10 STATUS 9542 1451 11 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95 9542 1451 12 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW). 9542 1451 13 FINANCING PARTY OF THE ISTC FOR THE PROJECT IS JAPAN. 9542 1451 14 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI) 9542 1451 15 DOCUMENTED IN INDC(BLR)-007, 1997. 9542 1451 16 9542 1451 17 MF=1 GENERAL INFORMATION 9542 1451 18 9542 1451 19 MT=451 COMMENTS AND DICTIONARY 9542 1451 20 MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION 9542 1451 21 SUM OF MT=455 AND MT=456. 9542 1451 22 MT=455 DELAYED NEUTRON DATA 9542 1451 23 NUMBER OF DELAYED NEUTRONS AND 9542 1451 24 DECAY CONSTANTS FROM BRADY ET AL./1/ 9542 1451 25 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9542 1451 26 MADLAND-NIX MODEL CALCULATIONS /2/ FITTED TO 9542 1451 27 THE MEASURED DATA OF HOWE ET AL./3/ 9542 1451 28 ABOVE EMISSIVE FISSION THRESHOLD 9542 1451 29 SUPERPOSITION OF NEUTRON EMISSION 9542 1451 30 IN (N,XNF) REACTIONS /4/ AND PROMPT FISSION 9542 1451 31 NEUTRONS IS EMPLOYED. 9542 1451 32 9542 1451 33 MF=2 RESONANCE PARAMETERS 9542 1451 34 9542 1451 35 MT=151 RESONANCE PARAMETERS (MLBW) 9542 1451 36 RESOLVED RESONANCE REGION : 1.0E-5 - 43 EV 9542 1451 37 PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED UPON 9542 1451 38 THE FISSION CROSS SECTION MEASUREMENTS OF BROWNE ET AL.9542 1451 39 /5/ 9542 1451 40 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE 9542 1451 41 INTEGRALS ARE: 9542 1451 42 2200 M/SEC RES.INTEG. 9542 1451 43 TOTAL 7624.69 b - 9542 1451 44 ELASTIC 5.2526 b - 9542 1451 45 FISSION 6390.21 b 1543.91 9542 1451 46 CAPTURE 1229.23 b 239.610 9542 1451 47 9542 1451 48 UNRESOLVED RESONANCE REGION : 9542 1451 49 ENERGY INDEPENDENT PARAMETERS: 9542 1451 50 R=9.1677 FM FROM OPTICAL MODEL CALCULATIONS 9542 1451 51 S1=2.020*10-4 FROM OPTICAL MODEL CALCULATIONS 9542 1451 52 S2=1.540*10-4 FROM OPTICAL MODEL CALCULATIONS 9542 1451 53 ENERGY DEPENDENT PARAMETERS: 9542 1451 54 S0-DECREASES FROM 1.215-4(0.15KEV) TO 1.15-4(27.28KEV),9542 1451 55 BELOW 0.1 KEV FLUCTUATES TO FIT FISSION CROSS SECTION. 9542 1451 56 D - SPIN DEPENDENT, NORMALIZED TO =0.271 EV 9542 1451 57 WITH ACCOUNT OF LEVEL MISSING /6/. 9542 1451 58 WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE 9542 1451 59 SPECTRA AT INNER AND OUTER BARRIER HUMPS, NORMALIZED 9542 1451 60 TO =0.395 mEV TO FIT UNRESOLVED RESONANCE REGION9542 1451 61 EXPERIMENTAL FISSION DATA /5/. 9542 1451 62 WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION AND 9542 1451 63 NEUTRON EMISSION COMPETITION, SPIN DEPENDENT. NORMA- 9542 1451 64 LIZED TO = 0.050 EV. 9542 1451 65 9542 1451 66 MF=3 NEUTRON CROSS SECTIONS 9542 1451 67 9542 1451 68 MT=1,4,51-75,91,102. TOTAL, ELASTIC AND INELASTIC 9542 1451 69 SCATTERING, CAPTURE CROSS SECTION 9542 1451 70 TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=55, 9542 1451 71 59 AND OPTICAL TRANSMISSION COEFFICIENTS FROM 9542 1451 72 COUPLED CHANNELS CALCULATIONS. 9542 1451 73 THE DEFORMED OPTICAL POTENTIAL USED: 9542 1451 74 VR=(46.10-0.3*E) MEV RR=1.26 FM AR=0.615 FM 9542 1451 75 WD=(3.53+0.4*E) MEV E < 10 MEV RD=1.24 FM 9542 1451 76 WD= 7.50 MEV E=> 10 MEV AD=0.5 FM 9542 1451 77 VSO=6.2 MEV RSO=1.12 FM ASO=0.47 FM B2=0.206 B4=0.092 9542 1451 78 THREE LEVELS OF METASTABLE STATE ROTATIONAL BAND 9542 1451 79 ARE COUPLED. 9542 1451 80 CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL 9542 1451 81 MODEL, SEE MT=18-21 9542 1451 82 ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE 9542 1451 83 CONSTANT. 9542 1451 84 ADOPTED LEVEL SCHEME OF AM-242 FROM NUCLEAR DATA 9542 1451 85 SHEETS /7/. 9542 1451 86 9542 1451 87 No ENERGY(MEV) SPIN-PARITY K 9542 1451 88 9542 1451 89 g.s. 0.0 5 - 0 9542 1451 90 1 -0.04863 1 - 0 9542 1451 91 2 -0.00453 0 - 5 9542 1451 92 3 0.00427 3 - 0 9542 1451 93 4 0.02717 2 - 0 9542 1451 94 5 0.06537 6 - 5 9542 1451 95 6 0.09137 6 - 6 9542 1451 96 7 0.09937 5 - 0 9542 1451 97 8 0.10127 4 - 0 9542 1451 98 9 0.14137 7 - 5 9542 1451 99 10 0.14897 3 - 9542 1451 100 11 0.16837 7 - 6 9542 1451 101 12 0.17137 1 - 1 9542 1451 102 13 0.18187 2 + 1 9542 1451 103 14 0.19337 2 - 1 9542 1451 104 15 0.19547 3 - 3 9542 1451 105 16 0.21437 6 - 0 9542 1451 106 17 0.21447 7 - 0 9542 1451 107 18 0.22147 2 + 9542 1451 108 19 0.22637 3 - 1 9542 1451 109 20 0.23467 3 + 9542 1451 110 21 0.23977 4 - 3 9542 1451 111 22 0.24317 2 - 2 9542 1451 112 23 0.25637 8 - 6 9542 1451 113 24 0.25827 3 - 9542 1451 114 25 0.27037 4 - 1 9542 1451 115 9542 1451 116 9542 1451 117 OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.273 MEV 9542 1451 118 LEVEL DENSITY PARAMETERS: SEE MT 18-21 9542 1451 119 MT=16,17. (N,2N) AND (N,3N) CROSS SECTION 9542 1451 120 FROM STATISTICAL MODEL CALCULATIONS /8/ WITH THE 9542 1451 121 ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-219542 1451 122 MT=18,19,20,21. FISSION CROSS SECTION IS CALCULATED WITHIN 9542 1451 123 STATISTICAL MODEL /9,10/, THE MEASURED DATA OF: 9542 1451 124 BROWNE ET AL./5/ AND FURSOV ET AL./11/ 9542 1451 125 ARE FITTED. 9542 1451 126 THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH 9542 1451 127 THE CONTRIBUTION OF EMISSIVE FISSION TO TOTAL FISSION 9542 1451 128 CROSS SECTION ACCORDING TO /9,12/. 9542 1451 129 9542 1451 130 MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS 9542 1451 131 9542 1451 132 FOR MT=2, 55, 59 FROM COUPLED CHANNELS CALCULATIONS 9542 1451 133 WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION. 9542 1451 134 9542 1451 135 MT=16,17,18-21,51-54,56-58,60-66,91 - ISOTROPIC 9542 1451 136 9542 1451 137 MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS 9542 1451 138 9542 1451 139 ENERGY DISTRIBUTIONS FOR MT=16,17 WERE 9542 1451 140 CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON 9542 1451 141 EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY 9542 1451 142 WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF 9542 1451 143 THE FIRST NEUTRON /4/ 9542 1451 144 ENERGY DISTRIBUTIONS FOR MT=18,19,20,21 WERE CALCULATED 9542 1451 145 BY MADLAND-NIX MODEL /2/ WITH ACCOUNT OF COMPETITION 9542 1451 146 BETWEEN MULTIPLE-CHANCE FISSION PROCESSES UP THROUGH 9542 1451 147 THIRD-CHANCE FISSION WITH THE ALLOWANCE OF PRE-EQUILIBRIUM9542 1451 148 EMISSION OF THE FIRST NEUTRON /4,8/ 9542 1451 149 9542 1451 150 REFERENCES 9542 1451 151 9542 1451 152 1. Brady M.C., Wright R.Q., England T.R., Report 9542 1451 153 ORNL/CSD/TM-226(1991), IAEA-NDS-102, 1992. 9542 1451 154 2. Madland D.G., Nix J.R., Nucl. Sci. Engng. 81, 213 (1982). 9542 1451 155 3. Howe R.E., Browne J.C., Dougan R.J., Dupzyk R.J., Landrum J.H.9542 1451 156 Nucl. Sci. Eng.,77, 454 (1984). 9542 1451 157 4. Maslov V.M., Porodzinskij Yu.V., Sukhovitskij E.Sh., Proc. 9542 1451 158 Int. Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR, 9542 1451 159 V.1, p.413, 1988. 9542 1451 160 5. Browne J.C., White R.M., Howe R.E. et al., Phys. Rev. C, 9542 1451 161 29, 2188 (1984). 9542 1451 162 6. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants, 9542 1451 163 4, p.27, 1987 (in Russian). 9542 1451 164 7. ENSDF, 1995. 9542 1451 165 8. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl. 9542 1451 166 Phys. 47, 224 (1988). 9542 1451 167 9. Ignatjuk A.V., Maslov V.M., Proc. Int. Symp. Nuclear Data 9542 1451 168 Evaluation Methodology, Brookhaven, USA, October 12-16, 1992, 9542 1451 169 p.440, World Scientific, 1993. 9542 1451 170 10. Maslov V.M. Sov. J. At. Energy 64, 478 (1988). 9542 1451 171 11. Fursov B.I., Samylin B.F., Smirenkin G.N., Polynov V.N., 9542 1451 172 Nuclear Data for Science and Technology, Proc. Int. Conf., 9542 1451 173 Gatlinburg, Tennessee, USA, May 9-13, 1994, v.1,p.269. 9542 1451 174 12. Maslov V.M., Kikuchi Y. JAERI-Research 96-030, 1996. 9542 1451 175 9542 1451 176 1 451 248 19542 1451 177 1 452 7 19542 1451 178 1 455 7 19542 1451 179 1 456 7 19542 1451 180 2 151 560 19542 1451 181 3 1 30 19542 1451 182 3 2 27 19542 1451 183 3 4 30 19542 1451 184 3 16 9 19542 1451 185 3 17 7 19542 1451 186 3 18 27 19542 1451 187 3 19 27 19542 1451 188 3 20 10 19542 1451 189 3 21 8 19542 1451 190 3 51 24 19542 1451 191 3 52 23 19542 1451 192 3 53 23 19542 1451 193 3 54 21 19542 1451 194 3 55 25 19542 1451 195 3 56 18 19542 1451 196 3 57 18 19542 1451 197 3 58 17 19542 1451 198 3 59 22 19542 1451 199 3 60 17 19542 1451 200 3 61 16 19542 1451 201 3 62 16 19542 1451 202 3 63 16 19542 1451 203 3 64 15 19542 1451 204 3 65 15 19542 1451 205 3 66 14 19542 1451 206 3 67 14 19542 1451 207 3 68 14 19542 1451 208 3 69 13 19542 1451 209 3 70 13 19542 1451 210 3 71 13 19542 1451 211 3 72 12 19542 1451 212 3 73 12 19542 1451 213 3 74 12 19542 1451 214 3 75 11 19542 1451 215 3 91 16 19542 1451 216 3 102 22 19542 1451 217 4 2 85 19542 1451 218 4 16 2 19542 1451 219 4 17 2 19542 1451 220 4 18 2 19542 1451 221 4 19 2 19542 1451 222 4 20 2 19542 1451 223 4 21 2 19542 1451 224 4 51 2 19542 1451 225 4 52 2 19542 1451 226 4 53 2 19542 1451 227 4 54 2 19542 1451 228 4 55 84 19542 1451 229 4 56 2 19542 1451 230 4 57 2 19542 1451 231 4 58 2 19542 1451 232 4 59 79 19542 1451 233 4 60 2 19542 1451 234 4 61 2 19542 1451 235 4 62 2 19542 1451 236 4 63 2 19542 1451 237 4 64 2 19542 1451 238 4 65 2 19542 1451 239 4 66 2 19542 1451 240 4 67 2 19542 1451 241 4 68 2 19542 1451 242 4 69 2 19542 1451 243 4 70 2 19542 1451 244 4 71 2 19542 1451 245 4 72 2 19542 1451 246 4 73 2 19542 1451 247 4 74 2 19542 1451 248 4 75 2 19542 1451 249 4 91 2 19542 1451 250 5 16 261 19542 1451 251 5 17 88 19542 1451 252 5 18 554 19542 1451 253 5 19 487 19542 1451 254 5 20 388 19542 1451 255 5 21 255 19542 1451 256 5 91 225 19542 1451 257 9542 1 0 258