JENDL-5 (Neutron sublibrary (activation cs)) Rb- 86 0 0 0 0 3.708600+4 8.517315+1 0 0 6 13728 1451 1 0.000000+0 1.000000+0 0 0 0 63728 1451 2 1.000000+0 2.000000+7 0 0 10 53728 1451 3 2.936000+2 0.000000+0 4 0 342 263728 1451 4 37-Rb- 86 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 3728 1451 5 DIST-DEC21 20091005 3728 1451 6 ----JENDL-5 MATERIAL 3728 3728 1451 7 -----INCIDENT NEUTRON DATA 3728 1451 8 ------ENDF-6 FORMAT 3728 1451 9 3728 1451 10 History 3728 1451 11 09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda. 3728 1451 12 09-10 Compiled by K. Shibata. 3728 1451 13 21-11 revised by O.Iwamoto 3728 1451 14 (MF8/MT4,16,17,22,28,32,102-107) added 3728 1451 15 3728 1451 16 MF= 1 General information 3728 1451 17 MT=451 Descriptive data and directory 3728 1451 18 3728 1451 19 MF= 2 Resonance parameters 3728 1451 20 MT=151 Resolved and unresolved resonance parameters 3728 1451 21 No resovled resonance parameters are given. 3728 1451 22 The 1/v-shaped capture cross section is assumed below 75 eV.3728 1451 23 At 0.0253 eV, the cross section was normalized to the value 3728 1451 24 of 1.5622, which was adopted in ENDF/B-VII.0. 3728 1451 25 The scattering cross section was calculated from 4*pi*R**2, 3728 1451 26 where the scattering radius R was obtained in the unresolved3728 1451 27 resonance region: R=6.515 fm. 3728 1451 28 Unresolved resonance region: 75 eV - 380 keV 3728 1451 29 The parameters were obtained by fitting to the total and 3728 1451 30 capture cross sections calculated from POD /1/. The 3728 1451 31 unresolved parameters should be used only for self-shielding3728 1451 32 calculation. 3728 1451 33 3728 1451 34 Thermal cross sections and resonance integrals at 300 K 3728 1451 35 ---------------------------------------------------------- 3728 1451 36 0.0253 eV res. integ. (*) 3728 1451 37 (barns) (barns) 3728 1451 38 ---------------------------------------------------------- 3728 1451 39 Total 6.9417E+00 3728 1451 40 Elastic 5.3699E+00 3728 1451 41 n,gamma 1.5629E+00 2.4614E+01 3728 1451 42 ---------------------------------------------------------- 3728 1451 43 (*) Integrated from 0.5 eV to 10 MeV. 3728 1451 44 3728 1451 45 MF= 3 Neutron cross sections 3728 1451 46 MT= 1 Total cross section 3728 1451 47 Sum of elatic and non-elastic cross sections below 75 eV. 3728 1451 48 Calculated with POD code /1/ above 75 eV. 3728 1451 49 3728 1451 50 MT= 2 Elastic scattering cross section 3728 1451 51 Obtained by subtracting non-elastic cross sections from total 3728 1451 52 cross sections above 75 eV. A constant value of 5.334 b was 3728 1451 53 assumed below 75 eV. 3728 1451 54 3728 1451 55 MT= 3 Non-elastic cross section 3728 1451 56 Sum of parial non-elastic cross sections. 3728 1451 57 3728 1451 58 MT= 4,51-91 (n,n') cross section 3728 1451 59 Calculated with POD code /1/. 3728 1451 60 3728 1451 61 MT= 16 (n,2n) cross section 3728 1451 62 Calculated with POD code /1/. 3728 1451 63 3728 1451 64 MT= 17 (n,3n) cross section 3728 1451 65 Calculated with POD code /1/. 3728 1451 66 3728 1451 67 MT= 22 (n,na) cross section 3728 1451 68 Calculated with POD code /1/. 3728 1451 69 3728 1451 70 MT= 28 (n,np) cross section 3728 1451 71 Calculated with POD code /1/. 3728 1451 72 3728 1451 73 MT= 32 (n,nd) cross section 3728 1451 74 Calculated with POD code /1/. 3728 1451 75 3728 1451 76 MT=102 Capture cross section 3728 1451 77 Calculated with POD code /1/. 3728 1451 78 3728 1451 79 MT=103 (n,p) cross section 3728 1451 80 Calculated with POD code /1/. 3728 1451 81 3728 1451 82 MT=104 (n,d) cross section 3728 1451 83 Calculated with POD code /1/. 3728 1451 84 3728 1451 85 MT=105 (n,t) cross section 3728 1451 86 Calculated with POD code /1/. 3728 1451 87 3728 1451 88 MT=106 (n,He3) cross section 3728 1451 89 Calculated with POD code /1/. 3728 1451 90 3728 1451 91 MT=107 (n,a) cross section 3728 1451 92 Calculated with POD code /1/. 3728 1451 93 3728 1451 94 MT=203 (n,xp) cross section 3728 1451 95 Calculated with POD code /1/. 3728 1451 96 3728 1451 97 MT=204 (n,xd) cross section 3728 1451 98 Calculated with POD code /1/. 3728 1451 99 3728 1451 100 MT=205 (n,xt) cross section 3728 1451 101 Calculated with POD code /1/. 3728 1451 102 3728 1451 103 MT=206 (n,xHe3) cross section 3728 1451 104 Calculated with POD code /1/. 3728 1451 105 3728 1451 106 MT=207 (n,xa) cross section 3728 1451 107 Calculated with POD code /1/. 3728 1451 108 3728 1451 109 MF= 4 Angular distributions of emitted neutrons 3728 1451 110 MT= 2 Elastic scattering 3728 1451 111 Calculated with POD code /1/. 3728 1451 112 3728 1451 113 MF= 6 Energy-angle distributions of emitted particles 3728 1451 114 MT= 16 (n,2n) reaction 3728 1451 115 Neutron spectra calculated with POD/1/. 3728 1451 116 3728 1451 117 MT= 17 (n,3n) reaction 3728 1451 118 Neutron spectra calculated with POD/1/. 3728 1451 119 3728 1451 120 MT= 22 (n,na) reaction 3728 1451 121 Neutron spectra calculated with POD/1/. 3728 1451 122 3728 1451 123 MT= 28 (n,np) reaction 3728 1451 124 Neutron spectra calculated with POD/1/. 3728 1451 125 3728 1451 126 MT= 32 (n,nd) reaction 3728 1451 127 Neutron spectra calculated with POD/1/. 3728 1451 128 3728 1451 129 MT= 51 (n,n') reaction 3728 1451 130 Neutron angular distributions calculated with POD/1/. 3728 1451 131 3728 1451 132 MT= 52 (n,n') reaction 3728 1451 133 Neutron angular distributions calculated with POD/1/. 3728 1451 134 3728 1451 135 MT= 53 (n,n') reaction 3728 1451 136 Neutron angular distributions calculated with POD/1/. 3728 1451 137 3728 1451 138 MT= 54 (n,n') reaction 3728 1451 139 Neutron angular distributions calculated with POD/1/. 3728 1451 140 3728 1451 141 MT= 55 (n,n') reaction 3728 1451 142 Neutron angular distributions calculated with POD/1/. 3728 1451 143 3728 1451 144 MT= 56 (n,n') reaction 3728 1451 145 Neutron angular distributions calculated with POD/1/. 3728 1451 146 3728 1451 147 MT= 57 (n,n') reaction 3728 1451 148 Neutron angular distributions calculated with POD/1/. 3728 1451 149 3728 1451 150 MT= 58 (n,n') reaction 3728 1451 151 Neutron angular distributions calculated with POD/1/. 3728 1451 152 3728 1451 153 MT= 59 (n,n') reaction 3728 1451 154 Neutron angular distributions calculated with POD/1/. 3728 1451 155 3728 1451 156 MT= 60 (n,n') reaction 3728 1451 157 Neutron angular distributions calculated with POD/1/. 3728 1451 158 3728 1451 159 MT= 61 (n,n') reaction 3728 1451 160 Neutron angular distributions calculated with POD/1/. 3728 1451 161 3728 1451 162 MT= 62 (n,n') reaction 3728 1451 163 Neutron angular distributions calculated with POD/1/. 3728 1451 164 3728 1451 165 MT= 63 (n,n') reaction 3728 1451 166 Neutron angular distributions calculated with POD/1/. 3728 1451 167 3728 1451 168 MT= 64 (n,n') reaction 3728 1451 169 Neutron angular distributions calculated with POD/1/. 3728 1451 170 3728 1451 171 MT= 65 (n,n') reaction 3728 1451 172 Neutron angular distributions calculated with POD/1/. 3728 1451 173 3728 1451 174 MT= 66 (n,n') reaction 3728 1451 175 Neutron angular distributions calculated with POD/1/. 3728 1451 176 3728 1451 177 MT= 67 (n,n') reaction 3728 1451 178 Neutron angular distributions calculated with POD/1/. 3728 1451 179 3728 1451 180 MT= 68 (n,n') reaction 3728 1451 181 Neutron angular distributions calculated with POD/1/. 3728 1451 182 3728 1451 183 MT= 69 (n,n') reaction 3728 1451 184 Neutron angular distributions calculated with POD/1/. 3728 1451 185 3728 1451 186 MT= 70 (n,n') reaction 3728 1451 187 Neutron angular distributions calculated with POD/1/. 3728 1451 188 3728 1451 189 MT= 71 (n,n') reaction 3728 1451 190 Neutron angular distributions calculated with POD/1/. 3728 1451 191 3728 1451 192 MT= 72 (n,n') reaction 3728 1451 193 Neutron angular distributions calculated with POD/1/. 3728 1451 194 3728 1451 195 MT= 73 (n,n') reaction 3728 1451 196 Neutron angular distributions calculated with POD/1/. 3728 1451 197 3728 1451 198 MT= 74 (n,n') reaction 3728 1451 199 Neutron angular distributions calculated with POD/1/. 3728 1451 200 3728 1451 201 MT= 75 (n,n') reaction 3728 1451 202 Neutron angular distributions calculated with POD/1/. 3728 1451 203 3728 1451 204 MT= 76 (n,n') reaction 3728 1451 205 Neutron angular distributions calculated with POD/1/. 3728 1451 206 3728 1451 207 MT= 77 (n,n') reaction 3728 1451 208 Neutron angular distributions calculated with POD/1/. 3728 1451 209 3728 1451 210 MT= 91 (n,n') reaction 3728 1451 211 Neutron spectra calculated with POD/1/. 3728 1451 212 3728 1451 213 MT= 203 (n,xp) reaction 3728 1451 214 Proton spectra calculated with POD/1/. 3728 1451 215 3728 1451 216 MT= 204 (n,xd) reaction 3728 1451 217 Deuteron spectra calculated with POD/1/. 3728 1451 218 3728 1451 219 MT= 205 (n,xt) reaction 3728 1451 220 Triton spectra calculated with POD/1/. 3728 1451 221 3728 1451 222 MT= 206 (n,xHe3) reaction 3728 1451 223 He3 spectra calculated with POD/1/. 3728 1451 224 3728 1451 225 MT= 207 (n,xa) reaction 3728 1451 226 Alpha spectra calculated with POD/1/. 3728 1451 227 3728 1451 228 MF=12 Gamma-ray multiplicities 3728 1451 229 MT= 3 Non-elastic gamma emission 3728 1451 230 Calculated with POD code /1/. 3728 1451 231 3728 1451 232 MF=14 Gamma-ray angular distributions 3728 1451 233 MT= 3 Non-elastic gamma emission 3728 1451 234 Assumed to be isotropic. 3728 1451 235 3728 1451 236 MF=15 Gamma-ray spectra 3728 1451 237 MT= 3 Non-elastic gamma emission 3728 1451 238 Calculated with POD code /1/. 3728 1451 239 3728 1451 240 3728 1451 241 3728 1451 242 *************************************************************** 3728 1451 243 * Nuclear Model Calculations with POD Code /1/ * 3728 1451 244 *************************************************************** 3728 1451 245 1. Theoretical models 3728 1451 246 The POD code is based on the spherical optical model, the 3728 1451 247 distorted-wave Born approximaiton (DWBA), one-component exciton 3728 1451 248 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3728 1451 249 tical model. With the preequilibrim model, semi-empirical 3728 1451 250 pickup and knockout process can be taken into account for 3728 1451 251 composite-particle emission. The gamma-ray emission from the 3728 1451 252 compound nucleus can be calculated within the framework of the 3728 1451 253 exciton model. The code is capable of reading in particle 3728 1451 254 transmission coefficients calculated by separate spherical or 3728 1451 255 coupled-channel optical model code. 3728 1451 256 3728 1451 257 2. Optical model parameters 3728 1451 258 Neutrons: 3728 1451 259 Coupled-channel optical model parameters /2/ 3728 1451 260 Protons: 3728 1451 261 Koning and Delaroche /3/ 3728 1451 262 Deuterons: 3728 1451 263 Lohr and Haeberli /4/ 3728 1451 264 Tritons: 3728 1451 265 Becchetti and Greenlees /5/ 3728 1451 266 He-3: 3728 1451 267 Becchetti and Greenlees /5/ 3728 1451 268 Alphas: 3728 1451 269 Lemos /6/ potentials modified by Arthur and Young /7/ 3728 1451 270 3728 1451 271 3. Level scheme of Rb- 86 3728 1451 272 ------------------------- 3728 1451 273 No. Ex(MeV) J PI 3728 1451 274 ------------------------- 3728 1451 275 0 0.00000 2 - 3728 1451 276 1 0.48820 1 + 3728 1451 277 2 0.55605 6 - 3728 1451 278 3 0.55700 3 - 3728 1451 279 4 0.78030 7 - 3728 1451 280 5 0.87320 4 - 3728 1451 281 6 0.97870 3 - 3728 1451 282 7 1.02720 1 + 3728 1451 283 8 1.03270 3 - 3728 1451 284 9 1.09280 5 - 3728 1451 285 10 1.10560 2 + 3728 1451 286 11 1.12200 2 + 3728 1451 287 12 1.15600 0 + 3728 1451 288 13 1.19640 3 - 3728 1451 289 14 1.24800 4 - 3728 1451 290 15 1.30510 3 + 3728 1451 291 16 1.30900 6 - 3728 1451 292 17 1.38940 3 + 3728 1451 293 18 1.41200 5 - 3728 1451 294 19 1.43900 3 - 3728 1451 295 20 1.47080 2 + 3728 1451 296 21 1.50170 3 + 3728 1451 297 22 1.55000 6 - 3728 1451 298 23 1.55850 7 + 3728 1451 299 24 1.66680 2 + 3728 1451 300 25 1.68370 8 + 3728 1451 301 26 1.70920 2 + 3728 1451 302 27 1.73800 1 - 3728 1451 303 ------------------------- 3728 1451 304 Levels above 1.74800 MeV are assumed to be continuous. 3728 1451 305 3728 1451 306 4. Level density parameters 3728 1451 307 Energy-dependent parameters of Mengoni-Nakajima /8/ were used 3728 1451 308 ---------------------------------------------------------- 3728 1451 309 Nuclei a* Pair Esh T E0 Ematch Elv_max 3728 1451 310 1/MeV MeV MeV MeV MeV MeV MeV 3728 1451 311 ---------------------------------------------------------- 3728 1451 312 Rb- 87 10.932 1.287 -0.777 0.871 -0.070 6.722 2.414 3728 1451 313 Rb- 86 9.932 0.000 0.007 0.898 -1.348 5.547 1.738 3728 1451 314 Rb- 85 10.720 1.302 1.529 0.855 -0.855 7.650 2.088 3728 1451 315 Rb- 84 11.060 0.000 2.125 0.783 -1.914 5.688 0.797 3728 1451 316 Kr- 86 11.310 2.588 -0.507 0.715 2.085 6.130 3.575 3728 1451 317 Kr- 85 11.890 1.302 0.718 0.695 0.285 5.433 2.637 3728 1451 318 Kr- 84 11.089 2.619 1.235 0.745 1.364 7.286 3.951 3728 1451 319 Br- 84 11.060 0.000 0.608 0.898 -2.409 6.862 0.408 3728 1451 320 Br- 83 10.507 1.317 1.382 0.813 -0.276 6.734 2.134 3728 1451 321 Br- 82 10.599 0.000 2.092 0.832 -2.117 6.154 1.261 3728 1451 322 ---------------------------------------------------------- 3728 1451 323 3728 1451 324 5. Gamma-ray strength functions 3728 1451 325 M1, E2: Standard Lorentzian (SLO) 3728 1451 326 E1 : Generalized Lorentzian (GLO) /9/ 3728 1451 327 3728 1451 328 6. Preequilibrium process 3728 1451 329 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3728 1451 330 Preequilibrium capture is on. 3728 1451 331 3728 1451 332 References 3728 1451 333 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3728 1451 334 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 3728 1451 335 3) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3728 1451 336 4) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3728 1451 337 5) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3728 1451 338 Phenomena in Nuclear Reactions," p.682, The University 3728 1451 339 of Wisconsin Press (1971). 3728 1451 340 6) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3728 1451 341 7) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3728 1451 342 8) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3728 1451 343 (1994). 3728 1451 344 9) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 3728 1451 345 3728 1451 346 1 451 372 13728 1451 347 2 151 4 13728 1451 348 3 4 24 13728 1451 349 3 16 8 13728 1451 350 3 17 4 13728 1451 351 3 22 7 13728 1451 352 3 28 8 13728 1451 353 3 32 6 13728 1451 354 3 102 126 13728 1451 355 3 103 15 13728 1451 356 3 104 9 13728 1451 357 3 105 8 13728 1451 358 3 106 5 13728 1451 359 3 107 12 13728 1451 360 8 4 2 13728 1451 361 8 16 2 13728 1451 362 8 17 2 13728 1451 363 8 22 2 13728 1451 364 8 28 2 13728 1451 365 8 32 2 13728 1451 366 8 102 2 13728 1451 367 8 103 2 13728 1451 368 8 104 2 13728 1451 369 8 105 2 13728 1451 370 8 106 2 13728 1451 371 8 107 2 13728 1451 372 3728 1 099999 3728 0 0 0 3.708600+4 8.517315+1 0 0 1 03728 2151 1 3.708600+4 1.000000+0 0 0 1 03728 2151 2 7.500000+1 3.800000+5 0 0 0 03728 2151 3 2.000000+0 6.515000-1 0 0 0 03728 2151 4 3728 2 099999 3728 0 0 0 3.708600+4 8.517315+1 0 0 0 03728 3 4 1 0.000000+0-4.882000+5 0 0 1 633728 3 4 2 63 2 3728 3 4 3 4.939319+5 0.000000+0 5.000000+5 2.066000-2 5.625785+5 7.606700-23728 3 4 4 5.635396+5 7.703174-2 6.000000+5 1.919500-1 7.000000+5 3.990400-13728 3 4 5 7.894613+5 5.257351-1 8.000000+5 5.408283-1 8.834521+5 6.166142-13728 3 4 6 9.000000+5 6.501920-1 9.901907+5 7.418672-1 1.000000+6 7.638380-13728 3 4 7 1.039260+6 7.607170-1 1.044825+6 7.610556-1 1.105630+6 7.837912-13728 3 4 8 1.118581+6 7.904185-1 1.135173+6 8.024130-1 1.169572+6 8.345764-13728 3 4 9 1.210447+6 8.748596-1 1.262653+6 9.426988-1 1.320423+6 1.031508+03728 3 4 10 1.324369+6 1.038527+0 1.405713+6 1.187174+0 1.428578+6 1.234624+03728 3 4 11 1.455895+6 1.294479+0 1.488068+6 1.372830+0 1.500000+6 1.407174+03728 3 4 12 1.519331+6 1.412807+0 1.568198+6 1.431888+0 1.576798+6 1.435637+03728 3 4 13 1.686370+6 1.483865+0 1.703468+6 1.492990+0 1.729267+6 1.506786+03728 3 4 14 1.758405+6 1.525112+0 1.768523+6 1.532704+0 2.000000+6 1.798381+03728 3 4 15 2.500000+6 1.984232+0 3.000000+6 2.068936+0 3.500000+6 2.049001+03728 3 4 16 4.000000+6 1.983665+0 4.500000+6 1.904300+0 5.000000+6 1.834518+03728 3 4 17 5.500000+6 1.780814+0 6.000000+6 1.751634+0 6.500000+6 1.736622+03728 3 4 18 7.000000+6 1.731685+0 7.500000+6 1.731422+0 8.000000+6 1.731452+03728 3 4 19 8.500000+6 1.728650+0 9.000000+6 1.706107+0 9.500000+6 1.593030+03728 3 4 20 1.000000+7 1.392450+0 1.100000+7 1.034662+0 1.200000+7 7.586684-13728 3 4 21 1.300000+7 5.759181-1 1.400000+7 4.509008-1 1.450000+7 4.141892-13728 3 4 22 1.500000+7 3.788783-1 1.600000+7 3.312289-1 1.700000+7 2.971612-13728 3 4 23 1.800000+7 2.717235-1 1.900000+7 2.514592-1 2.000000+7 2.357254-13728 3 4 24 3728 3 099999 3.708600+4 8.517315+1 0 0 0 03728 3 16 1 -8.651003+6-8.651003+6 0 0 1 153728 3 16 2 15 2 3728 3 16 3 8.752572+6 0.000000+0 9.000000+6 1.804000-2 9.500000+6 1.248000-13728 3 16 4 1.000000+7 3.194000-1 1.100000+7 6.658000-1 1.200000+7 9.280000-13728 3 16 5 1.300000+7 1.090000+0 1.400000+7 1.189000+0 1.450000+7 1.212000+03728 3 16 6 1.500000+7 1.233000+0 1.600000+7 1.253000+0 1.700000+7 1.261000+03728 3 16 7 1.800000+7 1.264000+0 1.900000+7 1.263000+0 2.000000+7 1.258000+03728 3 16 8 3728 3 099999 3.708600+4 8.517315+1 0 0 0 03728 3 17 1 -1.913962+7-1.913962+7 0 0 1 23728 3 17 2 2 2 3728 3 17 3 1.936434+7 0.000000+0 2.000000+7 2.206000-4 3728 3 17 4 3728 3 099999 3.708600+4 8.517315+1 0 0 0 03728 3 22 1 -7.675468+6-7.675468+6 0 0 1 103728 3 22 2 10 2 3728 3 22 3 7.765584+6 0.000000+0 1.300000+7 0.000000+0 1.400000+7 2.475000-73728 3 22 4 1.450000+7 1.994000-6 1.500000+7 8.627000-6 1.600000+7 8.229000-53728 3 22 5 1.700000+7 3.932000-4 1.800000+7 1.248000-3 1.900000+7 2.756000-33728 3 22 6 2.000000+7 4.650000-3 3728 3 22 7 3728 3 099999 3.708600+4 8.517315+1 0 0 0 03728 3 28 1 -8.555720+6-8.555720+6 0 0 1 133728 3 28 2 13 2 3728 3 28 3 8.656171+6 0.000000+0 1.000000+7 0.000000+0 1.100000+7 7.190000-63728 3 28 4 1.200000+7 2.599000-4 1.300000+7 1.698000-3 1.400000+7 5.570000-33728 3 28 5 1.450000+7 8.304000-3 1.500000+7 1.223000-2 1.600000+7 2.103000-23728 3 28 6 1.700000+7 3.119000-2 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