JENDL-5 (Neutron sublibrary (activation cs)) Ru- 98 0 0 0 0 4.409800+4 9.706423+1 0 0 6 14431 1451 1 0.000000+0 0.000000+0 0 0 0 64431 1451 2 1.000000+0 2.000000+7 0 0 10 54431 1451 3 2.936000+2 0.000000+0 4 0 389 264431 1451 4 44-Ru- 98 JAEA EVAL-JUL12 K.Shibata 4431 1451 5 JNST 50, 1177 (2013) DIST-DEC21 20180517 4431 1451 6 ----JENDL-5 MATERIAL 4431 4431 1451 7 -----INCIDENT NEUTRON DATA 4431 1451 8 ------ENDF-6 FORMAT 4431 1451 9 4431 1451 10 History 4431 1451 11 12-07 The fast neutron cross sections were re-evaluated by 4431 1451 12 K.Shibata (JAEA) /1/ using the POD code /2/. 4431 1451 13 18-05 Activation cross sections added by K.Shibata. 4431 1451 14 21-11 revised by O.Iwamoto 4431 1451 15 (MF8/MT4) added 4431 1451 16 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 4431 1451 17 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 4431 1451 18 4431 1451 19 4431 1451 20 MF= 1 General information 4431 1451 21 MT=451 Descriptive data and directory 4431 1451 22 4431 1451 23 MF= 2 Resonance parameters 4431 1451 24 MT=151 Resolved and unresolved resonance parameters 4431 1451 25 No resolved resonance parameters are given. 4431 1451 26 4431 1451 27 Unresolved resonance region: 140 eV - 300 keV 4431 1451 28 The parameters were obtained by fitting to the calculated 4431 1451 29 total and capture cross sections. The unresolved resonance 4431 1451 30 parameters obtained should be used only for self-shielding 4431 1451 31 calculation. URP's were re-calculated by fitting to the 4431 1451 32 total and capture cross sections calculated by POD /2/. 4431 1451 33 4431 1451 34 Thermal cross sections and resonance integrals at 300 K 4431 1451 35 ---------------------------------------------------------- 4431 1451 36 0.0253 eV res. integ. (*) 4431 1451 37 (barns) (barns) 4431 1451 38 ---------------------------------------------------------- 4431 1451 39 Total 9.0359E+00 4431 1451 40 Elastic 5.0297E+00 4431 1451 41 n,gamma 4.0018E+00 9.4660E+00 4431 1451 42 ---------------------------------------------------------- 4431 1451 43 (*) Integrated from 0.5 eV to 10 MeV. 4431 1451 44 4431 1451 45 MF= 3 Neutron cross sections 4431 1451 46 MT= 1 Total cross section 4431 1451 47 Calculated with POD code /2/. Below 140 eV, the cross 4431 1451 48 sections were obtained by summing up the partial cross 4431 1451 49 cross sections. 4431 1451 50 4431 1451 51 MT= 2 Elastic scattering cross section 4431 1451 52 Below 140 eV, the constant cross section is the same as that 4431 1451 53 for JENDL-4.0, i.e., 5.0 b. Above 170 eV, the cross section 4431 1451 54 was obtained by subtracting the non-elastic cross section 4431 1451 55 from the total cross section. 4431 1451 56 4431 1451 57 MT= 3 Non-elastic cross section 4431 1451 58 Calculated with POD code /2/. 4431 1451 59 4431 1451 60 MT= 4,51-91 (n,n') cross section 4431 1451 61 Calculated with POD code /2/. 4431 1451 62 4431 1451 63 MT= 16 (n,2n) cross section 4431 1451 64 Calculated with POD code /2/. 4431 1451 65 4431 1451 66 MT= 17 (n,3n) cross section 4431 1451 67 Calculated with POD code /2/. 4431 1451 68 4431 1451 69 MT= 22 (n,na) cross section 4431 1451 70 Calculated with POD code /2/. 4431 1451 71 4431 1451 72 MT= 28 (n,np) cross section 4431 1451 73 Calculated with POD code /2/. 4431 1451 74 4431 1451 75 MT= 32 (n,nd) cross section 4431 1451 76 Calculated with POD code /2/. 4431 1451 77 4431 1451 78 MT=102 Capture cross section 4431 1451 79 Calculated with POD code /2/. Below 140 eV, the 1/v 4431 1451 80 cross section was assumed with 4.0 b at 0.0253 eV. 4431 1451 81 4431 1451 82 MT=103 (n,p) cross section 4431 1451 83 Calculated with POD code /2/. 4431 1451 84 4431 1451 85 MT=104 (n,d) cross section 4431 1451 86 Calculated with POD code /2/. 4431 1451 87 4431 1451 88 MT=105 (n,t) cross section 4431 1451 89 Calculated with POD code /2/. 4431 1451 90 4431 1451 91 MT=106 (n,He3) cross section 4431 1451 92 Calculated with POD code /2/. 4431 1451 93 4431 1451 94 MT=107 (n,a) cross section 4431 1451 95 Calculated with POD code /2/. 4431 1451 96 4431 1451 97 MT=203 (n,xp) cross section 4431 1451 98 Calculated with POD code /2/. 4431 1451 99 4431 1451 100 MT=204 (n,xd) cross section 4431 1451 101 Calculated with POD code /2/. 4431 1451 102 4431 1451 103 MT=205 (n,xt) cross section 4431 1451 104 Calculated with POD code /2/. 4431 1451 105 4431 1451 106 MT=206 (n,xHe3) cross section 4431 1451 107 Calculated with POD code /2/. 4431 1451 108 4431 1451 109 MT=207 (n,xa) cross section 4431 1451 110 Calculated with POD code /2/. 4431 1451 111 4431 1451 112 MF= 4 Angular distributions of emitted neutrons 4431 1451 113 MT= 2 Elastic scattering 4431 1451 114 Calculated with POD code /2/. 4431 1451 115 4431 1451 116 MF= 6 Energy-angle distributions of emitted particles 4431 1451 117 MT= 16 (n,2n) reaction 4431 1451 118 Neutron spectra calculated with POD/2/. 4431 1451 119 4431 1451 120 MT= 17 (n,3n) reaction 4431 1451 121 Neutron spectra calculated with POD/2/. 4431 1451 122 4431 1451 123 MT= 22 (n,na) reaction 4431 1451 124 Neutron spectra calculated with POD/2/. 4431 1451 125 4431 1451 126 MT= 28 (n,np) reaction 4431 1451 127 Neutron spectra calculated with POD/2/. 4431 1451 128 4431 1451 129 MT= 32 (n,nd) reaction 4431 1451 130 Neutron spectra calculated with POD/2/. 4431 1451 131 4431 1451 132 MT= 51 (n,n') reaction 4431 1451 133 Neutron angular distributions calculated with POD/2/. 4431 1451 134 4431 1451 135 MT= 52 (n,n') reaction 4431 1451 136 Neutron angular distributions calculated with POD/2/. 4431 1451 137 4431 1451 138 MT= 53 (n,n') reaction 4431 1451 139 Neutron angular distributions calculated with POD/2/. 4431 1451 140 4431 1451 141 MT= 54 (n,n') reaction 4431 1451 142 Neutron angular distributions calculated with POD/2/. 4431 1451 143 4431 1451 144 MT= 55 (n,n') reaction 4431 1451 145 Neutron angular distributions calculated with POD/2/. 4431 1451 146 4431 1451 147 MT= 56 (n,n') reaction 4431 1451 148 Neutron angular distributions calculated with POD/2/. 4431 1451 149 4431 1451 150 MT= 57 (n,n') reaction 4431 1451 151 Neutron angular distributions calculated with POD/2/. 4431 1451 152 4431 1451 153 MT= 58 (n,n') reaction 4431 1451 154 Neutron angular distributions calculated with POD/2/. 4431 1451 155 4431 1451 156 MT= 59 (n,n') reaction 4431 1451 157 Neutron angular distributions calculated with POD/2/. 4431 1451 158 4431 1451 159 MT= 60 (n,n') reaction 4431 1451 160 Neutron angular distributions calculated with POD/2/. 4431 1451 161 4431 1451 162 MT= 61 (n,n') reaction 4431 1451 163 Neutron angular distributions calculated with POD/2/. 4431 1451 164 4431 1451 165 MT= 62 (n,n') reaction 4431 1451 166 Neutron angular distributions calculated with POD/2/. 4431 1451 167 4431 1451 168 MT= 63 (n,n') reaction 4431 1451 169 Neutron angular distributions calculated with POD/2/. 4431 1451 170 4431 1451 171 MT= 64 (n,n') reaction 4431 1451 172 Neutron angular distributions calculated with POD/2/. 4431 1451 173 4431 1451 174 MT= 65 (n,n') reaction 4431 1451 175 Neutron angular distributions calculated with POD/2/. 4431 1451 176 4431 1451 177 MT= 66 (n,n') reaction 4431 1451 178 Neutron angular distributions calculated with POD/2/. 4431 1451 179 4431 1451 180 MT= 67 (n,n') reaction 4431 1451 181 Neutron angular distributions calculated with POD/2/. 4431 1451 182 4431 1451 183 MT= 68 (n,n') reaction 4431 1451 184 Neutron angular distributions calculated with POD/2/. 4431 1451 185 4431 1451 186 MT= 69 (n,n') reaction 4431 1451 187 Neutron angular distributions calculated with POD/2/. 4431 1451 188 4431 1451 189 MT= 70 (n,n') reaction 4431 1451 190 Neutron angular distributions calculated with POD/2/. 4431 1451 191 4431 1451 192 MT= 71 (n,n') reaction 4431 1451 193 Neutron angular distributions calculated with POD/2/. 4431 1451 194 4431 1451 195 MT= 72 (n,n') reaction 4431 1451 196 Neutron angular distributions calculated with POD/2/. 4431 1451 197 4431 1451 198 MT= 73 (n,n') reaction 4431 1451 199 Neutron angular distributions calculated with POD/2/. 4431 1451 200 4431 1451 201 MT= 74 (n,n') reaction 4431 1451 202 Neutron angular distributions calculated with POD/2/. 4431 1451 203 4431 1451 204 MT= 75 (n,n') reaction 4431 1451 205 Neutron angular distributions calculated with POD/2/. 4431 1451 206 4431 1451 207 MT= 76 (n,n') reaction 4431 1451 208 Neutron angular distributions calculated with POD/2/. 4431 1451 209 4431 1451 210 MT= 77 (n,n') reaction 4431 1451 211 Neutron angular distributions calculated with POD/2/. 4431 1451 212 4431 1451 213 MT= 78 (n,n') reaction 4431 1451 214 Neutron angular distributions calculated with POD/2/. 4431 1451 215 4431 1451 216 MT= 91 (n,n') reaction 4431 1451 217 Neutron spectra calculated with POD/2/. 4431 1451 218 4431 1451 219 MT= 203 (n,xp) reaction 4431 1451 220 Proton spectra calculated with POD/2/. 4431 1451 221 4431 1451 222 MT= 204 (n,xd) reaction 4431 1451 223 Deuteron spectra calculated with POD/2/. 4431 1451 224 4431 1451 225 MT= 205 (n,xt) reaction 4431 1451 226 Triton spectra calculated with POD/2/. 4431 1451 227 4431 1451 228 MT= 206 (n,xHe3) reaction 4431 1451 229 He3 spectra calculated with POD/2/. 4431 1451 230 4431 1451 231 MT= 207 (n,xa) reaction 4431 1451 232 Alpha spectra calculated with POD/2/. 4431 1451 233 4431 1451 234 MF= 8 Information on decay data 4431 1451 235 MT= 16 (n,2n) reaction 4431 1451 236 4431 1451 237 MT= 17 (n,3n) reaction 4431 1451 238 4431 1451 239 MT= 22 (n,na) reaction 4431 1451 240 4431 1451 241 MT= 28 (n,np) reaction 4431 1451 242 4431 1451 243 MT= 32 (n,nd) reaction 4431 1451 244 4431 1451 245 MT=102 (n,g) reaction 4431 1451 246 4431 1451 247 MT=103 (n,p) reaction 4431 1451 248 4431 1451 249 MT=104 (n,d) reaction 4431 1451 250 4431 1451 251 MT=105 (n,t) reaction 4431 1451 252 4431 1451 253 MT=106 (n,He3) reaction 4431 1451 254 4431 1451 255 MT=107 (n,a) reaction 4431 1451 256 4431 1451 257 MF=10 Nuclide production cross sections 4431 1451 258 MT= 28 Partial (n,np) reactions 4431 1451 259 Calculated with POD code /2/. 4431 1451 260 4431 1451 261 MT= 32 Partial (n,nd) reactions 4431 1451 262 Calculated with POD code /2/. 4431 1451 263 4431 1451 264 MT=104 Partial (n,d) reactions 4431 1451 265 Calculated with POD code /2/. 4431 1451 266 4431 1451 267 MT=105 Partial (n,t) reactions 4431 1451 268 Calculated with POD code /2/. 4431 1451 269 4431 1451 270 MF=12 Gamma-ray multiplicities 4431 1451 271 MT= 3 Non-elastic gamma emission 4431 1451 272 Calculated with POD code /2/. 4431 1451 273 4431 1451 274 MF=14 Gamma-ray angular distributions 4431 1451 275 MT= 3 Non-elastic gamma emission 4431 1451 276 Assumed to be isotropic. 4431 1451 277 4431 1451 278 MF=15 Gamma-ray spectra 4431 1451 279 MT= 3 Non-elastic gamma emission 4431 1451 280 Calculated with POD code /2/. 4431 1451 281 4431 1451 282 4431 1451 283 4431 1451 284 *************************************************************** 4431 1451 285 * Nuclear Model Calculations with POD Code /2/ * 4431 1451 286 *************************************************************** 4431 1451 287 1. Theoretical models 4431 1451 288 The POD code is based on the spherical optical model, the 4431 1451 289 distorted-wave Born approximaiton (DWBA), one-component exciton 4431 1451 290 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 4431 1451 291 tical model. With the preequilibrim model, semi-empirical 4431 1451 292 pickup and knockout process can be taken into account for 4431 1451 293 composite-particle emission. The gamma-ray emission from the 4431 1451 294 compound nucleus can be calculated within the framework of the 4431 1451 295 exciton model. The code is capable of reading in particle 4431 1451 296 transmission coefficients calculated by separate spherical or 4431 1451 297 coupled-channel optical model code. 4431 1451 298 4431 1451 299 2. Optical model parameters 4431 1451 300 Neutrons: 4431 1451 301 Coupled-channel optical model parameters /3/ 4431 1451 302 Protons: 4431 1451 303 Koning and Delaroche /4/ 4431 1451 304 Deuterons: 4431 1451 305 Lohr and Haeberli /5/ 4431 1451 306 Tritons: 4431 1451 307 Becchetti and Greenlees /6/ 4431 1451 308 He-3: 4431 1451 309 Becchetti and Greenlees /6/ 4431 1451 310 Alphas: 4431 1451 311 Lemos /7/ potentials modified by Arthur and Young /8/ 4431 1451 312 4431 1451 313 3. Level scheme of Ru- 98 4431 1451 314 ------------------------- 4431 1451 315 No. Ex(MeV) J PI 4431 1451 316 ------------------------- 4431 1451 317 0 0.00000 0 + 4431 1451 318 1* 0.65244 2 + 4431 1451 319 2 1.32214 0 + 4431 1451 320 3* 1.39782 4 + 4431 1451 321 4 1.41429 2 + 4431 1451 322 5 1.79696 3 + 4431 1451 323 6 1.81722 2 + 4431 1451 324 7 1.95340 3 + 4431 1451 325 8 2.01270 3 + 4431 1451 326 9 2.22251 6 + 4431 1451 327 10 2.24140 4 + 4431 1451 328 11 2.24590 2 + 4431 1451 329 12 2.26650 4 + 4431 1451 330 13 2.27680 2 + 4431 1451 331 14 2.28500 4 + 4431 1451 332 15 2.36500 4 - 4431 1451 333 16 2.37450 4 - 4431 1451 334 17 2.40900 4 + 4431 1451 335 18 2.42714 2 + 4431 1451 336 19 2.43020 3 + 4431 1451 337 20* 2.43500 3 - 4431 1451 338 21 2.46760 2 + 4431 1451 339 22 2.47380 2 - 4431 1451 340 23 2.54699 6 + 4431 1451 341 24 2.60230 3 - 4431 1451 342 25 2.61980 1 - 4431 1451 343 26 2.65652 5 - 4431 1451 344 27 2.65962 3 + 4431 1451 345 28 2.72030 3 - 4431 1451 346 ------------------------- 4431 1451 347 Levels above 2.73030 MeV are assumed to be continuous. 4431 1451 348 The symbol (*) stands for the excited level involved in the 4431 1451 349 coupled-channel calculation. 4431 1451 350 4431 1451 351 4. Level density parameters 4431 1451 352 Energy-dependent parameters of Mengoni-Nakajima /9/ were used 4431 1451 353 ---------------------------------------------------------- 4431 1451 354 Nuclei a* Pair Esh T E0 Ematch Elv_max 4431 1451 355 1/MeV MeV MeV MeV MeV MeV MeV 4431 1451 356 ---------------------------------------------------------- 4431 1451 357 Ru- 99 13.423 1.206 0.677 0.770 -1.114 7.458 1.414 4431 1451 358 Ru- 98 12.623 2.424 -0.282 0.908 -0.590 10.214 2.720 4431 1451 359 Ru- 97 13.206 1.218 -1.096 0.800 -0.497 6.858 2.020 4431 1451 360 Ru- 96 12.406 2.449 -2.111 1.033 -0.854 11.220 3.380 4431 1451 361 Tc- 98 12.578 0.000 1.601 0.786 -2.453 6.486 0.568 4431 1451 362 Tc- 97 11.986 1.218 0.913 0.934 -2.321 9.757 1.393 4431 1451 363 Tc- 96 12.363 0.000 -0.160 0.891 -2.708 7.312 0.789 4431 1451 364 Mo- 96 13.196 2.449 1.024 0.752 0.274 8.412 3.007 4431 1451 365 Mo- 95 13.125 1.231 0.096 0.761 -0.609 6.814 1.879 4431 1451 366 Mo- 94 12.188 2.475 -0.706 0.937 -0.373 10.175 2.956 4431 1451 367 ---------------------------------------------------------- 4431 1451 368 4431 1451 369 5. Gamma-ray strength functions 4431 1451 370 M1, E2: Standard Lorentzian (SLO) 4431 1451 371 E1 : Modified Lorentzian (MLO) /10/ 4431 1451 372 4431 1451 373 6. Preequilibrium process 4431 1451 374 Preequilibrium is on for n, p, d, t, He-3, and alpha. 4431 1451 375 Preequilibrium capture is on. 4431 1451 376 4431 1451 377 References 4431 1451 378 1) K.Shibata, J. Nucl. Sci. Technol., 50, 1177 (2013). 4431 1451 379 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 4431 1451 380 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4431 1451 381 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 4431 1451 382 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 4431 1451 383 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 4431 1451 384 Phenomena in Nuclear Reactions," p.682, The University 4431 1451 385 of Wisconsin Press (1971). 4431 1451 386 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 4431 1451 387 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 4431 1451 388 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 4431 1451 389 (1994). 4431 1451 390 10) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 4431 1451 391 (2002). 4431 1451 392 4431 1451 393 1 451 419 14431 1451 394 2 151 4 14431 1451 395 3 4 25 14431 1451 396 3 16 7 14431 1451 397 3 17 4 14431 1451 398 3 22 8 14431 1451 399 3 102 121 14431 1451 400 3 103 12 14431 1451 401 3 106 7 14431 1451 402 3 107 14 14431 1451 403 8 4 2 14431 1451 404 8 16 2 14431 1451 405 8 17 2 14431 1451 406 8 22 2 14431 1451 407 8 28 3 14431 1451 408 8 32 3 14431 1451 409 8 102 2 14431 1451 410 8 103 2 14431 1451 411 8 104 3 14431 1451 412 8 105 3 14431 1451 413 8 106 2 14431 1451 414 8 107 2 14431 1451 415 10 28 13 14431 1451 416 10 32 9 14431 1451 417 10 104 17 14431 1451 418 10 105 13 14431 1451 419 4431 1 099999 4431 0 0 0 4.409800+4 9.706423+1 0 0 1 04431 2151 1 4.409800+4 1.000000+0 0 0 1 04431 2151 2 1.400000+2 3.000000+5 0 0 0 04431 2151 3 0.000000+0 6.805000-1 0 0 0 04431 2151 4 4431 2 099999 4431 0 0 0 4.409800+4 9.706423+1 0 0 0 04431 3 4 1 0.000000+0-6.524400+5 0 0 1 644431 3 4 2 64 2 4431 3 4 3 6.591617+5 0.000000+0 6.760000+5 1.449000-1 7.000000+5 2.595000-14431 3 4 4 8.000000+5 5.812000-1 9.000000+5 7.668000-1 1.000000+6 8.885000-14431 3 4 5 1.250000+6 1.071000+0 1.335761+6 1.060709+0 1.412221+6 1.105722+04431 3 4 6 1.428861+6 1.125998+0 1.500000+6 1.351580+0 1.815473+6 1.474879+04431 3 4 7 1.835942+6 1.496113+0 1.973525+6 1.758927+0 2.000000+6 1.830190+04431 3 4 8 2.033436+6 1.816729+0 2.245407+6 1.785504+0 2.264492+6 1.782810+04431 3 4 9 2.269038+6 1.782842+0 2.289851+6 1.791133+0 2.300257+6 1.796822+04431 3 4 10 2.308541+6 1.804647+0 2.389365+6 1.892969+0 2.398963+6 1.905213+04431 3 4 11 2.433819+6 1.956050+0 2.452146+6 1.985332+0 2.455237+6 1.991684+04431 3 4 12 2.460086+6 2.003144+0 2.493022+6 2.092259+0 2.499286+6 2.114587+04431 3 4 13 2.500000+6 2.119585+0 2.573230+6 2.117550+0 2.629110+6 2.116264+04431 3 4 14 2.646790+6 2.118118+0 2.683889+6 2.128348+0 2.687021+6 2.129305+04431 3 4 15 2.748326+6 2.155967+0 2.758429+6 2.161710+0 3.000000+6 2.377074+04431 3 4 16 3.500000+6 2.370272+0 4.000000+6 2.343197+0 4.500000+6 2.308047+04431 3 4 17 5.000000+6 2.277169+0 5.500000+6 2.251493+0 6.000000+6 2.229088+04431 3 4 18 6.500000+6 2.207506+0 7.000000+6 2.186121+0 7.500000+6 2.163218+04431 3 4 19 8.000000+6 2.140767+0 8.500000+6 2.134898+0 9.000000+6 2.097014+04431 3 4 20 9.500000+6 2.090398+0 1.000000+7 2.056674+0 1.100000+7 1.834564+04431 3 4 21 1.200000+7 1.342256+0 1.300000+7 9.756335-1 1.400000+7 7.566534-14431 3 4 22 1.450000+7 6.913430-1 1.500000+7 6.317180-1 1.600000+7 5.540965-14431 3 4 23 1.700000+7 5.008058-1 1.800000+7 4.532521-1 1.900000+7 4.215799-14431 3 4 24 2.000000+7 3.954541-1 4431 3 4 25 4431 3 099999 4.409800+4 9.706423+1 0 0 0 04431 3 16 1 -1.018354+7-1.018354+7 0 0 1 124431 3 16 2 12 2 4431 3 16 3 1.028846+7 0.000000+0 1.100000+7 1.847000-1 1.200000+7 6.419000-14431 3 16 4 1.300000+7 9.710000-1 1.400000+7 1.149000+0 1.450000+7 1.199000+04431 3 16 5 1.500000+7 1.229000+0 1.600000+7 1.261000+0 1.700000+7 1.273000+04431 3 16 6 1.800000+7 1.280000+0 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