JENDL-5 (Neutron sublibrary (activation cs)) Sb-126 0 0 0 0 5.112600+4 1.248256+2 0 0 6 15140 1451 1 0.000000+0 1.000000+0 0 0 0 65140 1451 2 1.000000+0 2.000000+7 0 0 10 55140 1451 3 2.936000+2 0.000000+0 4 0 299 275140 1451 4 51-Sb-126 JAEA EVAL-MAR13 K.Shibata 5140 1451 5 JNST 51, 425 (2014) DIST-DEC21 20180518 5140 1451 6 ----JENDL-5 MATERIAL 5140 5140 1451 7 -----INCIDENT NEUTRON DATA 5140 1451 8 ------ENDF-6 FORMAT 5140 1451 9 5140 1451 10 History 5140 1451 11 13-03 Re-evaluation was performed by K. Shibata (JAEA)./1/ 5140 1451 12 13-06 Thermal capture cross section was revised. 5140 1451 13 18-05 Activation cross sections added by K.Shibata. 5140 1451 14 5140 1451 15 MF= 1 General information 5140 1451 16 MT=451 Descriptive data and directory 5140 1451 17 5140 1451 18 MF= 2 Resonance parameters 5140 1451 19 MT=151 Resolved and unresolved resonance parameters 5140 1451 20 No resolved resonance parameters 5140 1451 21 5140 1451 22 Unresolved resonance region: 30 eV - 300 keV 5140 1451 23 The parameters were obtained by fitting to the evaluated 5140 1451 24 total and capture cross sections. The unresolved resonance 5140 1451 25 parameters obtained should be used only for self-shielding 5140 1451 26 calculation. 5140 1451 27 5140 1451 28 Thermal cross sections and resonance integrals at 300 K 5140 1451 29 ---------------------------------------------------------- 5140 1451 30 0.0253 eV res. integ. (*) 5140 1451 31 (barns) (barns) 5140 1451 32 ---------------------------------------------------------- 5140 1451 33 Total 6.2552E+00 5140 1451 34 Elastic 3.5760E+00 5140 1451 35 n,gamma 2.6740E+00 5.1331E+01 5140 1451 36 ---------------------------------------------------------- 5140 1451 37 (*) Integrated from 0.5 eV to 10 MeV. 5140 1451 38 5140 1451 39 MF= 3 Neutron cross sections 5140 1451 40 MT= 1 Total cross section 5140 1451 41 Calculated with POD code /2/. 5140 1451 42 5140 1451 43 MT= 2 Elastic scattering cross section 5140 1451 44 The cross section was obtained by subtracting the non-elastic 5140 1451 45 cross section from the total cross section. Below 30 eV, the 5140 1451 46 cross section was set to 3.5614 barns. 5140 1451 47 5140 1451 48 MT= 3 Non-elastic cross section 5140 1451 49 Sum of partial non-elastic cross sections. 5140 1451 50 5140 1451 51 MT= 4,51-91 (n,n') cross section 5140 1451 52 Calculated with POD code /2/. 5140 1451 53 5140 1451 54 MT= 16 (n,2n) cross section 5140 1451 55 Calculated with POD code /2/. 5140 1451 56 5140 1451 57 MT= 17 (n,3n) cross section 5140 1451 58 Calculated with POD code /2/. 5140 1451 59 5140 1451 60 MT= 22 (n,na) cross section 5140 1451 61 Calculated with POD code /2/. 5140 1451 62 5140 1451 63 MT= 28 (n,np) cross section 5140 1451 64 Calculated with POD code /2/. 5140 1451 65 5140 1451 66 MT= 32 (n,nd) cross section 5140 1451 67 Calculated with POD code /2/. 5140 1451 68 5140 1451 69 MT=102 Capture cross section 5140 1451 70 Calculated with POD code /2/. Below 30 eV, an 1/v shape 5140 1451 71 was assumed with 2.6728 barns /1/ at 0.0253 eV. 5140 1451 72 5140 1451 73 MT=103 (n,p) cross section 5140 1451 74 Calculated with POD code /2/. 5140 1451 75 5140 1451 76 MT=104 (n,d) cross section 5140 1451 77 Calculated with POD code /2/. 5140 1451 78 5140 1451 79 MT=105 (n,t) cross section 5140 1451 80 Calculated with POD code /2/. 5140 1451 81 5140 1451 82 MT=106 (n,He3) cross section 5140 1451 83 Calculated with POD code /2/. 5140 1451 84 5140 1451 85 MT=107 (n,a) cross section 5140 1451 86 Calculated with POD code /2/. 5140 1451 87 5140 1451 88 MT=203 (n,xp) cross section 5140 1451 89 Calculated with POD code /2/. 5140 1451 90 5140 1451 91 MT=204 (n,xd) cross section 5140 1451 92 Calculated with POD code /2/. 5140 1451 93 5140 1451 94 MT=205 (n,xt) cross section 5140 1451 95 Calculated with POD code /2/. 5140 1451 96 5140 1451 97 MT=206 (n,xHe3) cross section 5140 1451 98 Calculated with POD code /2/. 5140 1451 99 5140 1451 100 MT=207 (n,xa) cross section 5140 1451 101 Calculated with POD code /2/. 5140 1451 102 5140 1451 103 MF= 4 Angular distributions of emitted neutrons 5140 1451 104 MT= 2 Elastic scattering 5140 1451 105 Calculated with POD code /2/. 5140 1451 106 5140 1451 107 MF= 6 Energy-angle distributions of emitted particles 5140 1451 108 MT= 16 (n,2n) reaction 5140 1451 109 Neutron spectra calculated with POD/2/. 5140 1451 110 5140 1451 111 MT= 17 (n,3n) reaction 5140 1451 112 Neutron spectra calculated with POD/2/. 5140 1451 113 5140 1451 114 MT= 22 (n,na) reaction 5140 1451 115 Neutron spectra calculated with POD/2/. 5140 1451 116 5140 1451 117 MT= 28 (n,np) reaction 5140 1451 118 Neutron spectra calculated with POD/2/. 5140 1451 119 5140 1451 120 MT= 32 (n,nd) reaction 5140 1451 121 Neutron spectra calculated with POD/2/. 5140 1451 122 5140 1451 123 MT= 51 (n,n') reaction 5140 1451 124 Neutron angular distributions calculated with POD/2/. 5140 1451 125 5140 1451 126 MT= 52 (n,n') reaction 5140 1451 127 Neutron angular distributions calculated with POD/2/. 5140 1451 128 5140 1451 129 MT= 53 (n,n') reaction 5140 1451 130 Neutron angular distributions calculated with POD/2/. 5140 1451 131 5140 1451 132 MT= 54 (n,n') reaction 5140 1451 133 Neutron angular distributions calculated with POD/2/. 5140 1451 134 5140 1451 135 MT= 55 (n,n') reaction 5140 1451 136 Neutron angular distributions calculated with POD/2/. 5140 1451 137 5140 1451 138 MT= 91 (n,n') reaction 5140 1451 139 Neutron spectra calculated with POD/2/. 5140 1451 140 5140 1451 141 MT= 203 (n,xp) reaction 5140 1451 142 Proton spectra calculated with POD/2/. 5140 1451 143 5140 1451 144 MT= 204 (n,xd) reaction 5140 1451 145 Deuteron spectra calculated with POD/2/. 5140 1451 146 5140 1451 147 MT= 205 (n,xt) reaction 5140 1451 148 Triton spectra calculated with POD/2/. 5140 1451 149 5140 1451 150 MT= 206 (n,xHe3) reaction 5140 1451 151 He3 spectra calculated with POD/2/. 5140 1451 152 5140 1451 153 MT= 207 (n,xa) reaction 5140 1451 154 Alpha spectra calculated with POD/2/. 5140 1451 155 5140 1451 156 MF= 8 Information on decay data 5140 1451 157 MT= 4 (n,n') reaction 5140 1451 158 5140 1451 159 MT= 16 (n,2n) reaction 5140 1451 160 5140 1451 161 MT= 17 (n,3n) reaction 5140 1451 162 5140 1451 163 MT= 22 (n,na) reaction 5140 1451 164 5140 1451 165 MT= 28 (n,np) reaction 5140 1451 166 5140 1451 167 MT= 32 (n,nd) reaction 5140 1451 168 5140 1451 169 MT=102 (n,g) reaction 5140 1451 170 5140 1451 171 MT=103 (n,p) reaction 5140 1451 172 5140 1451 173 MT=104 (n,d) reaction 5140 1451 174 5140 1451 175 MT=105 (n,t) reaction 5140 1451 176 5140 1451 177 MT=106 (n,He3) reaction 5140 1451 178 5140 1451 179 MT=107 (n,a) reaction 5140 1451 180 5140 1451 181 MF=10 Nuclide production cross sections 5140 1451 182 MT= 4 Partial (n,n') reactions 5140 1451 183 Calculated with POD code /2/. 5140 1451 184 5140 1451 185 MT= 17 Partial (n,3n) reactions 5140 1451 186 Calculated with POD code /2/. 5140 1451 187 5140 1451 188 MT= 22 Partial (n,na) reactions 5140 1451 189 Calculated with POD code /2/. 5140 1451 190 5140 1451 191 MT= 28 Partial (n,np) reactions 5140 1451 192 Calculated with POD code /2/. 5140 1451 193 5140 1451 194 MT=104 Partial (n,d) reactions 5140 1451 195 Calculated with POD code /2/. 5140 1451 196 5140 1451 197 MT=106 Partial (n,He3) reactions 5140 1451 198 Calculated with POD code /2/. 5140 1451 199 5140 1451 200 MT=107 Partial (n,a) reactions 5140 1451 201 Calculated with POD code /2/. 5140 1451 202 5140 1451 203 MF=12 Gamma-ray multiplicities 5140 1451 204 MT= 3 Non-elastic gamma emission 5140 1451 205 Calculated with POD code /2/. 5140 1451 206 5140 1451 207 MF=14 Gamma-ray angular distributions 5140 1451 208 MT= 3 Non-elastic gamma emission 5140 1451 209 Assumed to be isotropic. 5140 1451 210 5140 1451 211 MF=15 Gamma-ray spectra 5140 1451 212 MT= 3 Non-elastic gamma emission 5140 1451 213 Calculated with POD code /2/. 5140 1451 214 5140 1451 215 5140 1451 216 5140 1451 217 *************************************************************** 5140 1451 218 * Nuclear Model Calculations with POD Code /2/ * 5140 1451 219 *************************************************************** 5140 1451 220 1. Theoretical models 5140 1451 221 The POD code is based on the spherical optical model, the 5140 1451 222 distorted-wave Born approximaiton (DWBA), one-component exciton 5140 1451 223 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 5140 1451 224 tical model. With the preequilibrim model, semi-empirical 5140 1451 225 pickup and knockout process can be taken into account for 5140 1451 226 composite-particle emission. The gamma-ray emission from the 5140 1451 227 compound nucleus can be calculated within the framework of the 5140 1451 228 exciton model. The code is capable of reading in particle 5140 1451 229 transmission coefficients calculated by separate spherical or 5140 1451 230 coupled-channel optical model code. 5140 1451 231 5140 1451 232 2. Optical model parameters 5140 1451 233 Neutrons: 5140 1451 234 Coupled-channel optical model parameters /3/ 5140 1451 235 Protons: 5140 1451 236 Koning and Delaroche /4/ 5140 1451 237 Deuterons: 5140 1451 238 Lohr and Haeberli /5/ 5140 1451 239 Tritons: 5140 1451 240 Becchetti and Greenlees /6/ 5140 1451 241 He-3: 5140 1451 242 Becchetti and Greenlees /6/ 5140 1451 243 Alphas: 5140 1451 244 Lemos /7/ potentials modified by Arthur and Young /8/ 5140 1451 245 5140 1451 246 3. Level scheme of Sb-126 5140 1451 247 ------------------------- 5140 1451 248 No. Ex(MeV) J PI 5140 1451 249 ------------------------- 5140 1451 250 0 0.00000 8 - 5140 1451 251 1 0.01770 5 + 5140 1451 252 2 0.04040 3 - 5140 1451 253 3 0.08300 2 - 5140 1451 254 4 0.10460 3 + 5140 1451 255 5 0.12790 2 + 5140 1451 256 ------------------------- 5140 1451 257 Levels above 0.13790 MeV are assumed to be continuous. 5140 1451 258 A giant resonance, which was estimated from DWBA, was added to 5140 1451 259 the continuum at Ex = 2.3 MeV. 5140 1451 260 5140 1451 261 4. Level density parameters 5140 1451 262 Energy-dependent parameters of Mengoni-Nakajima /9/ were used 5140 1451 263 ---------------------------------------------------------- 5140 1451 264 Nuclei a* Pair Esh T E0 Ematch Elv_max 5140 1451 265 1/MeV MeV MeV MeV MeV MeV MeV 5140 1451 266 ---------------------------------------------------------- 5140 1451 267 Sb-127 15.073 1.065 -1.601 0.710 -0.225 5.924 2.514 5140 1451 268 Sb-126 15.534 0.000 -0.617 0.741 -2.251 6.198 0.128 5140 1451 269 Sb-125 14.870 1.073 -0.068 0.553 0.610 4.053 2.299 5140 1451 270 Sb-124 14.872 0.000 0.763 0.688 -1.937 5.528 0.643 5140 1451 271 Sn-126 15.615 2.138 -2.600 0.800 0.152 8.327 2.795 5140 1451 272 Sn-125 16.177 1.073 -1.437 0.622 0.148 5.007 0.855 5140 1451 273 Sn-124 15.404 2.155 -0.998 0.704 0.534 7.380 2.879 5140 1451 274 In-124 15.326 0.000 -0.387 0.733 -2.180 6.059 0.243 5140 1451 275 In-123 14.667 1.082 0.204 0.520 0.800 3.642 2.186 5140 1451 276 In-122 15.117 0.000 0.977 0.559 -0.857 3.517 0.229 5140 1451 277 ---------------------------------------------------------- 5140 1451 278 5140 1451 279 5. Gamma-ray strength functions 5140 1451 280 M1, E2: Standard Lorentzian (SLO) 5140 1451 281 E1 : Modified Lorentzian (MLO) /10/ 5140 1451 282 5140 1451 283 6. Preequilibrium process 5140 1451 284 Preequilibrium is on for n, p, d, t, He-3, and alpha. 5140 1451 285 Preequilibrium capture is on. 5140 1451 286 5140 1451 287 References 5140 1451 288 1) K.Shibata, J. Nucl. Sci. Technol. 51, 425 (2014). 5140 1451 289 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5140 1451 290 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5140 1451 291 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5140 1451 292 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 5140 1451 293 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 5140 1451 294 Phenomena in Nuclear Reactions," p.682, The University 5140 1451 295 of Wisconsin Press (1971). 5140 1451 296 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 5140 1451 297 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 5140 1451 298 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 5140 1451 299 (1994). 5140 1451 300 10) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 5140 1451 301 (2002). 5140 1451 302 5140 1451 303 1 451 330 15140 1451 304 2 151 4 15140 1451 305 3 4 21 15140 1451 306 3 16 10 15140 1451 307 3 32 6 15140 1451 308 3 102 124 15140 1451 309 3 103 13 15140 1451 310 3 105 9 15140 1451 311 8 4 2 15140 1451 312 8 16 2 15140 1451 313 8 17 4 15140 1451 314 8 22 3 15140 1451 315 8 28 3 15140 1451 316 8 32 2 15140 1451 317 8 102 2 15140 1451 318 8 103 2 15140 1451 319 8 104 3 15140 1451 320 8 105 2 15140 1451 321 8 106 3 15140 1451 322 8 107 3 15140 1451 323 10 4 38 15140 1451 324 10 17 13 15140 1451 325 10 22 13 15140 1451 326 10 28 15 15140 1451 327 10 104 17 15140 1451 328 10 106 7 15140 1451 329 10 107 21 15140 1451 330 5140 1 099999 5140 0 0 0 5.112600+4 1.248256+2 0 0 1 05140 2151 1 5.112600+4 1.000000+0 0 0 1 05140 2151 2 3.000000+1 3.000000+5 0 0 0 05140 2151 3 8.000000+0 5.323600-1 0 0 0 05140 2151 4 5140 2 099999 5140 0 0 0 5.112600+4 1.248256+2 0 0 0 05140 3 4 1 0.000000+0-1.770000+4 0 0 1 545140 3 4 2 54 2 5140 3 4 3 1.784180+4 0.000000+0 2.000000+4 0.000000+0 3.000000+4 1.088000-45140 3 4 4 4.000000+4 3.887000-4 4.072365+4 4.150340-4 5.000000+4 7.526000-45140 3 4 5 6.000000+4 1.204180-3 7.000000+4 1.752658-3 8.000000+4 2.380386-35140 3 4 6 8.366493+4 2.637406-3 9.000000+4 3.081682-3 1.000000+5 3.908680-35140 3 4 7 1.054380+5 4.754699-3 1.289246+5 8.409267-3 1.390047+5 9.977764-35140 3 4 8 2.000000+5 1.946884-2 3.000000+5 3.757511-2 4.000000+5 5.837293-25140 3 4 9 5.000000+5 7.948994-2 6.000000+5 1.021366-1 7.000000+5 1.220259-15140 3 4 10 8.000000+5 1.539122-1 9.000000+5 1.725879-1 1.000000+6 2.505505-15140 3 4 11 1.250000+6 3.650574-1 1.500000+6 6.440772-1 2.000000+6 1.209687+05140 3 4 12 2.500000+6 1.474057+0 3.000000+6 1.669136+0 3.500000+6 1.868898+05140 3 4 13 4.000000+6 2.038520+0 4.500000+6 2.119831+0 5.000000+6 2.125752+05140 3 4 14 5.500000+6 2.087878+0 6.000000+6 2.032419+0 6.500000+6 1.975713+05140 3 4 15 7.000000+6 1.895591+0 7.500000+6 1.798616+0 8.000000+6 1.703305+05140 3 4 16 8.500000+6 1.599955+0 9.000000+6 1.503870+0 9.500000+6 1.402685+05140 3 4 17 1.000000+7 1.263234+0 1.100000+7 9.772209-1 1.200000+7 7.224231-15140 3 4 18 1.300000+7 5.469865-1 1.400000+7 4.375311-1 1.450000+7 4.026182-15140 3 4 19 1.500000+7 3.705513-1 1.600000+7 3.290278-1 1.700000+7 3.025605-15140 3 4 20 1.800000+7 2.836859-1 1.900000+7 2.689865-1 2.000000+7 2.573406-15140 3 4 21 5140 3 099999 5.112600+4 1.248256+2 0 0 0 05140 3 16 1 -6.214233+6-6.214233+6 0 0 1 205140 3 16 2 20 2 5140 3 16 3 6.264016+6 0.000000+0 6.500000+6 5.330000-3 7.000000+6 4.590000-25140 3 16 4 7.500000+6 1.186000-1 8.000000+6 2.093000-1 8.500000+6 3.197000-15140 3 16 5 9.000000+6 4.282000-1 9.500000+6 5.420000-1 1.000000+7 6.918000-15140 3 16 6 1.100000+7 9.862000-1 1.200000+7 1.237000+0 1.300000+7 1.396000+05140 3 16 7 1.400000+7 1.486000+0 1.450000+7 1.511000+0 1.500000+7 1.536000+05140 3 16 8 1.600000+7 1.558000+0 1.700000+7 1.499000+0 1.800000+7 1.356000+05140 3 16 9 1.900000+7 1.181000+0 2.000000+7 1.002000+0 5140 3 16 10 5140 3 099999 5.112600+4 1.248256+2 0 0 0 05140 3 32 1 -1.129739+7-1.129739+7 0 0 1 95140 3 32 2 9 2 5140 3 32 3 1.138789+7 0.000000+0 1.400000+7 0.000000+0 1.450000+7 1.55900-105140 3 32 4 1.500000+7 3.395000-9 1.600000+7 1.664000-7 1.700000+7 2.192000-65140 3 32 5 1.800000+7 1.421000-5 1.900000+7 6.052000-5 2.000000+7 1.940000-45140 3 32 6 5140 3 099999 5.112600+4 1.248256+2 0 0 0 05140 3102 1 8.373001+6 8.373001+6 0 0 1 3635140 3102 2 363 2 5140 3102 3 1.000000-5 1.344405+2 1.103037-5 1.280074+2 1.216691-5 1.218821+25140 3102 4 1.342055-5 1.160500+2 1.480336-5 1.104969+2 1.632865-5 1.052095+25140 3102 5 1.801111-5 1.001751+2 1.986691-5 9.538166+1 2.191394-5 9.081756+15140 3102 6 2.417189-5 8.647186+1 2.666248-5 8.233411+1 2.940971-5 7.839435+15140 3102 7 3.243999-5 7.464311+1 3.578251-5 7.107137+1 3.946943-5 6.767054+15140 3102 8 4.353624-5 6.443245+1 4.802208-5 6.134930+1 5.297013-5 5.841368+15140 3102 9 5.842801-5 5.561853+1 6.444825-5 5.295714+1 7.108881-5 5.042309+15140 3102 10 7.841358-5 4.801030+1 8.649308-5 4.571297+1 9.540506-5 4.352556+15140 3102 11 1.052353-4 4.144283+1 1.160784-4 3.945975+1 1.280388-4 3.757157+15140 3102 12 1.412315-4 3.577373+1 1.557836-4 3.406193+1 1.718351-4 3.243204+15140 3102 13 1.895404-4 3.088013+1 2.090701-4 2.940249+1 2.306120-4 2.799556+15140 3102 14 2.543736-4 2.665595+1 2.805835-4 2.538043+1 3.094939-4 2.416596+15140 3102 15 3.413832-4 2.300960+1 3.765583-4 2.190857+1 4.153577-4 2.086022+15140 3102 16 4.581549-4 1.986204+1 5.053618-4 1.891163+1 5.574328-4 1.800669+15140 3102 17 6.148689-4 1.714505+1 6.782232-4 1.632465+1 7.481052-4 1.554350+15140 3102 18 8.251877-4 1.479973+1 9.102125-4 1.409155+1 1.003998-3 1.341725+15140 3102 19 1.107447-3 1.277523+1 1.221555-3 1.216392+1 1.347420-3 1.158187+15140 3102 20 1.486254-3 1.102766+1 1.639393-3 1.049998+1 1.808311-3 9.997546+05140 3102 21 1.994634-3 9.519154+0 2.200155-3 9.063654+0 2.426853-3 8.629951+05140 3102 22 2.676908-3 8.217000+0 2.952729-3 7.823811+0 3.256969-3 7.449436+05140 3102 23 3.592557-3 7.092978+0 3.962723-3 6.753582+0 4.371030-3 6.430436+05140 3102 24 4.821407-3 6.122771+0 5.318191-3 5.829862+0 5.866161-3 5.551021+05140 3102 25 6.470592-3 5.285593+0 7.137302-3 5.032940+0 7.872708-3 4.792426+05140 3102 26 8.683888-3 4.563415+0 9.578649-3 4.345293+0 1.056560-2 4.137512+05140 3102 27 1.165425-2 3.939600+0 1.285507-2 3.751126+0 1.417962-2 3.571665+05140 3102 28 1.564064-2 3.400753+0 1.725221-2 3.238014+0 1.902982-2 3.083083+05140 3102 29 2.099059-2 2.935594+0 2.315340-2 2.795158+0 2.524188-2 2.677002+05140 3102 30 2.530000-2 2.673924+0 2.790683-2 2.545882+0 3.078227-2 2.424027+05140 3102 31 3.395398-2 2.308111+0 3.745250-2 2.197670+0 4.131149-2 2.092462+05140 3102 32 4.556810-2 1.992393+0 5.026329-2 1.897089+0 5.544227-2 1.806223+05140 3102 33 6.115487-2 1.719729+0 6.745608-2 1.637604+0 7.493143-2 1.553755+05140 3102 34 8.265213-2 1.479303+0 9.116835-2 1.408620+0 1.005621-1 1.341241+05140 3102 35 1.109237-1 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