JENDL-5 (Neutron sublibrary (activation cs)) Xe-133 0 0 0 0 5.413300+4 1.317642+2 0 0 6 15452 1451 1 0.000000+0 1.000000+0 0 0 0 65452 1451 2 1.000000+0 2.000000+7 0 0 10 55452 1451 3 2.936000+2 0.000000+0 4 0 245 275452 1451 4 54-Xe-133 JAEA EVAL-FEB22 S.Kunieda, A.Ichihara, K.Shibata+5452 1451 5 DIST-DEC21 20100316 5452 1451 6 ----JENDL-5 MATERIAL 5452 5452 1451 7 -----INCIDENT NEUTRON DATA 5452 1451 8 ------ENDF-6 FORMAT 5452 1451 9 5452 1451 10 History 5452 1451 11 09-11 Re-evaluation was performed for JENDL-4.0 5452 1451 12 10-03 Compiled by S.Kunieda 5452 1451 13 21-11 revised by O.Iwamoto 5452 1451 14 (MF8/MT4,16,17,22,28,32,41,102-104,107) 5452 1451 15 JENDL/AD-2017 adopted 5452 1451 16 (MF8/MT105,106) added 5452 1451 17 (MF10/MT4,17,22,28,104) JENDL/AD-2017 based 5452 1451 18 5452 1451 19 MF= 1 General information 5452 1451 20 5452 1451 21 MT=451 Descriptive data and directory 5452 1451 22 5452 1451 23 5452 1451 24 MF= 2 Resonance parameters 5452 1451 25 5452 1451 26 MT=151 Resolved and unresolved resonance parameters 5452 1451 27 5452 1451 28 - No resolved resonance parameters are given. 5452 1451 29 Below 80.5 eV, the capture and elastic scattering cross 5452 1451 30 sections were assumed to be in 1/v form and constant, 5452 1451 31 respectively. The capture cross section at 0.0253 eV was 5452 1451 32 taken from Ref./1/, and the scattering cross section was 5452 1451 33 estimated from r = 5.4 fm. Those data are given in MF=3. 5452 1451 34 5452 1451 35 - Unresolved resonance region: 80.5 eV - 250 keV 5452 1451 36 The parameters were obtained by fitting to the total and 5452 1451 37 capture cross sections calculated by the POD code /2/. 5452 1451 38 The ASREP code /3/ was employed in this evaluation. 5452 1451 39 The unresolved parameters should be used only for 5452 1451 40 self-shielding calculation. 5452 1451 41 5452 1451 42 Thermal cross sections & resonance integrals at 300 K 5452 1451 43 ---------------------------------------------------------- 5452 1451 44 0.0253 eV res. integ. (*) 5452 1451 45 (barns) (barns) 5452 1451 46 ---------------------------------------------------------- 5452 1451 47 Total 1.94262E+02 5452 1451 48 Elastic 3.61460E+00 5452 1451 49 n,gamma 1.90083E+02 8.90633E+01 5452 1451 50 ---------------------------------------------------------- 5452 1451 51 (*) Integrated from 0.5 eV to 10 MeV. 5452 1451 52 5452 1451 53 5452 1451 54 MF= 3 Neutron cross sections 5452 1451 55 5452 1451 56 MT= 1 Total cross section 5452 1451 57 Sum of partial cross sections. 5452 1451 58 5452 1451 59 MT= 2 Elastic scattering cross section 5452 1451 60 The OPTMAN /4/ & POD /2/ calculations. 5452 1451 61 5452 1451 62 MT= 3 Non-elastic cross section 5452 1451 63 Sum of partial non-elastic cross sections. 5452 1451 64 5452 1451 65 MT= 4,51-91 (n,n') cross section 5452 1451 66 The OPTMAN /4/ & POD /2/ calculations. 5452 1451 67 5452 1451 68 MT= 16 (n,2n) cross section 5452 1451 69 MT= 17 (n,3n) cross section 5452 1451 70 MT= 22 (n,na) cross section 5452 1451 71 MT= 28 (n,np) cross section 5452 1451 72 MT= 32 (n,nd) cross section 5452 1451 73 MT=102 Capture cross section 5452 1451 74 MT=103 (n,p) cross section 5452 1451 75 MT=104 (n,d) cross section 5452 1451 76 MT=105 (n,t) cross section 5452 1451 77 MT=106 (n,He3) cross section 5452 1451 78 MT=107 (n,a) cross section 5452 1451 79 Calculated by the POD code /2/. 5452 1451 80 5452 1451 81 MT=203 (n,xp) cross section 5452 1451 82 Sum of (n,np) and (n,p) 5452 1451 83 5452 1451 84 MT=204 (n,xd) cross section 5452 1451 85 Sum of (n,nd) and (n,d) 5452 1451 86 5452 1451 87 MT=205 (n,xt) cross section 5452 1451 88 MT=206 (n,xHe3) cross section 5452 1451 89 Calculated by the POD code /2/. 5452 1451 90 5452 1451 91 MT=207 (n,xa) cross section 5452 1451 92 Sum of (n,na) and (n,a) 5452 1451 93 5452 1451 94 5452 1451 95 MF= 4 Angular distributions of emitted neutrons 5452 1451 96 5452 1451 97 MT= 2 Elastic scattering 5452 1451 98 The OPTMAN /4/ & POD /2/ calculations. 5452 1451 99 5452 1451 100 5452 1451 101 MF= 6 Energy-angle distributions of emitted particles 5452 1451 102 5452 1451 103 MT= 16 (n,2n) reaction 5452 1451 104 MT= 17 (n,3n) reaction 5452 1451 105 MT= 22 (n,na) reaction 5452 1451 106 MT= 28 (n,np) reaction 5452 1451 107 MT= 32 (n,nd) reaction 5452 1451 108 Neutron spectra calculated by the POD code /2/. 5452 1451 109 5452 1451 110 MT= 51-90 (n,n') reaction 5452 1451 111 Neutron angular distributions calculated by 5452 1451 112 OPTMAN /4/ & POD /2/. 5452 1451 113 5452 1451 114 MT= 91 (n,n') reaction 5452 1451 115 Neutron spectra calculated by the POD code /2/. 5452 1451 116 5452 1451 117 MT= 203 (n,xp) reaction 5452 1451 118 MT= 204 (n,xd) reaction 5452 1451 119 MT= 205 (n,xt) reaction 5452 1451 120 MT= 206 (n,xHe3) reaction 5452 1451 121 MT= 207 (n,xa) reaction 5452 1451 122 Light-ion spectra calculated by the POD code /6/. 5452 1451 123 5452 1451 124 5452 1451 125 MF=12 Gamma-ray multiplicities 5452 1451 126 5452 1451 127 MT= 3 Non-elastic gamma emission 5452 1451 128 Calculated by the POD code /2/. 5452 1451 129 5452 1451 130 5452 1451 131 MF=14 Gamma-ray angular distributions 5452 1451 132 5452 1451 133 MT= 3 Non-elastic gamma emission 5452 1451 134 Assumed to be isotropic. 5452 1451 135 5452 1451 136 5452 1451 137 MF=15 Gamma-ray spectra 5452 1451 138 5452 1451 139 MT= 3 Non-elastic gamma emission 5452 1451 140 Calculated by the POD code /2/. 5452 1451 141 5452 1451 142 5452 1451 143 5452 1451 144 5452 1451 145 *************************************************************** 5452 1451 146 * Nuclear Model Calculations with POD Code /2/ * 5452 1451 147 *************************************************************** 5452 1451 148 1. Theoretical models 5452 1451 149 The POD code is based on the spherical optical model, the 5452 1451 150 distorted-wave Born approximaiton (DWBA), one-component exciton 5452 1451 151 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 5452 1451 152 tical model. With the preequilibrium model, semi-empirical 5452 1451 153 pickup and knockout process can be taken into account for 5452 1451 154 composite-particle emission. The gamma-ray emission from the 5452 1451 155 compound nucleus can be calculated within the framework of the 5452 1451 156 exciton model. The code is capable of reading in particle 5452 1451 157 transmission coefficients calculated by separate spherical or 5452 1451 158 coupled-channel optical model code. In this evaluation, the OPTMAN5452 1451 159 code /4/ was employed for neutrons, while the ECIS code 5452 1451 160 /5/ was adopted for charged particles. 5452 1451 161 5452 1451 162 2. Optical model & parameters 5452 1451 163 Neutrons: 5452 1451 164 Model: The coupled-channel method based on the rigid-rotor 5452 1451 165 model was adopted. Deformation parameter beta2 was 5452 1451 166 taken from ref./6/ 5452 1451 167 OMP : Coupled-channel optical potential /7/ was applied. 5452 1451 168 Protons: 5452 1451 169 Model: Spherical 5452 1451 170 OMP : Koning and Delaroche /8/ 5452 1451 171 Deuterons: 5452 1451 172 Model: Spherical 5452 1451 173 OMP : Bojowald et al. /9/ 5452 1451 174 Tritons: 5452 1451 175 Mode: Spherical 5452 1451 176 OMP : Becchetti and Greenlees /10/ 5452 1451 177 He-3: 5452 1451 178 Model: Spherical 5452 1451 179 OMP : Becchetti and Greenlees /10/ 5452 1451 180 Alphas: 5452 1451 181 Model: Spherical 5452 1451 182 OMP : A simplified folding model potential /11/ 5452 1451 183 (The nucleon OMP was taken from Ref./7/.) 5452 1451 184 5452 1451 185 3. Level scheme of Xe-133 5452 1451 186 ------------------------------------ 5452 1451 187 No. Ex(MeV) J PI CC 5452 1451 188 ------------------------------------ 5452 1451 189 0 0.00000 3/2 + * 5452 1451 190 1 0.23322 11/2 - 5452 1451 191 2 0.26270 1/2 + 5452 1451 192 3 0.52987 5/2 + * 5452 1451 193 4 0.60787 5/2 + 5452 1451 194 5 0.68026 3/2 + 5452 1451 195 6 0.74375 7/2 - 5452 1451 196 7 0.87533 7/2 + 5452 1451 197 8 0.91145 1/2 + 5452 1451 198 ------------------------------------ 5452 1451 199 Levels above 0.92145 MeV are assumed to be continuous. 5452 1451 200 5452 1451 201 5452 1451 202 4. Level density parameters 5452 1451 203 Energy-dependent parameters of Mengoni-Nakajima /12/ were used 5452 1451 204 ---------------------------------------------------------- 5452 1451 205 Nuclei a* Pair Esh T E0 Ematch Elv_max 5452 1451 206 1/MeV MeV MeV MeV MeV MeV MeV 5452 1451 207 ---------------------------------------------------------- 5452 1451 208 Xe-134 16.449 2.073 -2.814 0.742 0.503 7.492 2.409 5452 1451 209 Xe-133 16.992 1.041 -1.762 0.696 -0.731 6.456 0.911 5452 1451 210 Xe-132 16.240 2.089 -1.146 0.723 0.006 8.026 2.425 5452 1451 211 Xe-131 16.786 1.048 -0.172 0.686 -1.237 7.025 0.700 5452 1451 212 I -133 15.660 1.041 -3.586 0.875 -1.279 8.089 2.025 5452 1451 213 I -132 16.152 0.000 -2.493 0.768 -1.905 5.957 0.162 5452 1451 214 I -131 15.458 1.048 -1.637 0.769 -1.003 7.186 1.623 5452 1451 215 Te-131 22.166 1.048 -3.417 0.613 -0.582 5.846 1.043 5452 1451 216 Te-130 16.030 2.105 -2.605 0.776 0.213 8.078 1.815 5452 1451 217 Te-129 20.892 1.057 -1.456 0.590 -0.837 6.047 0.360 5452 1451 218 ---------------------------------------------------------- 5452 1451 219 5452 1451 220 5. Gamma-ray strength functions 5452 1451 221 M1, E2: Standard Lorentzian (SLO) 5452 1451 222 E1 : Generalized Lorentzian (GLO) /13/ 5452 1451 223 5452 1451 224 6. Preequilibrium process 5452 1451 225 Preequilibrium is on for n, p, d, t, He-3, and alpha. 5452 1451 226 Preequilibrium capture is on. 5452 1451 227 5452 1451 228 5452 1451 229 References 5452 1451 230 1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, 5452 1451 231 Part A", Academic Press (1981). 5452 1451 232 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5452 1451 233 3) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) 5452 1451 234 [in Japanese]. 5452 1451 235 4) E.Soukhovitski et al., JAERI-Data/Code 2005-002 (2005). 5452 1451 236 5) J.Raynal, CEA Saclay report, CEA-N-2772 (1994). 5452 1451 237 6) S.Raman et al., At. Data and Nucl. Data Tables 78, 1 (1995) 5452 1451 238 7) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5452 1451 239 8) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5452 1451 240 9) Bojowald et al., Phys. Rev. C 38, 1153 (1988). 5452 1451 241 10) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 5452 1451 242 Phenomena in Nuclear Reactions," p.682, The University 5452 1451 243 of Wisconsin Press (1971). 5452 1451 244 11) D.G.Madland, NEANDC-245 (1988), p. 103. 5452 1451 245 12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 5452 1451 246 (1994). 5452 1451 247 13) M.Brink, Ph.D thesis, Oxford University, 1955. 5452 1451 248 5452 1451 249 1 451 276 15452 1451 250 2 151 4 15452 1451 251 3 4 24 15452 1451 252 3 16 10 15452 1451 253 3 32 6 15452 1451 254 3 102 152 15452 1451 255 3 103 17 15452 1451 256 3 105 9 15452 1451 257 3 106 8 15452 1451 258 3 107 21 15452 1451 259 8 4 2 15452 1451 260 8 16 2 15452 1451 261 8 17 3 15452 1451 262 8 22 3 15452 1451 263 8 28 3 15452 1451 264 8 32 2 15452 1451 265 8 102 2 15452 1451 266 8 103 2 15452 1451 267 8 104 3 15452 1451 268 8 105 2 15452 1451 269 8 106 2 15452 1451 270 8 107 2 15452 1451 271 10 4 24 15452 1451 272 10 17 9 15452 1451 273 10 22 25 15452 1451 274 10 28 15 15452 1451 275 10 104 17 15452 1451 276 5452 1 099999 5452 0 0 0 5.413300+4 1.317642+2 0 0 1 05452 2151 1 5.413300+4 1.000000+0 0 0 1 05452 2151 2 8.050000+1 2.500000+5 0 0 0 05452 2151 3 1.500000+0 4.732300-1 0 0 0 05452 2151 4 5452 2 099999 5452 0 0 0 5.413300+4 1.317642+2 0 0 0 05452 3 4 1 0.000000+0-2.332210+5 0 0 1 635452 3 4 2 63 2 5452 3 4 3 2.349910+5 0.000000+0 2.500000+5 4.281000-3 2.646937+5 7.275282-35452 3 4 4 3.000000+5 1.070200-1 3.500000+5 1.744400-1 4.000000+5 2.179600-15452 3 4 5 4.500000+5 2.500900-1 5.000000+5 2.765800-1 5.338903+5 2.870792-15452 3 4 6 5.500000+5 3.814200-1 6.000000+5 4.896100-1 6.124833+5 4.993719-15452 3 4 7 6.500000+5 6.295100-1 6.854197+5 6.810102-1 7.000000+5 7.456600-15452 3 4 8 7.493966+5 8.353840-1 7.500000+5 8.420350-1 8.000000+5 9.341500-15452 3 4 9 8.500000+5 1.000850+0 8.819732+5 1.022969+0 9.000000+5 1.067410+05452 3 4 10 9.183673+5 1.161285+0 9.284432+5 1.219733+0 9.500000+5 1.344820+05452 3 4 11 1.000000+6 1.389771+0 1.200000+6 1.551785+0 1.400000+6 1.681723+05452 3 4 12 1.600000+6 1.783497+0 1.800000+6 1.860245+0 2.000000+6 1.919964+05452 3 4 13 2.200000+6 1.971033+0 2.400000+6 2.020782+0 2.600000+6 2.073112+05452 3 4 14 2.800000+6 2.128651+0 3.000000+6 2.185691+0 3.250000+6 2.253570+05452 3 4 15 3.500000+6 2.311230+0 3.750000+6 2.355980+0 4.000000+6 2.384905+05452 3 4 16 4.250000+6 2.397988+0 4.500000+6 2.397099+0 4.750000+6 2.383209+05452 3 4 17 5.000000+6 2.360548+0 5.500000+6 2.299998+0 6.000000+6 2.237955+05452 3 4 18 6.500000+6 2.189037+0 7.000000+6 2.085920+0 7.500000+6 1.903187+05452 3 4 19 8.000000+6 1.652662+0 8.500000+6 1.380682+0 9.000000+6 1.104850+05452 3 4 20 9.500000+6 8.579743-1 1.000000+7 6.608148-1 1.100000+7 4.055572-15452 3 4 21 1.200000+7 2.732771-1 1.300000+7 2.048130-1 1.400000+7 1.695837-15452 3 4 22 1.500000+7 1.502262-1 1.600000+7 1.383470-1 1.700000+7 1.296651-15452 3 4 23 1.800000+7 1.223957-1 1.900000+7 1.158172-1 2.000000+7 1.096289-15452 3 4 24 5452 3 099999 5.413300+4 1.317642+2 0 0 0 05452 3 16 1 -6.434435+6-6.434435+6 0 0 1 195452 3 16 2 19 2 5452 3 16 3 6.483268+6 0.000000+0 6.500000+6 0.000000+0 7.000000+6 7.046000-25452 3 16 4 7.500000+6 2.367000-1 8.000000+6 4.819000-1 8.500000+6 7.541000-15452 3 16 5 9.000000+6 1.032000+0 9.500000+6 1.278000+0 1.000000+7 1.472000+05452 3 16 6 1.100000+7 1.712000+0 1.200000+7 1.822000+0 1.300000+7 1.865000+05452 3 16 7 1.400000+7 1.878000+0 1.500000+7 1.879000+0 1.600000+7 1.874000+05452 3 16 8 1.700000+7 1.788000+0 1.800000+7 1.549000+0 1.900000+7 1.244000+05452 3 16 9 2.000000+7 9.566000-1 5452 3 16 10 5452 3 099999 5.413300+4 1.317642+2 0 0 0 05452 3 32 1 -1.333496+7-1.333496+7 0 0 1 85452 3 32 2 8 2 5452 3 32 3 1.343616+7 0.000000+0 1.400000+7 1.31500-26 1.500000+7 1.34800-165452 3 32 4 1.600000+7 6.43200-11 1.700000+7 3.174000-8 1.800000+7 1.384000-65452 3 32 5 1.900000+7 1.749000-5 2.000000+7 1.013000-4 5452 3 32 6 5452 3 099999 5.413300+4 1.317642+2 0 0 0 05452 3102 1 8.552208+6 8.552208+6 0 0 1 4475452 3102 2 447 2 5452 3102 3 1.000000-5 9.557008+3 1.103037-5 9.099697+3 1.216691-5 8.664268+35452 3102 4 1.342055-5 8.249675+3 1.480336-5 7.854921+3 1.632865-5 7.479056+35452 3102 5 1.801111-5 7.121176+3 1.986691-5 6.780422+3 2.191394-5 6.455972+35452 3102 6 2.417189-5 6.147048+3 2.666248-5 5.852907+3 2.940971-5 5.572840+35452 3102 7 3.243999-5 5.306174+3 3.578251-5 5.052269+3 3.946943-5 4.810514+35452 3102 8 4.353624-5 4.580326+3 4.802208-5 4.361153+3 5.297013-5 4.152468+35452 3102 9 5.842801-5 3.953769+3 6.444825-5 3.764577+3 7.108881-5 3.584439+35452 3102 10 7.841358-5 3.412920+3 8.649308-5 3.249609+3 9.540506-5 3.094112+35452 3102 11 1.052353-4 2.946056+3 1.160784-4 2.805084+3 1.280388-4 2.670858+35452 3102 12 1.412315-4 2.543055+3 1.557836-4 2.421368+3 1.718351-4 2.305503+35452 3102 13 1.895404-4 2.195182+3 2.090701-4 2.090141+3 2.306120-4 1.990125+35452 3102 14 2.543736-4 1.894896+3 2.805835-4 1.804223+3 3.094939-4 1.717889+35452 3102 15 3.413832-4 1.635687+3 3.765583-4 1.557417+3 4.153577-4 1.482893+35452 3102 16 4.581549-4 1.411935+3 5.053618-4 1.344373+3 5.574328-4 1.280043+35452 3102 17 6.148689-4 1.218792+3 6.782232-4 1.160471+3 7.481052-4 1.104942+35452 3102 18 8.251877-4 1.052069+3 9.102125-4 1.001726+3 1.003998-3 9.537926+25452 3102 19 1.107447-3 9.081526+2 1.221555-3 8.646965+2 1.347420-3 8.233199+25452 3102 20 1.486254-3 7.839231+2 1.639393-3 7.464115+2 1.808311-3 7.106950+25452 3102 21 1.994634-3 6.766874+2 2.200155-3 6.443072+2 2.426853-3 6.134764+25452 3102 22 2.676908-3 5.841209+2 2.952729-3 5.561702+2 3.256969-3 5.295570+25452 3102 23 3.592557-3 5.042175+2 3.962723-3 4.800911+2 4.371030-3 4.571202+25452 3102 24 4.821407-3 4.352503+2 5.318191-3 4.144299+2 5.866161-3 3.946100+25452 3102 25 6.470592-3 3.757437+2 7.137302-3 3.577849+2 7.872708-3 3.406877+25452 3102 26 8.683888-3 3.244065+2 9.578649-3 3.088984+2 1.056560-2 2.941250+25452 3102 27 1.165425-2 2.800538+2 1.285507-2 2.666558+2 1.417962-2 2.538975+25452 3102 28 1.564064-2 2.417478+2 1.725221-2 2.301777+2 1.902982-2 2.191611+25452 3102 29 2.099059-2 2.086728+2 2.315340-2 1.986889+2 2.524188-2 1.902927+25452 3102 30 2.530000-2 1.900740+2 2.790683-2 1.809762+2 3.078227-2 1.723158+25452 3102 31 3.395398-2 1.640773+2 3.745250-2 1.562268+2 4.131149-2 1.487463+25452 3102 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