JENDL-5 (Neutron sublibrary (activation cs)) Xe-135 0 0 0 0 5.413500+4 1.337483+2 0 0 6 15458 1451 1 0.000000+0 1.000000+0 0 0 0 65458 1451 2 1.000000+0 2.000000+7 0 0 10 55458 1451 3 2.936000+2 0.000000+0 4 0 250 275458 1451 4 54-Xe-135 JAEA EVAL-FEB22 S.Kunieda, A.Ichihara, K.Shibata+5458 1451 5 DIST-DEC21 20100316 5458 1451 6 ----JENDL-5 MATERIAL 5458 5458 1451 7 -----INCIDENT NEUTRON DATA 5458 1451 8 ------ENDF-6 FORMAT 5458 1451 9 5458 1451 10 History 5458 1451 11 09-11 Re-evaluation was performed for JENDL-4.0 5458 1451 12 10-03 Compiled by S.Kunieda 5458 1451 13 21-11 revised by O.Iwamoto 5458 1451 14 (MF8/MT4,16,17,22,28,32,102-104,107) JENDL/AD-2017 adopted 5458 1451 15 (MF8/MT105,106) added 5458 1451 16 (MF10/MT4,17,22) JENDL/AD-2017 based 5458 1451 17 5458 1451 18 MF= 1 General information 5458 1451 19 5458 1451 20 MT=451 Descriptive data and directory 5458 1451 21 5458 1451 22 5458 1451 23 MF= 2 Resonance parameters 5458 1451 24 5458 1451 25 MT=151 Resolved and unresolved resonance parameters 5458 1451 26 5458 1451 27 - Resolved resonance region (MLBW formula): below 190 eV 5458 1451 28 Resonance parameters of JENDL-3.3 were replaced by the 5458 1451 29 original data by Smith et al./1/. The resonance energy 5458 1451 30 and total spin j were estimated to be 0.08415 eV and 2, 5458 1451 31 respectively. The neutron and radiation widths were slightly5458 1451 32 modified so as to reproduce the thermal capture cross 5458 1451 33 section of 2.76 mega-barns measured by Smith et al. 5458 1451 34 5458 1451 35 - Unresolved resonance region: 190 eV - 200 keV 5458 1451 36 The parameters were obtained by fitting to the total and 5458 1451 37 capture cross sections calculated by the POD code /2/. 5458 1451 38 The ASREP code /3/ was employed in this evaluation. 5458 1451 39 The unresolved parameters should be used only for 5458 1451 40 self-shielding calculation. 5458 1451 41 5458 1451 42 Thermal cross sections & resonance integrals at 300 K 5458 1451 43 ---------------------------------------------------------- 5458 1451 44 0.0253 eV res. integ. (*) 5458 1451 45 (barns) (barns) 5458 1451 46 ---------------------------------------------------------- 5458 1451 47 Total 3.11026E+06 5458 1451 48 Elastic 3.32250E+05 5458 1451 49 n,gamma 2.77801E+06 7.91423E+03 5458 1451 50 ---------------------------------------------------------- 5458 1451 51 (*) Integrated from 0.5 eV to 10 MeV. 5458 1451 52 5458 1451 53 5458 1451 54 MF= 3 Neutron cross sections 5458 1451 55 5458 1451 56 MT= 1 Total cross section 5458 1451 57 Sum of partial cross sections. 5458 1451 58 5458 1451 59 MT= 2 Elastic scattering cross section 5458 1451 60 The OPTMAN /4/ & POD /2/ calculations. 5458 1451 61 5458 1451 62 MT= 3 Non-elastic cross section 5458 1451 63 Sum of partial non-elastic cross sections. 5458 1451 64 5458 1451 65 MT= 4,51-91 (n,n') cross section 5458 1451 66 The OPTMAN /4/ & POD /2/ calculations. 5458 1451 67 5458 1451 68 MT= 16 (n,2n) cross section 5458 1451 69 MT= 17 (n,3n) cross section 5458 1451 70 MT= 22 (n,na) cross section 5458 1451 71 MT= 28 (n,np) cross section 5458 1451 72 MT= 32 (n,nd) cross section 5458 1451 73 MT=102 Capture cross section 5458 1451 74 MT=103 (n,p) cross section 5458 1451 75 MT=104 (n,d) cross section 5458 1451 76 MT=105 (n,t) cross section 5458 1451 77 MT=106 (n,He3) cross section 5458 1451 78 MT=107 (n,a) cross section 5458 1451 79 Calculated by the POD code /2/. 5458 1451 80 5458 1451 81 MT=203 (n,xp) cross section 5458 1451 82 Sum of (n,np) and (n,p) 5458 1451 83 5458 1451 84 MT=204 (n,xd) cross section 5458 1451 85 Sum of (n,nd) and (n,d) 5458 1451 86 5458 1451 87 MT=205 (n,xt) cross section 5458 1451 88 MT=206 (n,xHe3) cross section 5458 1451 89 Calculated by the POD code /2/. 5458 1451 90 5458 1451 91 MT=207 (n,xa) cross section 5458 1451 92 Sum of (n,na) and (n,a) 5458 1451 93 5458 1451 94 5458 1451 95 MF= 4 Angular distributions of emitted neutrons 5458 1451 96 5458 1451 97 MT= 2 Elastic scattering 5458 1451 98 The OPTMAN /4/ & POD /2/ calculations. 5458 1451 99 5458 1451 100 5458 1451 101 MF= 6 Energy-angle distributions of emitted particles 5458 1451 102 5458 1451 103 MT= 16 (n,2n) reaction 5458 1451 104 MT= 17 (n,3n) reaction 5458 1451 105 MT= 22 (n,na) reaction 5458 1451 106 MT= 28 (n,np) reaction 5458 1451 107 MT= 32 (n,nd) reaction 5458 1451 108 Neutron spectra calculated by the POD code /2/. 5458 1451 109 5458 1451 110 MT= 51-90 (n,n') reaction 5458 1451 111 Neutron angular distributions calculated by 5458 1451 112 OPTMAN /4/ & POD /2/. 5458 1451 113 5458 1451 114 MT= 91 (n,n') reaction 5458 1451 115 Neutron spectra calculated by the POD code /2/. 5458 1451 116 5458 1451 117 MT= 203 (n,xp) reaction 5458 1451 118 MT= 204 (n,xd) reaction 5458 1451 119 MT= 205 (n,xt) reaction 5458 1451 120 MT= 206 (n,xHe3) reaction 5458 1451 121 MT= 207 (n,xa) reaction 5458 1451 122 Light-ion spectra calculated by the POD code /6/. 5458 1451 123 5458 1451 124 5458 1451 125 MF=12 Gamma-ray multiplicities 5458 1451 126 5458 1451 127 MT= 3 Non-elastic gamma emission 5458 1451 128 Calculated by the POD code /2/. 5458 1451 129 5458 1451 130 5458 1451 131 MF=14 Gamma-ray angular distributions 5458 1451 132 5458 1451 133 MT= 3 Non-elastic gamma emission 5458 1451 134 Assumed to be isotropic. 5458 1451 135 5458 1451 136 5458 1451 137 MF=15 Gamma-ray spectra 5458 1451 138 5458 1451 139 MT= 3 Non-elastic gamma emission 5458 1451 140 Calculated by the POD code /2/. 5458 1451 141 5458 1451 142 5458 1451 143 5458 1451 144 5458 1451 145 *************************************************************** 5458 1451 146 * Nuclear Model Calculations with POD Code /2/ * 5458 1451 147 *************************************************************** 5458 1451 148 1. Theoretical models 5458 1451 149 The POD code is based on the spherical optical model, the 5458 1451 150 distorted-wave Born approximaiton (DWBA), one-component exciton 5458 1451 151 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 5458 1451 152 tical model. With the preequilibrium model, semi-empirical 5458 1451 153 pickup and knockout process can be taken into account for 5458 1451 154 composite-particle emission. The gamma-ray emission from the 5458 1451 155 compound nucleus can be calculated within the framework of the 5458 1451 156 exciton model. The code is capable of reading in particle 5458 1451 157 transmission coefficients calculated by separate spherical or 5458 1451 158 coupled-channel optical model code. In this evaluation, the OPTMAN5458 1451 159 code /4/ was employed for neutrons, while the ECIS code 5458 1451 160 /5/ was adopted for charged particles. 5458 1451 161 5458 1451 162 2. Optical model & parameters 5458 1451 163 Neutrons: 5458 1451 164 Model: The coupled-channel method based on the rigid-rotor 5458 1451 165 model was adopted. Deformation parameter beta2 was 5458 1451 166 taken from ref./6/ 5458 1451 167 OMP : Coupled-channel optical potential /7/ was applied. 5458 1451 168 Protons: 5458 1451 169 Model: Spherical 5458 1451 170 OMP : Koning and Delaroche /8/ 5458 1451 171 Deuterons: 5458 1451 172 Model: Spherical 5458 1451 173 OMP : Bojowald et al. /9/ 5458 1451 174 Tritons: 5458 1451 175 Mode: Spherical 5458 1451 176 OMP : Becchetti and Greenlees /10/ 5458 1451 177 He-3: 5458 1451 178 Model: Spherical 5458 1451 179 OMP : Becchetti and Greenlees /10/ 5458 1451 180 Alphas: 5458 1451 181 Model: Spherical 5458 1451 182 OMP : A simplified folding model potential /11/ 5458 1451 183 (The nucleon OMP was taken from Ref./7/.) 5458 1451 184 5458 1451 185 3. Level scheme of Xe-135 5458 1451 186 ------------------------------------ 5458 1451 187 No. Ex(MeV) J PI CC 5458 1451 188 ------------------------------------ 5458 1451 189 0 0.00000 3/2 + * 5458 1451 190 1 0.28846 1/2 + 5458 1451 191 2 0.52655 11/2 - 5458 1451 192 3 1.13151 7/2 + 5458 1451 193 4 1.26042 5/2 + * 5458 1451 194 5 1.44836 3/2 + 5458 1451 195 6 1.45757 5/2 + 5458 1451 196 7 1.54370 1/2 + 5458 1451 197 8 1.56529 9/2 + 5458 1451 198 9 1.67807 7/2 + 5458 1451 199 10 1.78139 11/2 + 5458 1451 200 11 1.79121 5/2 + 5458 1451 201 12 1.89445 7/2 - 5458 1451 202 13 1.92729 7/2 + 5458 1451 203 14 1.96832 9/2 + 5458 1451 204 ------------------------------------ 5458 1451 205 Levels above 1.97832 MeV are assumed to be continuous. 5458 1451 206 5458 1451 207 5458 1451 208 4. Level density parameters 5458 1451 209 Energy-dependent parameters of Mengoni-Nakajima /12/ were used 5458 1451 210 ---------------------------------------------------------- 5458 1451 211 Nuclei a* Pair Esh T E0 Ematch Elv_max 5458 1451 212 1/MeV MeV MeV MeV MeV MeV MeV 5458 1451 213 ---------------------------------------------------------- 5458 1451 214 Xe-136 16.658 2.058 -4.823 0.873 0.098 8.676 2.582 5458 1451 215 Xe-135 17.198 1.033 -3.799 0.704 0.072 5.487 1.968 5458 1451 216 Xe-134 16.449 2.073 -2.814 0.742 0.503 7.492 2.409 5458 1451 217 Xe-133 16.992 1.041 -1.762 0.696 -0.731 6.456 0.911 5458 1451 218 I -135 15.861 1.033 -5.868 0.979 -0.961 8.260 1.133 5458 1451 219 I -134 16.358 0.000 -4.805 0.906 -2.236 7.123 0.210 5458 1451 220 I -133 15.660 1.041 -3.586 0.875 -1.279 8.089 2.025 5458 1451 221 Te-133 16.992 1.041 -5.785 0.914 -0.835 7.754 0.308 5458 1451 222 Te-132 16.240 2.089 -4.641 0.884 0.085 8.791 1.925 5458 1451 223 Te-131 22.166 1.048 -3.417 0.613 -0.582 5.846 1.043 5458 1451 224 ---------------------------------------------------------- 5458 1451 225 5458 1451 226 5. Gamma-ray strength functions 5458 1451 227 M1, E2: Standard Lorentzian (SLO) 5458 1451 228 E1 : Generalized Lorentzian (GLO) /13/ 5458 1451 229 5458 1451 230 6. Preequilibrium process 5458 1451 231 Preequilibrium is on for n, p, d, t, He-3, and alpha. 5458 1451 232 Preequilibrium capture is on. 5458 1451 233 5458 1451 234 5458 1451 235 References 5458 1451 236 1) Smith, E.C. et al. : Phys. Rev., 115, 1693 (1959). 5458 1451 237 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5458 1451 238 3) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) 5458 1451 239 [in Japanese]. 5458 1451 240 4) E.Soukhovitski et al., JAERI-Data/Code 2005-002 (2005). 5458 1451 241 5) J.Raynal, CEA Saclay report, CEA-N-2772 (1994). 5458 1451 242 6) S.Raman et al., At. Data and Nucl. Data Tables 78, 1 (1995) 5458 1451 243 7) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5458 1451 244 8) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5458 1451 245 9) Bojowald et al., Phys. Rev. C 38, 1153 (1988). 5458 1451 246 10) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 5458 1451 247 Phenomena in Nuclear Reactions," p.682, The University 5458 1451 248 of Wisconsin Press (1971). 5458 1451 249 11) Macklin, R.L.: ORNL-TM-10766 (1988). 5458 1451 250 12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 5458 1451 251 (1994). 5458 1451 252 13) M.Brink, Ph.D thesis, Oxford University, 1955. 5458 1451 253 5458 1451 254 1 451 281 15458 1451 255 2 151 4 15458 1451 256 3 4 26 15458 1451 257 3 16 10 15458 1451 258 3 28 7 15458 1451 259 3 32 6 15458 1451 260 3 102 237 15458 1451 261 3 103 15 15458 1451 262 3 104 9 15458 1451 263 3 105 9 15458 1451 264 3 106 7 15458 1451 265 3 107 21 15458 1451 266 8 4 2 15458 1451 267 8 16 2 15458 1451 268 8 17 3 15458 1451 269 8 22 3 15458 1451 270 8 28 2 15458 1451 271 8 32 2 15458 1451 272 8 102 2 15458 1451 273 8 103 2 15458 1451 274 8 104 2 15458 1451 275 8 105 2 15458 1451 276 8 106 2 15458 1451 277 8 107 2 15458 1451 278 10 4 24 15458 1451 279 10 17 9 15458 1451 280 10 22 23 15458 1451 281 5458 1 099999 5458 0 0 0 5.413500+4 1.337483+2 0 0 1 05458 2151 1 5.413500+4 1.000000+0 0 0 1 05458 2151 2 1.000000-5 1.900000+2 0 0 0 05458 2151 3 1.500000+0 5.310000-1 0 0 0 05458 2151 4 5458 2 099999 5458 0 0 0 5.413500+4 1.337483+2 0 0 0 05458 3 4 1 0.000000+0-2.884550+5 0 0 1 685458 3 4 2 68 2 5458 3 4 3 2.906117+5 0.000000+0 3.000000+5 4.141000-2 3.500000+5 1.201000-15458 3 4 4 4.000000+5 1.649000-1 4.500000+5 1.931000-1 5.000000+5 2.128000-15458 3 4 5 5.304879+5 2.221293-1 5.500000+5 2.365750-1 6.000000+5 2.629000-15458 3 4 6 6.500000+5 2.853600-1 7.000000+5 3.060100-1 7.500000+5 3.260000-15458 3 4 7 8.000000+5 3.458000-1 8.500000+5 3.655600-1 9.000000+5 3.852200-15458 3 4 8 9.500000+5 4.048100-1 1.000000+6 4.242000-1 1.139970+6 4.580028-15458 3 4 9 1.200000+6 5.787000-1 1.269844+6 6.108632-1 1.400000+6 8.159000-15458 3 4 10 1.459189+6 8.278266-1 1.468468+6 8.352145-1 1.555242+6 9.673398-15458 3 4 11 1.576993+6 1.009541+0 1.600000+6 1.074090+0 1.690616+6 1.131622+05458 3 4 12 1.794709+6 1.255418+0 1.800000+6 1.264218+0 1.804602+6 1.268329+05458 3 4 13 1.908614+6 1.400177+0 1.941700+6 1.455003+0 1.983037+6 1.545623+05458 3 4 14 1.993111+6 1.573459+0 2.000000+6 1.592594+0 2.200000+6 1.716980+05458 3 4 15 2.400000+6 1.822750+0 2.600000+6 1.919110+0 2.800000+6 2.009420+05458 3 4 16 3.000000+6 2.093050+0 3.250000+6 2.182230+0 3.500000+6 2.258590+05458 3 4 17 3.750000+6 2.311585+0 4.000000+6 2.347820+0 4.250000+6 2.364663+05458 3 4 18 4.500000+6 2.366353+0 4.750000+6 2.356100+0 5.000000+6 2.335382+05458 3 4 19 5.500000+6 2.278057+0 6.000000+6 2.218814+0 6.500000+6 2.173294+05458 3 4 20 7.000000+6 2.050230+0 7.500000+6 1.867083+0 8.000000+6 1.636687+05458 3 4 21 8.500000+6 1.396356+0 9.000000+6 1.122113+0 9.500000+6 8.749006-15458 3 4 22 1.000000+7 6.750565-1 1.100000+7 4.138615-1 1.200000+7 2.774872-15458 3 4 23 1.300000+7 2.076738-1 1.400000+7 1.731768-1 1.500000+7 1.542903-15458 3 4 24 1.600000+7 1.423765-1 1.700000+7 1.334503-1 1.800000+7 1.259983-15458 3 4 25 1.900000+7 1.189417-1 2.000000+7 1.122483-1 5458 3 4 26 5458 3 099999 5.413500+4 1.337483+2 0 0 0 05458 3 16 1 -6.363860+6-6.363860+6 0 0 1 195458 3 16 2 19 2 5458 3 16 3 6.411441+6 0.000000+0 6.500000+6 0.000000+0 7.000000+6 9.456000-25458 3 16 4 7.500000+6 2.652000-1 8.000000+6 4.935000-1 8.500000+6 7.361000-15458 3 16 5 9.000000+6 1.013000+0 9.500000+6 1.260000+0 1.000000+7 1.456000+05458 3 16 6 1.100000+7 1.701000+0 1.200000+7 1.814000+0 1.300000+7 1.861000+05458 3 16 7 1.400000+7 1.877000+0 1.500000+7 1.882000+0 1.600000+7 1.864000+05458 3 16 8 1.700000+7 1.700000+0 1.800000+7 1.403000+0 1.900000+7 1.088000+05458 3 16 9 2.000000+7 8.197000-1 5458 3 16 10 5458 3 099999 5.413500+4 1.337483+2 0 0 0 05458 3 28 1 -9.633513+6-9.633513+6 0 0 1 125458 3 28 2 12 2 5458 3 28 3 9.705540+6 0.000000+0 1.000000+7 2.52800-30 1.100000+7 3.64100-155458 3 28 4 1.200000+7 2.179000-9 1.300000+7 6.920000-7 1.400000+7 1.990000-55458 3 28 5 1.500000+7 1.811000-4 1.600000+7 8.568000-4 1.700000+7 2.685000-35458 3 28 6 1.800000+7 6.433000-3 1.900000+7 1.254000-2 2.000000+7 2.098000-25458 3 28 7 5458 3 099999 5.413500+4 1.337483+2 0 0 0 05458 3 32 1 -1.366616+7-1.366616+7 0 0 1 85458 3 32 2 8 2 5458 3 32 3 1.376833+7 0.000000+0 1.400000+7 1.44900-34 1.500000+7 3.13400-195458 3 32 4 1.600000+7 2.39500-12 1.700000+7 6.567000-9 1.800000+7 4.625000-75458 3 32 5 1.900000+7 8.048000-6 2.000000+7 6.071000-5 5458 3 32 6 5458 3 099999 5.413500+4 1.337483+2 0 0 0 05458 3102 1 8.079422+6 8.079422+6 0 0 1 7005458 3102 2 700 2 5458 3102 3 1.000000-5 9.306713+7 1.103037-5 8.861454+7 1.216691-5 8.437505+75458 3102 4 1.342055-5 8.033847+7 1.480336-5 7.649508+7 1.632865-5 7.283565+75458 3102 5 1.801111-5 6.935138+7 1.986691-5 6.603388+7 2.191394-5 6.287518+75458 3102 6 2.417189-5 5.986769+7 2.666248-5 5.700416+7 2.940971-5 5.427773+75458 3102 7 3.243999-5 5.168182+7 3.578251-5 4.921020+7 3.946943-5 4.685693+75458 3102 8 4.353624-5 4.461634+7 4.802208-5 4.248305+7 5.297013-5 4.045194+75458 3102 9 5.842801-5 3.851811+7 6.444825-5 3.667692+7 7.108881-5 3.492395+75458 3102 10 7.841358-5 3.325497+7 8.649308-5 3.166598+7 9.540506-5 3.015316+75458 3102 11 1.052353-4 2.871288+7 1.160784-4 2.734166+7 1.280388-4 2.603623+75458 3102 12 1.412315-4 2.479344+7 1.557836-4 2.361031+7 1.718351-4 2.248400+75458 3102 13 1.895404-4 2.141180+7 2.090701-4 2.039114+7 2.306120-4 1.941958+75458 3102 14 2.543736-4 1.849478+7 2.805835-4 1.761453+7 3.094939-4 1.677671+75458 3102 15 3.413832-4 1.597932+7 3.765583-4 1.522046+7 4.153577-4 1.449830+75458 3102 16 4.581549-4 1.381111+7 5.053618-4 1.315726+7 5.574328-4 1.253518+75458 3102 17 6.148689-4 1.194338+7 6.782232-4 1.138045+7 7.481052-4 1.084505+75458 3102 18 8.251877-4 1.033590+7 9.102125-4 9.851781+6 1.003998-3 9.391541+65458 3102 19 1.107447-3 8.954082+6 1.221555-3 8.538363+6 1.347420-3 8.143393+65458 3102 20 1.486254-3 7.768234+6 1.639393-3 7.411992+6 1.808311-3 7.073824+65458 3102 21 1.994634-3 6.752928+6 2.215676-3 6.427343+6 2.461091-3 6.119983+65458 3102 22 2.733825-3 5.829733+6 3.036632-3 5.556086+6 3.373145-3 5.298059+65458 3102 23 3.746766-3 5.055213+6 4.161975-3 4.826692+6 4.622969-3 4.612133+65458 3102 24 5.135277-3 4.410808+6 5.704077-3 4.222427+6 6.336191-3 4.046376+65458 3102 25 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