JENDL-5 (Neutron sublibrary (activation cs)) Ce-141 0 0 0 0 5.814100+4 1.396978+2 0 0 6 15840 1451 1 0.000000+0 1.000000+0 0 0 0 65840 1451 2 1.000000+0 2.000000+7 0 0 10 55840 1451 3 2.936000+2 0.000000+0 4 0 281 265840 1451 4 58-Ce-141 JAEA EVAL-FEB10 S.Kunieda, A.Ichihara, K.Shibata+5840 1451 5 DIST-DEC21 20100223 5840 1451 6 ----JENDL-5 MATERIAL 5840 5840 1451 7 -----INCIDENT NEUTRON DATA 5840 1451 8 ------ENDF-6 FORMAT 5840 1451 9 5840 1451 10 History 5840 1451 11 10-02 Re-evaluation was performed for JENDL-4 5840 1451 12 (compiled by S. Kunieda). 5840 1451 13 21-11 revised by O.Iwamoto 5840 1451 14 (MF8/MT4,16,17,22,28,32,102-107) added 5840 1451 15 5840 1451 16 MF= 1 General information 5840 1451 17 5840 1451 18 MT=451 Descriptive data and directory 5840 1451 19 5840 1451 20 5840 1451 21 MF= 2 Resonance parameters 5840 1451 22 5840 1451 23 MT=151 Resolved and unresolved resonance parameters 5840 1451 24 5840 1451 25 - Resolved resonance region (MLBW formula): below 40 eV 5840 1451 26 For JENDL3.3, experimental data measured by Anufriev et 5840 1451 27 al./1/ for 6 resonances below 335 eV were used. 5840 1451 28 Resonance energies, neutron and radiation widths obtained 5840 1451 29 by Anufriev et al. were adopted. Total spin J was 5840 1451 30 determined with a random number method. Finally, a negative5840 1451 31 resonance was added so as to reproduce the thermal capture 5840 1451 32 cross section given by Mughabghab et al./2/ 5840 1451 33 For JENDL-4.0, the neutron width of 7.4-eV resonance was 5840 1451 34 modified. That of JENDL-3.3 was 10 times larger than 5840 1451 35 reported value. Total spin J of each resonance was 5840 1451 36 re-evaluated. Neutron width of -5.0-eV resonance was 5840 1451 37 adjusted to reproduce the capture cross section of 29+-3 b 5840 1451 38 /3/. Upper boundary of the resolved resonance region was 5840 1451 39 set to 40 eV instead of 350 eV of JENDL-3.3, because level- 5840 1451 40 missing was seen above this energy. 5840 1451 41 5840 1451 42 - Unresolved resonance region: 40 eV - 200 keV 5840 1451 43 The parameters were obtained by fitting to the total and 5840 1451 44 capture cross sections calculated by the POD code /4/. 5840 1451 45 The ASREP code /5/ was employed in this evaluation. 5840 1451 46 The unresolved parameters should be used only for 5840 1451 47 self-shielding calculation. 5840 1451 48 5840 1451 49 Thermal cross sections & resonance integrals at 300 K 5840 1451 50 ---------------------------------------------------------- 5840 1451 51 0.0253 eV res. integ. (*) 5840 1451 52 (barns) (barns) 5840 1451 53 ---------------------------------------------------------- 5840 1451 54 Total 3.23139E+01 5840 1451 55 Elastic 3.28994E+00 5840 1451 56 n,gamma 2.90240E+01 1.48336E+02 5840 1451 57 ---------------------------------------------------------- 5840 1451 58 (*) Integrated from 0.5 eV to 10 MeV. 5840 1451 59 5840 1451 60 5840 1451 61 MF= 3 Neutron cross sections 5840 1451 62 5840 1451 63 MT= 1 Total cross section 5840 1451 64 Sum of partial cross sections. 5840 1451 65 5840 1451 66 MT= 2 Elastic scattering cross section 5840 1451 67 The OPTMAN /6/ & POD calculations /4/. 5840 1451 68 5840 1451 69 MT= 3 Non-elastic cross section 5840 1451 70 Sum of partial non-elastic cross sections. 5840 1451 71 5840 1451 72 MT= 4,51-91 (n,n') cross section 5840 1451 73 The OPTMAN /6/ & POD calculations /4/. 5840 1451 74 5840 1451 75 MT= 16 (n,2n) cross section 5840 1451 76 MT= 17 (n,3n) cross section 5840 1451 77 MT= 22 (n,na) cross section 5840 1451 78 MT= 28 (n,np) cross section 5840 1451 79 MT= 32 (n,nd) cross section 5840 1451 80 MT=102 Capture cross section 5840 1451 81 MT=103 (n,p) cross section 5840 1451 82 MT=104 (n,d) cross section 5840 1451 83 MT=105 (n,t) cross section 5840 1451 84 MT=106 (n,He3) cross section 5840 1451 85 MT=107 (n,a) cross section 5840 1451 86 Calculated by the POD code /4/. 5840 1451 87 5840 1451 88 MT=203 (n,xp) cross section 5840 1451 89 Sum of (n,np) and (n,p) 5840 1451 90 5840 1451 91 MT=204 (n,xd) cross section 5840 1451 92 Sum of (n,nd) and (n,d) 5840 1451 93 5840 1451 94 MT=205 (n,xt) cross section 5840 1451 95 MT=206 (n,xHe3) cross section 5840 1451 96 Calculated by the POD code /4/. 5840 1451 97 5840 1451 98 MT=207 (n,xa) cross section 5840 1451 99 Sum of (n,na) and (n,a) 5840 1451 100 5840 1451 101 5840 1451 102 MF= 4 Angular distributions of emitted neutrons 5840 1451 103 5840 1451 104 MT= 2 Elastic scattering 5840 1451 105 The OPTMAN /6/ & POD calculations /4/. 5840 1451 106 5840 1451 107 5840 1451 108 MF= 6 Energy-angle distributions of emitted particles 5840 1451 109 5840 1451 110 MT= 16 (n,2n) reaction 5840 1451 111 MT= 17 (n,3n) reaction 5840 1451 112 MT= 22 (n,na) reaction 5840 1451 113 MT= 28 (n,np) reaction 5840 1451 114 MT= 32 (n,nd) reaction 5840 1451 115 Neutron spectra calculated by the POD code /4/. 5840 1451 116 5840 1451 117 MT= 51-90 (n,n') reaction 5840 1451 118 Neutron angular distributions calculated by 5840 1451 119 OPTMAN /6/ & POD /4/. 5840 1451 120 5840 1451 121 MT= 91 (n,n') reaction 5840 1451 122 Neutron spectra calculated by the POD code /4/. 5840 1451 123 5840 1451 124 MT= 203 (n,xp) reaction 5840 1451 125 MT= 204 (n,xd) reaction 5840 1451 126 MT= 205 (n,xt) reaction 5840 1451 127 MT= 206 (n,xHe3) reaction 5840 1451 128 MT= 207 (n,xa) reaction 5840 1451 129 Light-ion spectra calculated by the POD code /6/. 5840 1451 130 5840 1451 131 5840 1451 132 MF=12 Gamma-ray multiplicities 5840 1451 133 5840 1451 134 MT= 3 Non-elastic gamma emission 5840 1451 135 Calculated by the POD code /4/. 5840 1451 136 5840 1451 137 5840 1451 138 MF=14 Gamma-ray angular distributions 5840 1451 139 5840 1451 140 MT= 3 Non-elastic gamma emission 5840 1451 141 Assumed to be isotropic. 5840 1451 142 5840 1451 143 5840 1451 144 MF=15 Gamma-ray spectra 5840 1451 145 5840 1451 146 MT= 3 Non-elastic gamma emission 5840 1451 147 Calculated by the POD code /4/. 5840 1451 148 5840 1451 149 5840 1451 150 5840 1451 151 5840 1451 152 *************************************************************** 5840 1451 153 * Nuclear Model Calculations with POD Code /4/ * 5840 1451 154 *************************************************************** 5840 1451 155 1. Theoretical models 5840 1451 156 The POD code is based on the spherical optical model, the 5840 1451 157 distorted-wave Born approximaiton (DWBA), one-component exciton 5840 1451 158 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 5840 1451 159 tical model. With the preequilibrium model, semi-empirical 5840 1451 160 pickup and knockout process can be taken into account for 5840 1451 161 composite-particle emission. The gamma-ray emission from the 5840 1451 162 compound nucleus can be calculated within the framework of the 5840 1451 163 exciton model. The code is capable of reading in particle 5840 1451 164 transmission coefficients calculated by separate spherical or 5840 1451 165 coupled-channel optical model code. In this evaluation, the OPTMAN5840 1451 166 code /6/ was employed for neutrons, while the ECIS code 5840 1451 167 /7/ was adopted for charged particles. 5840 1451 168 5840 1451 169 2. Optical model & parameters 5840 1451 170 Neutrons: 5840 1451 171 Model: Coupled-channel model based on the rigid-rotor model 5840 1451 172 OMP : Based on the Coupled-channel optical potential /8/ 5840 1451 173 The original Parameters were slightly modified as 5840 1451 174 listed below to reproduce experimental total cross 5840 1451 175 sections measured by Camarda et al /9/. 5840 1451 176 ------------------------------------------------------------ 5840 1451 177 - Real-volume term 5840 1451 178 VR0= -3.85E+1 MeV VR1= 2.70E-2 MeV VR2= 1.20E-4 MeV 5840 1451 179 VR3= 3.50E-7 MeV VRLA= 9.49E+1 MeV ALAVR= 4.22E-3 5840 1451 180 r= 1.21E+0 a= 6.30E-1 5840 1451 181 - Imaginary-surface term 5840 1451 182 WDBW= 1.30E+1 MeV WDWID= 1.40E+1 MeV ALAWD= 1.40E-2 5840 1451 183 r= 1.21E+0 a= 6.75E-1 5840 1451 184 - Imaginary-volume term 5840 1451 185 WCBW= 1.70E+1 MeV WCWID= 1.05E+2 MeV 5840 1451 186 r= 1.21E+0 a= 6.75E-1 5840 1451 187 - Spin-orbit term 5840 1451 188 VS= 6.34E+0 MeV ALASO= 5.00E-3 5840 1451 189 WSBW= -3.10E+0 MeV WSWID= 1.60E+2 MeV 5840 1451 190 r= 1.06E+0 a= 5.90E-1 5840 1451 191 - Isospin coefficients 5840 1451 192 CISO= 2.43E+1 WCISO= 1.80E+1 CCOUL= 9.00E-1 5840 1451 193 - Deformation parameter 5840 1451 194 Beta2= -1.00E-1 5840 1451 195 ------------------------------------------------------------ 5840 1451 196 Protons: 5840 1451 197 Model: Spherical 5840 1451 198 OMP : Koning and Delaroche /10/ 5840 1451 199 Deuterons: 5840 1451 200 Model: Spherical 5840 1451 201 OMP : Bojowald et al. /11/ 5840 1451 202 Tritons: 5840 1451 203 Mode: Spherical 5840 1451 204 OMP : Becchetti and Greenlees /12/ 5840 1451 205 He-3: 5840 1451 206 Model: Spherical 5840 1451 207 OMP : Becchetti and Greenlees /12/ 5840 1451 208 Alphas: 5840 1451 209 Model: Spherical 5840 1451 210 OMP : A simplified folding model potential /13/ 5840 1451 211 (The nucleon OMP was taken form Ref./8/.) 5840 1451 212 5840 1451 213 3. Level scheme of Ce-141 5840 1451 214 ------------------------------------ 5840 1451 215 No. Ex(MeV) J PI CC 5840 1451 216 ------------------------------------ 5840 1451 217 0 0.00000 7/2 - * 5840 1451 218 1 0.66206 3/2 - 5840 1451 219 2 1.13700 1/2 - 5840 1451 220 3 1.35452 9/2 - * 5840 1451 221 4 1.36870 13/2 + 5840 1451 222 5 1.37800 9/2 - 5840 1451 223 6 1.49700 5/2 - 5840 1451 224 7 1.62650 3/2 + 5840 1451 225 8 1.69330 11/2 - 5840 1451 226 9 1.73900 7/2 - 5840 1451 227 10 1.78500 1/2 + 5840 1451 228 11 1.80870 3/2 - 5840 1451 229 12 1.81200 5/2 - 5840 1451 230 13 1.91500 9/2 - 5840 1451 231 14 1.94200 1/2 + 5840 1451 232 ------------------------------------ 5840 1451 233 Levels above 1.95200 MeV are assumed to be continuous. 5840 1451 234 5840 1451 235 5840 1451 236 4. Level density parameters 5840 1451 237 Energy-dependent parameters of Mengoni-Nakajima /14/ were used 5840 1451 238 ---------------------------------------------------------- 5840 1451 239 Nuclei a* Pair Esh T E0 Ematch Elv_max 5840 1451 240 1/MeV MeV MeV MeV MeV MeV MeV 5840 1451 241 ---------------------------------------------------------- 5840 1451 242 Ce-142 17.282 2.014 -0.311 0.610 0.530 6.671 2.365 5840 1451 243 Ce-141 17.686 1.011 -1.072 0.493 0.659 3.613 1.942 5840 1451 244 Ce-140 17.074 2.028 -1.942 0.640 0.903 6.384 2.481 5840 1451 245 Ce-139 17.607 1.018 -1.120 0.492 0.694 3.570 1.985 5840 1451 246 La-141 16.464 1.011 -0.489 0.665 -0.737 6.277 0.929 5840 1451 247 La-140 17.665 0.000 -1.411 0.615 -1.257 4.391 0.602 5840 1451 248 La-139 16.263 1.018 -2.218 0.812 -1.629 8.151 1.257 5840 1451 249 Ba-139 20.276 1.018 -2.224 0.511 0.373 4.093 2.038 5840 1451 250 Ba-138 16.830 2.043 -3.130 0.710 0.829 6.866 3.155 5840 1451 251 Ba-137 18.884 1.025 -2.239 0.463 0.926 3.110 1.908 5840 1451 252 ---------------------------------------------------------- 5840 1451 253 5840 1451 254 5. Gamma-ray strength functions 5840 1451 255 M1, E2: Standard Lorentzian (SLO) 5840 1451 256 E1 : Generalized Lorentzian (GLO) /15/ 5840 1451 257 5840 1451 258 6. Preequilibrium process 5840 1451 259 Preequilibrium is on for n, p, d, t, He-3, and alpha. 5840 1451 260 Preequilibrium capture is on. 5840 1451 261 5840 1451 262 5840 1451 263 References 5840 1451 264 1) B.A.Anufriev et al. : 1980 Kiev, Vol.2, p.136 (1980). 5840 1451 265 2) S.F.Mughabghab et al.: "Neutron Cross Sections, Vol. I, 5840 1451 266 Part A," Academic Press (1981). 5840 1451 267 3) P.M.Lantz et al.: Nucl. Sci. Eng., 20, 302 (1964). 5840 1451 268 4) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5840 1451 269 5) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) 5840 1451 270 [in Japanese]. 5840 1451 271 6) E.Soukhovitski et al., JAERI-Data/Code 2005-002 (2005). 5840 1451 272 7) J.Raynal, CEA Saclay report, CEA-N-2772 (1994). 5840 1451 273 8) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5840 1451 274 9) Camarda et al., Phys. Rev. C 29, 2106 (1984). 5840 1451 275 10) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5840 1451 276 11) Bojowald et al., Phys. Rev. C 38, 1153 (1988). 5840 1451 277 12) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 5840 1451 278 Phenomena in Nuclear Reactions," p.682, The University 5840 1451 279 of Wisconsin Press (1971). 5840 1451 280 13) D.G.Madland, NEANDC-245 (1988), p. 103. 5840 1451 281 14) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 5840 1451 282 (1994). 5840 1451 283 15) M.Brink, Ph.D thesis, Oxford University, 1955. 5840 1451 284 5840 1451 285 1 451 311 15840 1451 286 2 151 4 15840 1451 287 3 4 23 15840 1451 288 3 16 10 15840 1451 289 3 17 6 15840 1451 290 3 22 8 15840 1451 291 3 28 7 15840 1451 292 3 32 6 15840 1451 293 3 102 421 15840 1451 294 3 103 11 15840 1451 295 3 104 8 15840 1451 296 3 105 8 15840 1451 297 3 106 6 15840 1451 298 3 107 21 15840 1451 299 8 4 2 15840 1451 300 8 16 2 15840 1451 301 8 17 2 15840 1451 302 8 22 2 15840 1451 303 8 28 2 15840 1451 304 8 32 2 15840 1451 305 8 102 2 15840 1451 306 8 103 2 15840 1451 307 8 104 2 15840 1451 308 8 105 2 15840 1451 309 8 106 2 15840 1451 310 8 107 2 15840 1451 311 5840 1 099999 5840 0 0 0 5.814100+4 1.396978+2 0 0 1 05840 2151 1 5.814100+4 1.000000+0 0 0 1 05840 2151 2 1.000000-5 4.000000+1 0 0 0 05840 2151 3 3.500000+0 5.000000-1 0 0 0 05840 2151 4 5840 2 099999 5840 0 0 0 5.814100+4 1.396978+2 0 0 0 05840 3 4 1 0.000000+0-6.620600+5 0 0 1 605840 3 4 2 60 2 5840 3 4 3 6.667992+5 0.000000+0 7.000000+5 3.420000-2 7.500000+5 5.174000-25840 3 4 4 8.000000+5 6.495000-2 8.500000+5 7.662000-2 9.000000+5 8.782000-25840 3 4 5 9.500000+5 9.918000-2 1.000000+6 1.109000-1 1.145139+6 1.456608-15840 3 4 6 1.200000+6 1.668510-1 1.364216+6 2.119028-1 1.378498+6 2.488599-15840 3 4 7 1.387864+6 2.820779-1 1.400000+6 3.686300-1 1.507716+6 5.232186-15840 3 4 8 1.600000+6 7.089300-1 1.638143+6 7.342894-1 1.705421+6 7.877273-15840 3 4 9 1.751448+6 8.587359-1 1.797778+6 9.692402-1 1.800000+6 9.749473-15840 3 4 10 1.821647+6 1.007702+0 1.824971+6 1.013141+0 1.928708+6 1.209321+05840 3 4 11 1.955901+6 1.278750+0 1.965973+6 1.304836+0 2.000000+6 1.397289+05840 3 4 12 2.200000+6 1.604363+0 2.400000+6 1.776463+0 2.600000+6 1.917471+05840 3 4 13 2.800000+6 2.028990+0 3.000000+6 2.117840+0 3.250000+6 2.203355+05840 3 4 14 3.500000+6 2.263388+0 3.750000+6 2.301129+0 4.000000+6 2.319071+05840 3 4 15 4.250000+6 2.315234+0 4.500000+6 2.294216+0 4.750000+6 2.264173+05840 3 4 16 5.000000+6 2.230417+0 5.500000+6 2.163903+0 6.000000+6 2.061231+05840 3 4 17 6.500000+6 1.912894+0 7.000000+6 1.761999+0 7.500000+6 1.649550+05840 3 4 18 8.000000+6 1.474188+0 8.500000+6 1.224121+0 9.000000+6 9.874337-15840 3 4 19 9.500000+6 7.604918-1 1.000000+7 6.211195-1 1.100000+7 4.110597-15840 3 4 20 1.200000+7 3.036073-1 1.300000+7 2.489583-1 1.400000+7 2.200255-15840 3 4 21 1.500000+7 2.041874-1 1.600000+7 1.932050-1 1.700000+7 1.843951-15840 3 4 22 1.800000+7 1.765292-1 1.900000+7 1.690702-1 2.000000+7 1.620448-15840 3 4 23 5840 3 099999 5.814100+4 1.396978+2 0 0 0 05840 3 16 1 -5.428143+6-5.428143+6 0 0 1 215840 3 16 2 21 2 5840 3 16 3 5.467000+6 0.000000+0 5.500000+6 0.000000+0 6.000000+6 5.700000-25840 3 16 4 6.500000+6 1.824000-1 7.000000+6 3.301000-1 7.500000+6 4.500000-15840 3 16 5 8.000000+6 6.379000-1 8.500000+6 8.978000-1 9.000000+6 1.138000+05840 3 16 6 9.500000+6 1.364000+0 1.000000+7 1.497000+0 1.100000+7 1.689000+05840 3 16 7 1.200000+7 1.779000+0 1.300000+7 1.821000+0 1.400000+7 1.841000+05840 3 16 8 1.500000+7 1.848000+0 1.600000+7 1.835000+0 1.700000+7 1.756000+05840 3 16 9 1.800000+7 1.580000+0 1.900000+7 1.355000+0 2.000000+7 1.110000+05840 3 16 10 5840 3 099999 5.814100+4 1.396978+2 0 0 0 05840 3 17 1 -1.463024+7-1.463024+7 0 0 1 75840 3 17 2 7 2 5840 3 17 3 1.473497+7 0.000000+0 1.500000+7 0.000000+0 1.600000+7 1.072000-25840 3 17 4 1.700000+7 8.497000-2 1.800000+7 2.443000-1 1.900000+7 4.432000-15840 3 17 5 2.000000+7 6.545000-1 5840 3 17 6 5840 3 099999 5.814100+4 1.396978+2 0 0 0 05840 3 22 1 -1.437930+5-1.437930+5 0 0 1 145840 3 22 2 14 2 5840 3 22 3 1.448223+5 0.000000+0 9.000000+6 0.000000+0 9.500000+6 7.088000-75840 3 22 4 1.000000+7 3.061000-6 1.100000+7 2.142000-5 1.200000+7 7.981000-55840 3 22 5 1.300000+7 2.401000-4 1.400000+7 6.486000-4 1.500000+7 1.585000-35840 3 22 6 1.600000+7 3.409000-3 1.700000+7 6.327000-3 1.800000+7 1.019000-25840 3 22 7 1.900000+7 1.465000-2 2.000000+7 1.935000-2 5840 3 22 8 5840 3 099999 5.814100+4 1.396978+2 0 0 0 05840 3 28 1 -8.408044+6-8.408044+6 0 0 1 115840 3 28 2 11 2 5840 3 28 3 8.468232+6 0.000000+0 1.100000+7 0.000000+0 1.200000+7 6.278000-75840 3 28 4 1.300000+7 1.718000-5 1.400000+7 1.464000-4 1.500000+7 6.901000-45840 3 28 5 1.600000+7 2.225000-3 1.700000+7 5.477000-3 1.800000+7 1.098000-25840 3 28 6 1.900000+7 1.880000-2 2.000000+7 2.865000-2 5840 3 28 7 5840 3 099999 5.814100+4 1.396978+2 0 0 0 05840 3 32 1 -1.134446+7-1.134446+7 0 0 1 75840 3 32 2 7 2 5840 3 32 3 1.142566+7 0.000000+0 1.500000+7 0.000000+0 1.600000+7 2.144000-65840 3 32 4 1.700000+7 3.615000-5 1.800000+7 2.609000-4 1.900000+7 1.046000-35840 3 32 5 2.000000+7 2.775000-3 5840 3 32 6 5840 3 099999 5.814100+4 1.396978+2 0 0 0 05840 3102 1 7.169691+6 7.169691+6 0 0 1 12535840 3102 2 1253 2 5840 3102 3 1.000000-5 1.471256+3 1.103037-5 1.400854+3 1.216691-5 1.333822+35840 3102 4 1.342055-5 1.269997+3 1.480336-5 1.209226+3 1.632865-5 1.151363+35840 3102 5 1.801111-5 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