JENDL-5 (Neutron sublibrary (activation cs)) Sn-126 0 0 0 0 5.012600+4 1.248260+2 0 0 6 15067 1451 1 0.000000+0 1.000000+0 0 0 0 65067 1451 2 1.000000+0 2.000000+7 0 0 10 55067 1451 3 2.936000+2 0.000000+0 4 0 228 245067 1451 4 50-Sn-126 JAEA EVAL-Dec09 N.Iwamoto 5067 1451 5 DIST-DEC21 20100119 5067 1451 6 ----JENDL-5 MATERIAL 5067 5067 1451 7 -----INCIDENT NEUTRON DATA 5067 1451 8 ------ENDF-6 FORMAT 5067 1451 9 5067 1451 10 History 5067 1451 11 09-12 The data above the resolved resonance region were evaluated 5067 1451 12 and compiled by N.Iwamoto. 5067 1451 13 21-11 revised by O.Iwamoto 5067 1451 14 (MF8/MT4,16,17,22,28,102-107) added 5067 1451 15 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 5067 1451 16 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 5067 1451 17 5067 1451 18 5067 1451 19 MF= 1 General information 5067 1451 20 MT=451 Descriptive data and directory 5067 1451 21 5067 1451 22 MF= 2 Resonance parameters 5067 1451 23 MT=151 Resolved and unresolved resonances 5067 1451 24 No resolved resonance parameters 5067 1451 25 5067 1451 26 Unresolved resonance region : 6.8 keV - 200 keV 5067 1451 27 The unresolved resonance paramters (URP) were determined by 5067 1451 28 ASREP code /1/ so as to reproduce the evaluated total and 5067 1451 29 capture cross sections calculated with optical model code 5067 1451 30 OPTMAN /2/ and CCONE /3/. The unresolved parameters 5067 1451 31 should be used only for self-shielding calculation. 5067 1451 32 5067 1451 33 Thermal cross sections and resonance integrals at 300 K 5067 1451 34 ---------------------------------------------------------- 5067 1451 35 0.0253 eV res. integ. (*) 5067 1451 36 (barn) (barn) 5067 1451 37 ---------------------------------------------------------- 5067 1451 38 Total 4.9138e+00 5067 1451 39 Elastic 4.8197e+00 5067 1451 40 n,gamma 9.0035e-02 9.6380e-02 5067 1451 41 ---------------------------------------------------------- 5067 1451 42 (*) Integrated from 0.5 eV to 10 MeV. 5067 1451 43 5067 1451 44 MF= 3 Neutron cross sections 5067 1451 45 MT= 1 Total cross section 5067 1451 46 Sum of partial cross sections. 5067 1451 47 5067 1451 48 MT= 2 Elastic scattering cross section 5067 1451 49 Obtained by subtracting non-elastic scattering cross sections 5067 1451 50 from total cross section. 5067 1451 51 5067 1451 52 MT= 4 (n,n') cross section 5067 1451 53 Calculated with CCONE code /3/. 5067 1451 54 5067 1451 55 MT= 16 (n,2n) cross section 5067 1451 56 Calculated with CCONE code /3/. 5067 1451 57 5067 1451 58 MT= 17 (n,3n) cross section 5067 1451 59 Calculated with CCONE code /3/. 5067 1451 60 5067 1451 61 MT= 22 (n,na) cross section 5067 1451 62 Calculated with CCONE code /3/. 5067 1451 63 5067 1451 64 MT= 28 (n,np) cross section 5067 1451 65 Calculated with CCONE code /3/. 5067 1451 66 5067 1451 67 MT= 51-91 (n,n') cross section 5067 1451 68 Calculated with CCONE code /3/. 5067 1451 69 5067 1451 70 MT=102 Capture cross section 5067 1451 71 Calculated with CCONE code /3/. 5067 1451 72 5067 1451 73 MT=103 (n,p) cross section 5067 1451 74 Calculated with CCONE code /3/. 5067 1451 75 5067 1451 76 MT=104 (n,d) cross section 5067 1451 77 Calculated with CCONE code /3/. 5067 1451 78 5067 1451 79 MT=105 (n,t) cross section 5067 1451 80 Calculated with CCONE code /3/. 5067 1451 81 5067 1451 82 MT=106 (n,He3) cross section 5067 1451 83 Calculated with CCONE code /3/. 5067 1451 84 5067 1451 85 MT=107 (n,a) cross section 5067 1451 86 Calculated with CCONE code /3/. 5067 1451 87 5067 1451 88 MF= 4 Angular distributions of emitted neutrons 5067 1451 89 MT= 2 Elastic scattering 5067 1451 90 Calculated with CCONE code /3/. 5067 1451 91 5067 1451 92 MF= 6 Energy-angle distributions of emitted particles 5067 1451 93 MT= 16 (n,2n) reaction 5067 1451 94 Calculated with CCONE code /3/. 5067 1451 95 5067 1451 96 MT= 17 (n,3n) reaction 5067 1451 97 Calculated with CCONE code /3/. 5067 1451 98 5067 1451 99 MT= 22 (n,na) reaction 5067 1451 100 Calculated with CCONE code /3/. 5067 1451 101 5067 1451 102 MT= 28 (n,np) reaction 5067 1451 103 Calculated with CCONE code /3/. 5067 1451 104 5067 1451 105 MT= 51-91 (n,n') reaction 5067 1451 106 Calculated with CCONE code /3/. 5067 1451 107 5067 1451 108 MT=102 Capture reaction 5067 1451 109 Calculated with CCONE code /3/. 5067 1451 110 5067 1451 111 5067 1451 112 5067 1451 113 ***************************************************************** 5067 1451 114 Nuclear Model Calculation with CCONE code /3/ 5067 1451 115 ***************************************************************** 5067 1451 116 5067 1451 117 Models and parameters used in the CCONE calculation 5067 1451 118 1) Optical model 5067 1451 119 * coupled channels calculation 5067 1451 120 coupled levels: 0,1 (see Table 1) 5067 1451 121 5067 1451 122 * optical model potential 5067 1451 123 neutron omp: Kunieda,S. et al./4/ (+) 5067 1451 124 proton omp: Kunieda,S. et al./4/ 5067 1451 125 deuteron omp: Lohr,J.M. and Haeberli,W./5/ 5067 1451 126 triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./6/ 5067 1451 127 He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./6/ 5067 1451 128 alpha omp: Huizenga,J.R. and Igo,G./7/ 5067 1451 129 (+) omp parameters were modified. 5067 1451 130 5067 1451 131 2) Two-component exciton model/8/ 5067 1451 132 * Global parametrization of Koning-Duijvestijn/9/ 5067 1451 133 was used. 5067 1451 134 * Gamma emission channel/10/ was added to simulate direct 5067 1451 135 and semi-direct capture reaction. 5067 1451 136 5067 1451 137 3) Hauser-Feshbach statistical model 5067 1451 138 * Width fluctuation correction/11/ was applied. 5067 1451 139 * Neutron, proton, deuteron, triton, He3, alpha and gamma 5067 1451 140 decay channel were taken into account. 5067 1451 141 * Transmission coefficients of neutrons were taken from 5067 1451 142 optical model calculation. 5067 1451 143 * The level scheme of the target is shown in Table 1. 5067 1451 144 * Level density formula of constant temperature and Fermi-gas 5067 1451 145 model were used with shell energy correction/12/. 5067 1451 146 Parameters are shown in Table 2. 5067 1451 147 * Gamma-ray strength function of generalized Lorentzian form 5067 1451 148 /13/,/14/ was used for E1 transition. 5067 1451 149 For M1 and E2 transitions the standard Lorentzian form was 5067 1451 150 adopted. The prameters are shown in Table 3. 5067 1451 151 5067 1451 152 5067 1451 153 ------------------------------------------------------------------5067 1451 154 Tables 5067 1451 155 ------------------------------------------------------------------5067 1451 156 5067 1451 157 Table 1. Level Scheme of Sn-126 5067 1451 158 ------------------- 5067 1451 159 No. Ex(MeV) J PI 5067 1451 160 ------------------- 5067 1451 161 0 0.00000 0 + * 5067 1451 162 1 1.14115 2 + * 5067 1451 163 2 2.04974 4 + 5067 1451 164 3 2.11079 2 + 5067 1451 165 4 2.13009 2 + 5067 1451 166 5 2.16154 5 - 5067 1451 167 6 2.19422 4 - 5067 1451 168 7 2.21899 7 - 5067 1451 169 8 2.25652 3 - 5067 1451 170 9 2.27685 2 + 5067 1451 171 10 2.29800 1 + 5067 1451 172 11 2.37046 2 + 5067 1451 173 12 2.47193 4 + 5067 1451 174 13 2.47751 6 - 5067 1451 175 14 2.48824 8 + 5067 1451 176 15 2.55000 3 - 5067 1451 177 16 2.56450 10 + 5067 1451 178 17 2.63103 3 + 5067 1451 179 18 2.63664 2 + 5067 1451 180 19 2.66298 7 + 5067 1451 181 20 2.71206 4 + 5067 1451 182 21 2.72000 3 - 5067 1451 183 22 2.74257 1 - 5067 1451 184 ------------------- 5067 1451 185 *) Coupled levels in CC calculation 5067 1451 186 5067 1451 187 Table 2. Level density parameters 5067 1451 188 -------------------------------------------------------- 5067 1451 189 Nuclide a* Pair Eshell T E0 Ematch 5067 1451 190 1/MeV MeV MeV MeV MeV MeV 5067 1451 191 -------------------------------------------------------- 5067 1451 192 Sn-127 16.3728 1.0648 -3.3108 0.7888 -0.7788 7.5329 5067 1451 193 Sn-126 15.6101 2.1381 -2.6047 0.8273 -0.2048 9.2786 5067 1451 194 Sn-125 16.1653 1.0733 -1.4420 0.6783 -0.3617 5.7801 5067 1451 195 Sn-124 15.3994 2.1553 -1.0033 0.7260 0.3147 7.5454 5067 1451 196 In-126 15.5298 0.0000 -2.3056 0.6831 -0.9476 4.1443 5067 1451 197 In-125 14.8507 1.0733 -1.3884 0.6557 0.2272 4.7782 5067 1451 198 In-124 15.3217 0.0000 -0.3915 0.6954 -1.7265 4.9806 5067 1451 199 In-123 14.6475 1.0820 0.1996 0.6115 0.1625 4.5397 5067 1451 200 Cd-124 15.3994 2.1553 -0.6710 0.6750 0.7153 6.7076 5067 1451 201 Cd-123 15.9572 1.0820 0.4830 0.7005 -1.2943 6.7635 5067 1451 202 Cd-122 15.1883 2.1729 0.5773 0.6134 0.9712 5.9920 5067 1451 203 Cd-121 15.7486 1.0909 1.5385 0.6783 -1.3360 6.5598 5067 1451 204 -------------------------------------------------------- 5067 1451 205 5067 1451 206 Table 3. Gamma-ray strength function for Sn-127 5067 1451 207 -------------------------------------------------------- 5067 1451 208 * E1: ER = 15.39 (MeV) EG = 4.82 (MeV) SIG = 288.56 (mb) 5067 1451 209 * M1: ER = 8.16 (MeV) EG = 4.00 (MeV) SIG = 0.65 (mb) 5067 1451 210 * E2: ER = 12.53 (MeV) EG = 4.59 (MeV) SIG = 2.56 (mb) 5067 1451 211 -------------------------------------------------------- 5067 1451 212 5067 1451 213 References 5067 1451 214 1) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) 5067 1451 215 [in Japanese]. 5067 1451 216 2) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004). 5067 1451 217 3) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007). 5067 1451 218 4) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 5067 1451 219 5) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 5067 1451 220 6) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. 5067 1451 221 J.H.Williams Lab., Univ. Minnesota (1969). 5067 1451 222 7) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962). 5067 1451 223 8) Kalbach,C.: Phys. Rev. C33, 818 (1986). 5067 1451 224 9) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 5067 1451 225 10) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 5067 1451 226 11) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 5067 1451 227 12) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 5067 1451 228 (1994). 5067 1451 229 13) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990). 5067 1451 230 14) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990). 5067 1451 231 5067 1451 232 1 451 256 15067 1451 233 2 151 4 15067 1451 234 3 4 34 15067 1451 235 3 16 12 15067 1451 236 3 17 8 15067 1451 237 3 22 11 15067 1451 238 3 28 8 15067 1451 239 3 102 167 15067 1451 240 3 103 14 15067 1451 241 3 104 22 15067 1451 242 3 105 10 15067 1451 243 3 106 6 15067 1451 244 3 107 18 15067 1451 245 8 4 2 15067 1451 246 8 16 2 15067 1451 247 8 17 2 15067 1451 248 8 22 2 15067 1451 249 8 28 2 15067 1451 250 8 102 2 15067 1451 251 8 103 2 15067 1451 252 8 104 2 15067 1451 253 8 105 2 15067 1451 254 8 106 2 15067 1451 255 8 107 2 15067 1451 256 5067 1 099999 5067 0 0 0 5.012600+4 1.248260+2 0 0 1 05067 2151 1 5.012600+4 1.000000+0 0 0 1 05067 2151 2 6.800000+3 2.000000+5 0 0 0 05067 2151 3 0.000000+0 5.571000-1 0 0 0 05067 2151 4 5067 2 099999 5067 0 0 0 5.012600+4 1.248260+2 0 0 0 05067 3 4 1 0.000000+0-1.041660+5 0 0 1 925067 3 4 2 92 2 5067 3 4 3 1.050000+5 0.000000+0 1.100000+5 3.716120-8 1.200000+5 3.896330-85067 3 4 4 1.300000+5 4.277180-8 1.400000+5 4.750460-8 1.500000+5 5.159890-85067 3 4 5 1.600000+5 5.532650-8 1.700000+5 5.827470-8 1.800000+5 6.058280-85067 3 4 6 1.900000+5 6.241520-8 2.000000+5 6.389980-8 2.250000+5 2.776350-75067 3 4 7 2.500000+5 3.619040-7 2.750000+5 4.242510-7 3.000000+5 4.614390-75067 3 4 8 4.000000+5 1.604040-6 5.000000+5 4.049080-6 6.000000+5 8.529880-65067 3 4 9 7.000000+5 1.596850-5 8.000000+5 2.748410-5 9.000000+5 4.440790-55067 3 4 10 1.000000+6 6.830880-5 1.100000+6 1.013350-4 1.150290+6 1.259840-45067 3 4 11 1.200000+6 2.752813-1 1.300000+6 4.637736-1 1.400000+6 5.568873-15067 3 4 12 1.500000+6 6.183123-1 1.600000+6 6.562678-1 1.700000+6 6.920053-15067 3 4 13 1.800000+6 7.284073-1 1.900000+6 7.664632-1 2.000000+6 8.064126-15067 3 4 14 2.066160+6 8.224549-1 2.127700+6 8.712448-1 2.147150+6 9.070910-15067 3 4 15 2.178860+6 9.744143-1 2.211800+6 1.027531+0 2.236770+6 1.067488+05067 3 4 16 2.250000+6 1.085456+0 2.274600+6 1.114597+0 2.295090+6 1.143795+05067 3 4 17 2.316410+6 1.183923+0 2.389450+6 1.297808+0 2.491730+6 1.410771+05067 3 4 18 2.497360+6 1.415815+0 2.500000+6 1.418095+0 2.508170+6 1.423494+05067 3 4 19 2.570430+6 1.460135+0 2.585040+6 1.469408+0 2.652110+6 1.508705+05067 3 4 20 2.657760+6 1.512550+0 2.684310+6 1.531058+0 2.733790+6 1.559330+05067 3 4 21 2.741790+6 1.563830+0 2.750000+6 1.568783+0 2.764540+6 1.577400+05067 3 4 22 3.000000+6 1.728213+0 3.500000+6 1.943271+0 4.000000+6 2.111838+05067 3 4 23 4.500000+6 2.221057+0 5.000000+6 2.256426+0 5.500000+6 2.233869+05067 3 4 24 6.000000+6 2.181999+0 6.500000+6 2.124289+0 7.000000+6 2.075023+05067 3 4 25 7.500000+6 2.040138+0 8.000000+6 2.019328+0 8.500000+6 1.928078+05067 3 4 26 9.000000+6 1.575900+0 9.500000+6 1.238894+0 1.000000+7 9.684231-15067 3 4 27 1.050000+7 7.547956-1 1.100000+7 6.027178-1 1.150000+7 4.973963-15067 3 4 28 1.200000+7 4.217279-1 1.250000+7 3.663624-1 1.300000+7 3.249773-15067 3 4 29 1.350000+7 2.954326-1 1.400000+7 2.702777-1 1.450000+7 2.504247-15067 3 4 30 1.500000+7 2.346365-1 1.550000+7 2.215678-1 1.600000+7 2.106001-15067 3 4 31 1.650000+7 2.008833-1 1.700000+7 1.922920-1 1.750000+7 1.843579-15067 3 4 32 1.800000+7 1.771395-1 1.850000+7 1.705501-1 1.900000+7 1.643366-15067 3 4 33 1.950000+7 1.585013-1 2.000000+7 1.530825-1 5067 3 4 34 5067 3 099999 5.012600+4 1.248260+2 0 0 0 05067 3 16 1 -8.193200+6-8.193200+6 0 0 1 255067 3 16 2 25 2 5067 3 16 3 8.258840+6 0.000000+0 8.500000+6 8.033230-2 9.000000+6 4.257030-15067 3 16 4 9.500000+6 7.567020-1 1.000000+7 1.020830+0 1.050000+7 1.230100+05067 3 16 5 1.100000+7 1.376000+0 1.150000+7 1.479380+0 1.200000+7 1.552000+05067 3 16 6 1.250000+7 1.604710+0 1.300000+7 1.643160+0 1.350000+7 1.666470+05067 3 16 7 1.400000+7 1.685990+0 1.450000+7 1.696540+0 1.500000+7 1.695670+05067 3 16 8 1.550000+7 1.674610+0 1.600000+7 1.636830+0 1.650000+7 1.578720+05067 3 16 9 1.700000+7 1.502760+0 1.750000+7 1.402060+0 1.800000+7 1.286190+05067 3 16 10 1.850000+7 1.160960+0 1.900000+7 1.038510+0 1.950000+7 9.213070-15067 3 16 11 2.000000+7 8.161910-1 5067 3 16 12 5067 3 099999 5.012600+4 1.248260+2 0 0 0 05067 3 17 1 -1.392630+7-1.392630+7 0 0 1 135067 3 17 2 13 2 5067 3 17 3 1.403790+7 0.000000+0 1.450000+7 7.263400-4 1.500000+7 1.010590-25067 3 17 4 1.550000+7 3.477260-2 1.600000+7 7.582800-2 1.650000+7 1.336820-15067 3 17 5 1.700000+7 2.103460-1 1.750000+7 3.093990-1 1.800000+7 4.251600-15067 3 17 6 1.850000+7 5.489050-1 1.900000+7 6.717500-1 1.950000+7 7.885590-15067 3 17 7 2.000000+7 8.949530-1 5067 3 17 8 5067 3 099999 5.012600+4 1.248260+2 0 0 0 05067 3 22 1 -7.715010+6-7.715010+6 0 0 1 225067 3 22 2 22 2 5067 3 22 3 7.776820+6 0.000000+0 1.000000+7 2.32370-29 1.050000+7 1.02660-245067 3 22 4 1.100000+7 1.61220-21 1.150000+7 8.58590-19 1.200000+7 1.12740-165067 3 22 5 1.250000+7 5.50870-15 1.300000+7 1.30710-13 1.350000+7 1.81980-125067 3 22 6 1.400000+7 1.68930-11 1.450000+7 1.15130-10 1.500000+7 6.20000-105067 3 22 7 1.550000+7 2.770530-9 1.600000+7 1.065710-8 1.650000+7 3.627620-85067 3 22 8 1.700000+7 1.115190-7 1.750000+7 3.141280-7 1.800000+7 8.197510-75067 3 22 9 1.850000+7 1.996300-6 1.900000+7 4.560610-6 1.950000+7 9.796820-65067 3 22 10 2.000000+7 1.981980-5 5067 3 22 11 5067 3 099999 5.012600+4 1.248260+2 0 0 0 05067 3 28 1 -1.282880+7-1.282880+7 0 0 1 145067 3 28 2 14 2 5067 3 28 3 1.293160+7 0.000000+0 1.400000+7 4.86110-17 1.450000+7 7.53160-135067 3 28 4 1.500000+7 2.03810-10 1.550000+7 8.273940-9 1.600000+7 1.146830-75067 3 28 5 1.650000+7 8.707440-7 1.700000+7 4.394470-6 1.750000+7 1.644390-55067 3 28 6 1.800000+7 4.901920-5 1.850000+7 1.217270-4 1.900000+7 2.607880-45067 3 28 7 1.950000+7 4.938220-4 2.000000+7 8.470370-4 5067 3 28 8 5067 3 099999 5.012600+4 1.248260+2 0 0 0 05067 3102 1 5.550000+6 5.550000+6 0 0 1 4925067 3102 2 492 2 5067 3102 3 1.000000-5 4.526955+0 1.103037-5 4.310336+0 1.216691-5 4.104083+05067 3102 4 1.342055-5 3.907699+0 1.480336-5 3.720712+0 1.632865-5 3.542673+05067 3102 5 1.801111-5 3.373153+0 1.986691-5 3.211744+0 2.191394-5 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