50-Sn-121MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5053 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 Evaluated with CCONE code by N.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 6.88 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 7.28081E+00 Elastic 5.97997E+00 Inelas 1.72111E-08 1.26887E-03 n,gamma 1.20912E+00 4.50886E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 23.03 eV the 1/v cross section was assumed. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 5 Total reaction (except fission) reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT=103 (n,p) reaction Calculated with CCONE code /1/. MT=104 (n,d) reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. MT=106 (n,He3) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : global OMP, A.J.Koning and J.P.Delaroche/4/ deuteron: Y.Han et al./5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/4/ He-3 : Y.Xu et al./6/ alpha : M.Avrigeanu and V.Avrigeanu/7/ * Level scheme of Sn-121 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 0.006310 11/2 - 2 0.060340 1/2 + 3 0.663630 9/2 - 4 0.869250 5/2 + 5 0.908800 5/2 + 6 0.925590 7/2 + 7 0.949200 7/2 - 8 1.031000 1/2 + 9 1.067000 5/2 + 10 1.101520 3/2 + 11 1.121200 5/2 + 12 1.156000 5/2 + 13 1.157000 15/2 - 14 1.247000 13/2 - 15 1.337000 7/2 + 16 1.350000 9/2 + 17 1.403500 5/2 + 18 1.432000 13/2 + 19 1.450000 7/2 + 20 1.498000 9/2 + 21 1.537000 13/2 + 22 1.571000 7/2 + 23 1.653200 1/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/8/) Energy dependent parameters of Mengoni-Nakajima/9/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Sn-122 15.509 2.173 0.163 0.624 0.868 6.235 3.082 Sn-121 14.811 1.091 0.975 0.634 -0.357 5.265 1.653 Sn-120 14.310 2.191 0.889 0.677 0.524 6.815 2.976 Sn-119 14.552 1.100 1.470 0.628 -0.377 5.216 1.718 In-121 15.405 1.091 1.390 0.497 0.528 3.574 1.614 In-120 15.300 0.000 1.931 0.550 -1.099 3.316 0.070 In-119 15.196 1.100 2.153 0.484 0.507 3.524 1.979 In-118 15.091 0.000 2.545 0.547 -1.177 3.339 0.060 Cd-120 15.300 2.191 1.699 0.549 1.162 5.436 2.034 Cd-119 15.196 1.100 2.488 0.609 -0.721 5.418 0.656 Cd-118 15.091 2.209 2.344 0.493 1.529 4.762 1.916 Cd-117 14.711 1.109 2.930 0.656 -1.239 6.120 0.779 Cd-116 14.882 2.228 2.717 0.631 0.183 6.833 2.910 Cd-115 15.530 1.119 3.120 0.550 -0.390 4.789 1.478 --------------------------------------------------------- * Gamma-ray strength functions for Sn-122 E1: hybrid model(GH)/10/ ER= 15.54 (MeV) EG= 4.90 (MeV) SIG= 275.88 (mb) M1: standard lorentzian model(SLO) ER= 8.27 (MeV) EG= 4.00 (MeV) SIG= 0.91 (mb) E2: standard lorentzian model(SLO) ER= 12.70 (MeV) EG= 4.65 (MeV) SIG= 2.63 (mb) References 1) O.Iwamoto, J. 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