51-Sb-119 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5119 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-09 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 6.85 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.46874E+01 Elastic 5.92198E+00 n,gamma 8.58031E+00 2.64131E+02 n,p 3.16526E-08 9.87598E-07 n,alpha 4.77700E-13 1.47183E-11 ---------------------------------------------------------- (*) 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= 33 (n,nt) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) 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 3.15 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= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) 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= 33 (n,nt) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) 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= 9 Isomeric branching ratios MT==102 Capture reaction Calculated with CCONE code /1/. MT=103 (n,p) reaction Calculated with CCONE code /1/. MT=107 (n,a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) 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 Sb-119 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 + 1 0.270520 7/2 + 2 0.644030 1/2 + 3 0.699880 3/2 + 4 0.970900 9/2 + 5 1.048420 7/2 + 6 1.212740 9/2 + 7 1.249740 9/2 + 8 1.327250 1/2 - 9 1.338610 3/2 + 10 1.340750 11/2 + 11 1.366340 11/2 - 12 1.407350 11/2 + 13 1.413210 3/2 - 14 1.450000 1/2 + 15 1.469000 5/2 + 16 1.482000 1/2 - 17 1.487610 3/2 + 18 1.547000 9/2 + 19 1.646500 1/2 + 20 1.660000 7/2 + 21 1.665000 3/2 + 22 1.675720 13/2 + 23 1.730000 7/2 + 24 1.749640 3/2 + 25 1.821140 1/2 + 26 1.848200 9/2 + 27 1.875320 1/2 + 28 1.970000 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 --------------------------------------------------------- Sb-120 15.300 0.000 2.188 0.524 -0.934 2.999 0.820 Sb-119 15.196 1.100 2.041 0.506 0.364 3.794 1.970 Sb-118 15.091 0.000 2.138 0.555 -1.145 3.362 1.405 Sb-117 14.987 1.109 1.858 0.533 0.245 4.065 1.624 Sn-119 14.552 1.100 1.470 0.628 -0.377 5.216 1.718 Sn-118 14.203 2.209 1.183 0.670 0.530 6.767 3.089 Sn-117 14.295 1.109 1.444 0.621 -0.210 5.000 1.770 Sn-116 14.882 2.228 1.079 0.579 1.207 5.615 3.416 In-118 15.091 0.000 2.545 0.547 -1.177 3.339 0.060 In-117 14.987 1.109 2.516 0.512 0.263 3.924 1.856 In-116 14.405 0.000 2.594 0.549 -1.031 3.166 1.253 In-115 14.777 1.119 2.462 0.551 -0.009 4.409 1.737 In-114 13.704 0.000 2.253 0.584 -1.043 3.327 1.425 In-113 14.567 1.129 2.055 0.600 -0.291 4.968 1.980 --------------------------------------------------------- * Gamma-ray strength functions for Sb-120 E1: hybrid model(GH)/10/ ER= 15.60 (MeV) EG= 4.94 (MeV) SIG= 272.15 (mb) M1: standard lorentzian model(SLO) ER= 8.31 (MeV) EG= 4.00 (MeV) SIG= 0.93 (mb) E2: standard lorentzian model(SLO) ER= 12.77 (MeV) EG= 4.67 (MeV) SIG= 2.76 (mb) References 1) O.Iwamoto, J. 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