49-In-114MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 4929 -----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 6.76 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.13166E+01 Elastic 5.77540E+00 Inelas 7.03081E-05 2.83321E-01 n,gamma 1.53175E+01 3.34036E+02 n,p 1.23467E-06 2.90567E-05 n,alpha 3.13019E-09 6.85140E-08 ---------------------------------------------------------- (*) 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= 24 (n,2na) 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 2.12 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= 24 (n,2na) 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= 24 (n,2na) 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=107 (n,a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 4 (n,n') 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= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT=104 (n,d) 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 In-114 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1 + 1 0.190270 5 + 2 0.221060 4 + 3 0.287730 2 + 4 0.497160 5 + 5 0.501950 8 - 6 0.536300 7 - 7 0.574420 6 - 8 0.600350 3 - 9 0.628030 3 + 10 0.641740 9 - 11 0.641750 7 + 12 0.687530 8 + 13 0.692930 2 - 14 0.696380 5 - 15 0.725100 3 + 16 0.728530 4 + 17 0.775340 4 + 18 0.824990 2 + 19 0.835660 4 - 20 0.906120 2 - 21 0.909500 6 + 22 0.970580 4 + 23 1.003130 5 + 24 1.006410 4 - 25 1.018670 4 - 26 1.019750 7 + 27 1.032050 3 - 28 1.037180 4 + 29 1.044900 6 + 30 1.047210 3 + 31 1.059490 2 + 32 1.062530 3 + 33 1.068600 4 - 34 1.074030 2 + 35 1.082700 3 - 36 1.095100 4 - 37 1.111800 2 + 38 1.139100 5 + 39 1.155360 4 + 40 1.164280 8 + ----------------------- * 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 --------------------------------------------------------- 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 In-112 14.461 0.000 1.669 0.561 -0.930 3.130 1.117 Cd-114 14.487 2.248 2.747 0.632 0.314 6.722 2.637 Cd-113 14.927 1.129 2.941 0.666 -1.471 6.413 1.505 Cd-112 14.063 2.268 2.419 0.710 -0.302 7.759 3.205 Cd-111 14.785 1.139 2.384 0.663 -1.167 6.158 1.392 Ag-113 14.567 1.129 3.744 0.687 -1.874 6.793 0.044 Ag-112 14.461 0.000 3.800 0.625 -2.190 4.597 0.018 Ag-111 14.356 1.139 3.581 0.642 -1.155 5.923 1.377 Ag-110 14.256 0.000 3.379 0.602 -1.743 4.067 0.986 Ag-109 14.144 1.149 2.964 0.669 -1.179 6.126 1.091 Ag-108 13.612 0.000 2.517 0.681 -2.085 4.813 1.034 --------------------------------------------------------- * Gamma-ray strength functions for In-115 E1: hybrid model(GH)/10/ ER= 15.75 (MeV) EG= 5.03 (MeV) SIG= 256.05 (mb) M1: standard lorentzian model(SLO) ER= 8.43 (MeV) EG= 4.00 (MeV) SIG= 0.95 (mb) E2: standard lorentzian model(SLO) ER= 12.96 (MeV) EG= 4.73 (MeV) SIG= 2.63 (mb) References 1) O.Iwamoto, J. 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