49-In-111 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 4919 -----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 6.71 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.04820E+01 Elastic 5.68631E+00 n,gamma 1.45717E+01 2.91961E+02 n,p 7.78154E-08 1.59046E-06 n,alpha 1.99800E-10 4.01529E-09 ---------------------------------------------------------- (*) 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 2.54 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/. MT=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) 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= 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=106 (n,He3) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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-111 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 9/2 + 1 0.536990 1/2 - 2 0.802920 3/2 - 3 1.101800 5/2 + 4 1.152850 11/2 + 5 1.187620 1/2 + 6 1.217510 5/2 + 7 1.279690 5/2 - 8 1.344740 3/2 + 9 1.350600 9/2 - 10 1.401160 13/2 + 11 1.461700 13/2 - 12 1.500450 7/2 + 13 1.542620 5/2 + 14 1.610080 9/2 + 15 1.671230 5/2 - 16 1.752600 9/2 + 17 1.831570 7/2 - 18 1.845980 7/2 - 19 1.849390 3/2 - 20 1.866840 5/2 + 21 1.914880 7/2 + 22 1.917390 9/2 + 23 1.919000 3/2 + 24 1.935400 3/2 + 25 1.969630 5/2 + 26 1.994640 15/2 + 27 2.002620 5/2 + 28 2.032180 11/2 + 29 2.034580 5/2 - 30 2.067010 3/2 - 31 2.082450 5/2 + 32 2.085000 1/2 + 33 2.090110 5/2 + 34 2.107020 7/2 + 35 2.112250 11/2 + 36 2.142070 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 --------------------------------------------------------- In-112 14.461 0.000 1.669 0.561 -0.930 3.130 1.117 In-111 14.356 1.139 1.283 0.610 -0.082 4.846 2.142 In-110 14.250 0.000 0.827 0.599 -0.961 3.383 1.118 In-109 14.144 1.149 0.212 0.633 0.129 4.811 1.817 Cd-111 14.785 1.139 2.384 0.663 -1.167 6.158 1.392 Cd-110 14.250 2.288 1.723 0.685 0.182 7.265 2.706 Cd-109 15.130 1.149 1.602 0.632 -0.677 5.605 1.318 Cd-108 14.038 2.309 0.685 0.741 0.068 7.845 3.171 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 Ag-107 13.932 1.160 1.968 0.651 -0.552 5.502 1.449 Ag-106 13.826 0.000 1.242 0.712 -2.061 5.083 1.225 --------------------------------------------------------- * Gamma-ray strength functions for In-112 E1: hybrid model(GH)/10/ ER= 14.79 (MeV) EG= 4.46 (MeV) SIG= 82.67 (mb) ER= 16.44 (MeV) EG= 5.46 (MeV) SIG= 165.34 (mb) M1: standard lorentzian model(SLO) ER= 8.51 (MeV) EG= 4.00 (MeV) SIG= 0.98 (mb) E2: standard lorentzian model(SLO) ER= 13.07 (MeV) EG= 4.77 (MeV) SIG= 2.68 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 4) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 5) Y.Han et al., Phys. Rev. C 74,044615(2006) 6) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 7) M.Avrigeanu and V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 8) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 9) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 10) S.Goriely, Phys. Lett. B436, 10 (1998)