48-Cd-113MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 4847 -----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 6.75 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 8.20363E+00 Elastic 5.74580E+00 Inelas 3.42614E-06 1.07724E-03 n,gamma 2.34639E+00 9.96681E+01 n,alpha 3.56650E-13 2.55831E-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= 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= 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 12.40 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= 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= 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=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= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT=103 (n,p) 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 Cd-113 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 + 1 0.263540 11/2 - 2 0.298600 3/2 + 3 0.316210 5/2 + 4 0.458630 7/2 + 5 0.522260 7/2 - 6 0.530000 7/2 + 7 0.583960 5/2 + 8 0.626600 3/2 + 9 0.638190 9/2 - 10 0.680530 3/2 + 11 0.708570 5/2 + 12 0.760000 1/2 + 13 0.815340 15/2 - 14 0.816710 7/2 + 15 0.855280 5/2 - 16 0.869810 15/2 - 17 0.878540 3/2 + 18 0.883620 1/2 + 19 0.897530 3/2 + 20 0.939790 9/2 + 21 0.960000 5/2 + 22 0.988400 1/2 + 23 0.999420 7/2 + 24 1.002870 3/2 + 25 1.007200 5/2 + 26 1.034090 3/2 + 27 1.037400 7/2 + 28 1.047650 7/2 + 29 1.049660 1/2 + 30 1.049900 3/2 + 31 1.051250 7/2 - 32 1.109320 13/2 - 33 1.124640 9/2 + 34 1.126250 3/2 + 35 1.170000 7/2 + 36 1.177720 9/2 - 37 1.177800 5/2 + 38 1.181350 7/2 + 39 1.190720 7/2 + 40 1.192090 9/2 + ----------------------- * 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 --------------------------------------------------------- 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 Pd-112 14.461 2.268 3.821 0.649 -0.220 7.256 0.349 Pd-111 15.082 1.139 4.170 0.602 -1.132 5.694 0.789 Pd-110 14.250 2.288 3.653 0.587 0.627 6.191 1.398 Pd-109 14.951 1.149 3.827 0.634 -1.387 6.110 0.883 Pd-108 13.630 2.309 3.179 0.645 0.389 6.732 2.141 Pd-107 14.379 1.160 3.188 0.616 -0.749 5.455 1.615 --------------------------------------------------------- * Gamma-ray strength functions for Cd-114 E1: hybrid model(GH)/10/ ER= 13.96 (MeV) EG= 4.00 (MeV) SIG= 84.01 (mb) ER= 16.89 (MeV) EG= 5.75 (MeV) SIG= 168.03 (mb) M1: standard lorentzian model(SLO) ER= 8.46 (MeV) EG= 4.00 (MeV) SIG= 0.98 (mb) E2: standard lorentzian model(SLO) ER= 12.99 (MeV) EG= 4.74 (MeV) SIG= 2.54 (mb) References 1) O.Iwamoto, J. 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