64-Gd-147 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 6410 -----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 7.29 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.94518E+01 Elastic 6.70444E+00 n,gamma 1.25122E+01 1.98854E+03 n,p 1.02295E-03 1.62283E-01 n,alpha 2.45299E-02 3.87641E+00 ---------------------------------------------------------- (*) 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= 44 (n,n2p) 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 1.77 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=108 (n,2a) 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/. MT=115 (n,pd) cross section Calculated with CCONE code /1/. MT=116 (n,pt) 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= 44 (n,n2p) 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=108 (n,2a) 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=115 (n,pd) reaction Calculated with CCONE code /1/. MT=116 (n,pt) 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= 44 (n,n2p) 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=108 (n,2a) 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. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT= 22 (n,na) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 17 (n,3n) 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 Gd-147 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 7/2 - 1 0.997100 13/2 + 2 1.152560 3/2 - 3 1.235600 7/2 - 4 1.292460 1/2 + 5 1.347100 13/2 + 6 1.397000 9/2 - 7 1.412190 3/2 + 8 1.509100 11/2 - 9 1.594100 11/2 + 10 1.627880 5/2 + 11 1.628300 7/2 + 12 1.643000 9/2 + 13 1.699520 3/2 + 14 1.701610 11/2 + 15 1.759850 1/2 + 16 1.775700 11/2 - 17 1.797200 9/2 - 18 1.847120 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 --------------------------------------------------------- Gd-148 18.176 1.973 0.477 0.441 1.578 4.148 2.082 Gd-147 18.075 0.990 -0.393 0.497 0.386 3.740 1.847 Gd-146 17.973 1.986 -1.324 0.595 0.821 6.049 3.639 Gd-145 17.872 0.997 -0.427 0.583 -0.324 5.071 1.667 Eu-147 18.075 0.990 0.998 0.539 -0.364 4.759 1.465 Eu-146 17.973 0.000 -0.043 0.477 -0.513 2.509 0.648 Eu-145 17.872 0.997 -0.797 0.488 0.591 3.453 2.028 Eu-144 17.770 0.000 -0.367 0.584 -1.333 4.087 1.294 Sm-146 17.973 1.986 0.585 0.532 0.839 5.509 2.737 Sm-145 15.992 0.997 -0.217 0.588 0.077 4.563 2.193 Sm-144 17.770 2.000 -1.080 0.537 1.323 5.078 2.976 Sm-143 17.669 1.003 -0.247 0.402 1.009 2.451 2.070 Sm-142 17.567 2.014 0.269 0.524 1.111 5.206 2.656 Sm-141 17.465 1.011 1.219 0.513 -0.023 4.243 1.345 --------------------------------------------------------- * Gamma-ray strength functions for Gd-148 E1: hybrid model(GH)/10/ ER= 14.85 (MeV) EG= 4.50 (MeV) SIG= 370.19 (mb) M1: standard lorentzian model(SLO) ER= 7.75 (MeV) EG= 4.00 (MeV) SIG= 0.90 (mb) E2: standard lorentzian model(SLO) ER= 11.91 (MeV) EG= 4.33 (MeV) SIG= 3.80 (mb) References 1) O.Iwamoto, J. 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