64-Gd-151 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 6422 -----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 7.35 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 4.73379E+01 Elastic 6.81155E+00 n,gamma 4.02305E+01 4.24906E+03 n,p 7.50690E-12 7.87390E-10 n,alpha 8.18577E-04 8.61750E-02 ---------------------------------------------------------- (*) 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 1.00 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=10 Nuclide production reactions MT= 28 (n,np) 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 Gd-151 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 7/2 - 1 0.108090 5/2 - 2 0.379300 9/2 - 3 0.395440 3/2 - 4 0.426690 5/2 - 5 0.575620 1/2 - 6 0.584780 9/2 - 7 0.587450 3/2 - 8 0.589100 5/2 + 9 0.618140 9/2 - 10 0.620600 3/2 - 11 0.670860 7/2 - 12 0.697000 5/2 + 13 0.705980 11/2 - 14 0.719460 9/2 - 15 0.784810 11/2 + 16 0.811830 3/2 - 17 0.839320 1/2 - 18 0.851900 13/2 + 19 0.882000 3/2 + 20 0.901970 13/2 - 21 0.905580 5/2 - 22 0.913000 9/2 - 23 0.913560 3/2 - 24 0.938770 7/2 - 25 0.982270 3/2 + ----------------------- * 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-152 18.580 1.947 3.285 0.489 0.435 5.540 2.117 Gd-151 18.479 0.977 2.927 0.528 -0.883 5.130 0.982 Gd-150 18.378 1.960 2.049 0.473 0.947 4.976 1.700 Gd-149 18.277 0.983 1.364 0.480 0.075 3.940 1.027 Eu-151 18.479 0.977 3.888 0.532 -1.202 5.412 0.697 Eu-150 18.378 0.000 3.178 0.432 -0.863 2.625 0.743 Eu-149 18.277 0.983 2.539 0.535 -0.804 5.107 1.135 Eu-148 18.176 0.000 1.670 0.543 -1.617 4.039 1.173 Eu-147 18.075 0.990 0.998 0.539 -0.364 4.759 1.465 Sm-150 18.270 1.960 3.252 0.524 0.113 6.055 1.927 Sm-149 19.200 0.983 2.909 0.493 -0.638 4.724 1.039 Sm-148 17.706 1.973 2.040 0.548 0.325 6.037 2.490 Sm-147 18.075 0.990 1.415 0.523 -0.308 4.586 1.642 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 --------------------------------------------------------- * Gamma-ray strength functions for Gd-152 E1: hybrid model(GH)/10/ ER= 12.99 (MeV) EG= 3.48 (MeV) SIG= 127.37 (mb) ER= 15.84 (MeV) EG= 5.09 (MeV) SIG= 254.75 (mb) M1: standard lorentzian model(SLO) ER= 7.68 (MeV) EG= 4.00 (MeV) SIG= 0.92 (mb) E2: standard lorentzian model(SLO) ER= 11.80 (MeV) EG= 4.29 (MeV) SIG= 3.74 (mb) References 1) O.Iwamoto, J. 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