63-Eu-152MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 6329 -----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 7.36 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.63336E+02 Elastic 6.83817E+00 Inelas 8.24473E-01 1.56425E+01 n,gamma 2.55293E+02 3.88527E+03 n,p 1.41622E-03 2.15576E-02 n,alpha 3.04368E-05 4.63327E-04 ---------------------------------------------------------- (*) 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= 9 Isomeric branching ratios MT= 22 (n,na) reaction Calculated with CCONE code /1/. 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/. ------------------------------------------------------------------ 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 Eu-152 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3 - 1 0.045600 0 - 2 0.065300 1 - 3 0.077260 3 - 4 0.078230 1 + 5 0.089610 4 - 6 0.089850 4 + 7 0.108120 5 + 8 0.109090 1 - 9 0.111450 2 - 10 0.113970 3 + 11 0.118170 2 - 12 0.120840 2 + 13 0.124540 4 + 14 0.141830 4 - 15 0.146090 3 + 16 0.147860 8 - 17 0.148740 4 + 18 0.148760 6 + 19 0.150690 4 - 20 0.158060 1 + 21 0.160880 3 + 22 0.174940 3 - 23 0.177690 3 + 24 0.178930 4 + 25 0.180630 5 - 26 0.192500 7 + 27 0.196910 3 + 28 0.199670 4 + 29 0.200750 5 - 30 0.201130 3 + 31 0.203110 1 - 32 0.203180 4 - 33 0.211610 6 + 34 0.214360 2 - 35 0.214430 4 + 36 0.219460 7 + 37 0.220800 3 - 38 0.221210 3 + 39 0.221450 2 - 40 0.224500 3 - ----------------------- * 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 --------------------------------------------------------- Eu-153 16.856 0.970 3.887 0.609 -1.715 6.248 0.841 Eu-152 18.867 0.000 4.221 0.508 -2.045 4.179 0.673 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 Sm-152 18.423 1.947 3.630 0.528 -0.083 6.232 1.879 Sm-151 19.603 0.977 3.979 0.527 -1.482 5.672 0.621 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 Pm-151 18.479 0.977 3.775 0.529 -1.130 5.333 0.898 Pm-150 18.378 0.000 4.030 0.452 -1.231 3.092 0.401 Pm-149 18.277 0.983 3.621 0.534 -1.095 5.332 0.873 Pm-148 17.695 0.000 2.869 0.458 -0.923 2.808 0.797 Pm-147 18.075 0.990 2.339 0.528 -0.610 4.883 1.310 Pm-146 17.973 0.000 1.544 0.435 -0.525 2.270 1.028 Pm-145 17.872 0.997 0.951 0.541 -0.324 4.733 1.558 --------------------------------------------------------- * Gamma-ray strength functions for Eu-153 E1: hybrid model(GH)/10/ ER= 12.64 (MeV) EG= 3.31 (MeV) SIG= 127.77 (mb) ER= 16.07 (MeV) EG= 5.23 (MeV) SIG= 255.54 (mb) M1: standard lorentzian model(SLO) ER= 7.67 (MeV) EG= 4.00 (MeV) SIG= 0.93 (mb) E2: standard lorentzian model(SLO) ER= 11.78 (MeV) EG= 4.27 (MeV) SIG= 3.61 (mb) References 1) O.Iwamoto, J. 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