65-Tb-152 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 6504 -----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 7.36 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.27879E+02 Elastic 6.83817E+00 n,gamma 2.20088E+02 5.70534E+03 n,p 5.52587E-01 1.42943E+01 n,alpha 2.51045E-02 6.50753E-01 ---------------------------------------------------------- (*) 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/. 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/. 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=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=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. 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. 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=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 Tb-152 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 2 - 1 0.235390 3 - 2 0.256930 1 + 3 0.277190 3 - 4 0.283290 4 - 5 0.342150 5 - 6 0.501740 8 + 7 0.600300 9 + 8 0.806100 10 + ----------------------- * 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 --------------------------------------------------------- Tb-153 18.681 0.970 3.776 0.535 -1.260 5.486 0.597 Tb-152 18.580 0.000 3.187 0.514 -1.780 3.994 0.806 Tb-151 18.479 0.977 2.658 0.521 -0.719 4.939 0.949 Tb-150 18.378 0.000 1.540 0.540 -1.591 4.017 1.897 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 Gd-148 18.176 1.973 0.477 0.441 1.578 4.148 2.082 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 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 --------------------------------------------------------- * Gamma-ray strength functions for Tb-153 E1: hybrid model(GH)/10/ ER= 12.88 (MeV) EG= 3.43 (MeV) SIG= 128.89 (mb) ER= 15.88 (MeV) EG= 5.11 (MeV) SIG= 257.79 (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= 3.85 (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)