68-Er-165 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 6834 -----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 7.55 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 3.61929E+01 Elastic 7.17851E+00 n,gamma 2.87464E+01 7.45805E+03 n,p 9.35490E-15 2.47274E-12 n,alpha 3.48835E-06 9.06323E-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= 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= 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= 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=104 (n,d) reaction Calculated with CCONE code /1/. MT=105 (n,t) 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 Er-165 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 - 1 0.047160 5/2 + 2 0.062670 7/2 + 3 0.077260 7/2 - 4 0.097960 9/2 + 5 0.167100 11/2 + 6 0.175820 9/2 - 7 0.237800 13/2 + 8 0.242930 3/2 - 9 0.295800 11/2 - 10 0.296130 5/2 - 11 0.297370 1/2 - 12 0.356530 3/2 - 13 0.372000 15/2 + 14 0.372710 7/2 - 15 0.384330 5/2 - 16 0.431000 1/2 + 17 0.463300 17/2 + 18 0.465000 7/2 + 19 0.467000 9/2 - 20 0.477760 5/2 - 21 0.507430 1/2 + 22 0.514000 7/2 - 23 0.519150 5/2 + 24 0.534560 3/2 + 25 0.551300 11/2 - 26 0.573000 7/2 - 27 0.589770 3/2 + 28 0.589930 1/2 - 29 0.599000 5/2 + 30 0.605510 7/2 - 31 0.608500 3/2 - 32 0.648000 7/2 + 33 0.674000 5/2 + 34 0.677900 19/2 + 35 0.684000 9/2 - 36 0.700000 7/2 + 37 0.706900 13/2 - 38 0.721000 3/2 + 39 0.730000 11/2 + 40 0.745960 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 --------------------------------------------------------- Er-166 19.983 1.863 2.179 0.529 -0.144 6.301 2.353 Er-165 19.638 0.934 2.577 0.546 -1.326 5.682 0.820 Er-164 19.784 1.874 2.671 0.523 -0.144 6.247 1.911 Er-163 20.259 0.940 3.049 0.520 -1.283 5.487 0.759 Ho-165 19.883 0.934 2.071 0.518 -0.872 5.106 1.038 Ho-164 19.784 0.000 2.263 0.392 -0.551 2.157 0.620 Ho-163 19.684 0.940 2.670 0.516 -0.966 5.159 0.965 Ho-162 19.584 0.000 2.894 0.497 -1.701 3.892 0.811 Dy-164 19.087 1.874 2.023 0.565 -0.309 6.672 1.346 Dy-163 19.223 0.940 2.172 0.572 -1.433 5.956 0.982 Dy-162 18.962 1.886 2.469 0.554 -0.270 6.555 1.634 Dy-161 19.458 0.946 2.774 0.559 -1.528 5.944 0.899 Dy-160 19.384 1.897 2.876 0.547 -0.408 6.647 1.757 Dy-159 18.411 0.952 3.164 0.564 -1.387 5.780 0.746 --------------------------------------------------------- * Gamma-ray strength functions for Er-166 E1: hybrid model(GH)/10/ ER= 12.15 (MeV) EG= 3.07 (MeV) SIG= 143.51 (mb) ER= 15.98 (MeV) EG= 5.17 (MeV) SIG= 287.02 (mb) M1: standard lorentzian model(SLO) ER= 7.46 (MeV) EG= 4.00 (MeV) SIG= 0.98 (mb) E2: standard lorentzian model(SLO) ER= 11.46 (MeV) EG= 4.12 (MeV) SIG= 4.03 (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)