40-Zr- 95 EVAL-Sep18 ichihara DIST-DEC21 20200318 ----JENDL-5 MATERIAL 4040 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2018-06 Evaluated with CCONE code by ichihara 2020-10 Energies of discrete primary photons were corrected. 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Unresolved resonance region : 125 eV - 100 keV The unresolved resonance parameters were calculated using the ASREP code/1/. The parameter values D0 = 2.5e+2 eV, S0 = 3.5e-5, S1 = 4.8e-4, R = 6.63 fm, Gg = 1.5e-1 eV were employed./2,3,4/ The parameters should be used only for the self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 6.353E+00 Elastic 5.332E+00 n,gamma 1.000E+00 5.516E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. MT= 2 Elastic scattering cross section Calculated with CCONE code /2/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 33 (n,nt) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary neutrons MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 33 (n,nt) reaction Calculated with CCONE code /2/. MT=51-91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. MF= 8 Information on decay data MT=4 (n,n') MT= 16 (n,2n) MT= 17 (n,3n) MT= 22 (n,na) MT= 24 (n,2na) MT= 28 (n,np) MT= 32 (n,nd) MT= 33 (n,nt) MT=102 Capture MT=103 (n,p) MT=104 (n,d) MT=105 (n,t) MT=107 (n,a) ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials alpha : V.Avrigeanu et al./5/ deuteron: J.M.Lohr and W.Haeberli/6/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/7/ neutron : S.Kunieda et al./3/ proton : S.Kunieda et al./3/ triton : F.D.Becchetti Jr. and G.W.Greenlees/7/ * Level scheme of Zr-95 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 + 1 0.953970 1/2 + 2 1.140000 5/2 + 3 1.323800 3/2 + 4 1.618350 3/2 + 5 1.624700 5/2 + 6 1.676320 7/2 + 7 1.721500 5/2 + 8 1.792200 9/2 + 9 1.892660 3/2 + 10 1.903970 5/2 + 11 1.940240 3/2 - 12 1.955920 5/2 + 13 2.021600 11/2 - 14 2.120000 9/2 + 15 2.250000 7/2 + 16 2.253700 1/2 + 17 2.293700 3/2 + 18 2.317000 3/2 + 19 2.372270 3/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/8/) Energy dependent parameters of Mengoni-Nakajima/4/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Zr-96 12.403 2.449 2.144 0.706 0.688 6.950 1.897 Zr-95 11.637 1.231 1.508 0.728 -0.039 5.469 2.372 Zr-94 12.185 2.475 1.414 0.767 0.469 7.586 2.151 Zr-93 12.414 1.244 0.476 0.795 -0.671 6.671 2.458 Y-95 11.759 1.231 2.582 0.476 1.182 2.752 2.021 Y-94 13.100 0.000 1.472 0.385 0.207 0.774 0.724 Y-93 11.549 1.244 1.580 0.750 -0.351 5.778 1.309 Y-92 12.600 0.000 0.366 0.732 -1.458 4.487 0.310 Sr-93 12.762 1.244 1.857 0.620 0.180 4.623 1.238 Sr-92 11.967 2.502 1.541 0.747 0.736 7.218 2.088 Sr-91 12.543 1.258 0.607 0.671 0.243 4.893 1.368 Sr-90 11.748 2.530 0.139 0.813 0.818 7.712 2.674 --------------------------------------------------------- * Gamma-ray strength functions for Zr-96 E1: standard lorentzian model(SLO) ER= 14.36 (MeV) EG= 4.22 (MeV) SIG= 65.30 (mb) ER= 17.72 (MeV) EG= 6.30 (MeV) SIG= 130.59 (mb) M1: standard lorentzian model(SLO) ER= 8.95 (MeV) EG= 4.00 (MeV) SIG= 3.98 (mb) E2: standard lorentzian model(SLO) ER= 13.76 (MeV) EG= 4.96 (MeV) SIG= 2.00 (mb) References 1) Kikuchi, Y., et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 2) Iwamoto, O.: J. Nucl. Sci. Technol., 44, 687 (2007). 3) Kunieda, S., et al.: J. Nucl. Sci. Technol., 44, 838 (2007). 4) Mengoni, A. and Nakajima, Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 5) Avrigeanu, V., et al.: Report OUNP-94-02 (1994) , Phys. Rev., C49, 2136 (1994). 6) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974). 7) Becchetti Jr., F.D. and Greenlees, G.W.: Ann. Rept. J.H. Williams Lab., Univ. Minnesota (1969). 8) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446 (1965).