41-Nb- 95 EVAL-Sep18 ichihara DIST-DEC21 20200318 ----JENDL-5 MATERIAL 4131 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2018-08 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 : 25 eV - 500 keV The unresolved resonance parameters were calculated using the ASREP code/1/. 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 1.278E+01 Elastic 5.736E+00 n,gamma 7.003E+00 4.488E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections Below 25 eV, the capture and elastic scattering cross sections were taken from JENDL-4.0. 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= 41 (n,2np) 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= 41 (n,2np) 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= 41 (n,2np) MT=102 Capture MT=103 (n,p) MT=104 (n,d) MT=105 (n,t) MT=107 (n,a) MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /2/. 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/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials alpha : O.F.Lemos/3/ deuteron: J.M.Lohr and W.Haeberli/4/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/5/ neutron : A.J.Koning and J.P.Delaroche/6/ proton : A.J.Koning and J.P.Delaroche/6/ triton : F.D.Becchetti Jr. and G.W.Greenlees/5/ * Level scheme of Nb-95 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 9/2 + 1 0.235690 1/2 - 2 0.724200 7/2 + 3 0.730000 5/2 + 4 0.756730 7/2 + 5 0.799000 3/2 - 6 0.805000 7/2 + 7 0.824700 13/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/7/) Energy dependent parameters of Mengoni-Nakajima/8/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Nb-96 12.360 0.000 1.861 0.729 -1.864 4.742 0.233 Nb-95 11.759 1.231 1.721 0.956 -2.918 9.376 0.825 Nb-94 12.822 0.000 0.581 0.720 -1.513 4.482 1.023 Nb-93 11.549 1.244 0.104 1.006 -2.466 9.756 0.810 Zr-95 11.637 1.231 1.508 0.704 0.041 5.134 1.956 Zr-94 12.185 2.475 1.414 0.767 0.469 7.586 1.671 Zr-93 12.414 1.244 0.476 0.821 -1.060 7.126 1.018 Zr-92 11.704 2.502 -0.006 0.851 0.532 8.230 2.820 Y-94 12.145 0.000 1.472 0.449 0.142 1.141 0.622 Y-93 11.549 1.244 1.580 0.750 -0.351 5.778 1.309 Y-92 11.929 0.000 0.366 0.548 -0.011 1.793 0.992 Y-91 11.338 1.258 0.165 0.854 -0.617 6.824 1.580 Y-90 10.454 0.000 -1.297 0.866 -0.784 4.548 0.954 --------------------------------------------------------- * Gamma-ray strength functions for Nb-96 E1: generalized lorentzian model(GLO)/9/ ER= 14.76 (MeV) EG= 4.45 (MeV) SIG= 65.73 (mb) ER= 17.42 (MeV) EG= 6.10 (MeV) SIG= 131.47 (mb) M1: standard lorentzian model(SLO) ER= 8.95 (MeV) EG= 4.00 (MeV) SIG= 0.76 (mb) E2: standard lorentzian model(SLO) ER= 13.76 (MeV) EG= 4.96 (MeV) SIG= 2.10 (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) Lemos, O.F.: Orsay, Series A ,No.136 (1972). 4) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974). 5) Becchetti Jr., F.D. and Greenlees, G.W.: Ann. Rept. J.H. Williams Lab., Univ. Minnesota (1969). 6) Koning, A.J. and Delaroche, J.P.: Nucl. Phys. A713, 231 (2003). 7) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446 (1965). 8) Mengoni, A. and Nakajima, Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 9) Kopecky, J. and Uhl, M.: Phys. Rev., C41, 1941 (1990).