41-Nb- 92 EVAL-Sep18 ichihara DIST-DEC21 20200318 ----JENDL-5 MATERIAL 4122 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2018-09 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 : 70 eV - 300 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 7.074E+00 Elastic 5.330E+00 n,gamma 1.726E+00 2.030E+01 n,p 8.922E-07 6.580E-03 n,a 1.170E-03 2.059E-02 ---------------------------------------------------------- (*) 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= 22 (n,na) 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= 41 (n,2np) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Thermal cross section 1.7257 b (0.0253 eV) was applied. /3/ 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=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. MT=111 (n,2p) cross section Calculated with CCONE code /2/. MT=116 (n,pt) 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= 22 (n,na) 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= 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=111 (n,2p) reaction Calculated with CCONE code /2/. MT=116 (n,pt) 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=750-799 (n,He3) 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= 22 (n,na) MT= 28 (n,np) MT= 32 (n,nd) MT= 41 (n,2np) MT=102 Capture MT=103 (n,p) MT=104 (n,d) MT=105 (n,t) MT=106 (n,He3) MT=107 (n,a) MT=111 (n,2p) MT=116 (n,pt) MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /2/. MT=107 (n,a) reaction Calculated with CCONE code /2/. 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=106 (n,He3) reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. MT=116 (n,pt) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials alpha : V.Avrigeanu et al./4/ deuteron: J.M.Lohr and W.Haeberli/5/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/6/ neutron : A.J.Koning and J.P.Delaroche/7/ proton : A.J.Koning and J.P.Delaroche/7/ triton : F.D.Becchetti Jr. and G.W.Greenlees/6/ * Level scheme of Nb-92 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 7 + 1 0.135500 2 + 2 0.225800 2 - 3 0.285700 3 + 4 0.357440 5 + 5 0.389800 3 - 6 0.480280 4 + 7 0.501260 6 + ----------------------- * 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 --------------------------------------------------------- Nb-93 11.549 1.244 0.104 1.006 -2.466 9.756 0.810 Nb-92 11.929 0.000 -1.409 0.928 -2.165 6.882 0.501 Nb-91 11.338 1.258 -1.938 0.984 -0.766 8.521 1.313 Zr-92 11.704 2.502 -0.006 0.851 0.532 8.230 2.820 Zr-91 11.890 1.258 -1.233 0.823 0.027 6.228 2.395 Zr-90 11.748 2.530 -1.956 0.846 1.531 7.511 2.739 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 Y-89 11.127 1.272 -1.867 0.721 1.290 3.964 2.622 Y-88 11.495 0.000 -0.510 0.852 -1.643 5.422 0.766 --------------------------------------------------------- * Gamma-ray strength functions for Nb-93 E1: generalized lorentzian model(GLO)/10/ ER= 16.56 (MeV) EG= 5.54 (MeV) SIG= 189.73 (mb) M1: standard lorentzian model(SLO) ER= 9.05 (MeV) EG= 4.00 (MeV) SIG= 0.76 (mb) E2: standard lorentzian model(SLO) ER= 13.91 (MeV) EG= 4.99 (MeV) SIG= 2.15 (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) Shibata, K.: J. Nucl. Sci. Technol., 51, 425 (2014). 4) Avrigeanu, V., et al.: Report OUNP-94-02 (1994) , Phys. Rev., C49, 2136 (1994). 5) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974). 6) Becchetti Jr., F.D. and Greenlees, G.W.: Ann. Rept. J.H. Williams Lab., Univ. Minnesota (1969). 7) Koning, A.J. and Delaroche, J.P.: Nucl. Phys. A713, 231 (2003). 8) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446 (1965). 9) Mengoni, A. and Nakajima, Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 10) Kopecky, J. and Uhl, M.: Phys. Rev. C 41, 1941 (1990)