41-Nb- 92MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 4123 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 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 6.35 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 6.92942E+00 Elastic 5.09976E+00 Inelas 1.39053E-05 1.25129E-02 n,gamma 1.68166E+00 3.17453E+01 n,p 4.48916E-02 8.62916E-01 n,alpha 2.29498E-03 4.91824E-02 ---------------------------------------------------------- (*) 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= 22 (n,na) 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 34.97 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=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MT=116 (n,pt) 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= 22 (n,na) 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MT=116 (n,pt) 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= 22 (n,na) 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. 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. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT==102 Capture reaction Calculated with CCONE code /1/. MT=107 (n,a) reaction Calculated with CCONE code /1/. 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= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. MT=106 (n,He3) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=116 (n,pt) 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 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 + 8 0.975000 2 - 9 1.089400 1 + 10 1.150000 1 - 11 1.310800 2 - 12 1.323800 2 - 13 1.345500 2 + 14 1.374000 3 - 15 1.374100 4 - 16 1.406200 5 + 17 1.410300 5 + 18 1.415000 3 - 19 1.422700 4 - 20 1.467900 4 + 21 1.472800 4 + 22 1.481300 1 + 23 1.524000 5 - 24 1.553900 1 - 25 1.565700 4 + 26 1.607000 4 + 27 1.632700 4 + 28 1.642000 2 - 29 1.650300 5 + 30 1.666600 1 - 31 1.678100 1 - 32 1.717000 4 - 33 1.730000 5 - 34 1.738200 3 + 35 1.768030 4 + 36 1.779000 6 - 37 1.816000 6 - 38 1.831000 4 + 39 1.832000 7 - 40 1.851000 7 - ----------------------- * 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 12.431 1.244 0.104 0.840 -1.094 7.355 2.507 Nb-92 12.322 0.000 -1.408 0.763 -0.863 4.205 2.335 Nb-91 12.213 1.258 -1.938 0.849 -0.007 6.653 2.793 Zr-92 11.759 2.502 -0.005 0.866 0.343 8.531 4.082 Zr-91 11.995 1.258 -1.232 0.749 0.561 5.102 3.636 Zr-90 12.104 2.530 -1.955 0.687 2.438 5.262 4.946 Zr-89 11.995 1.272 -0.594 0.750 0.296 5.366 3.214 Y-91 12.213 1.258 0.165 0.452 1.586 1.544 2.960 Y-90 10.563 0.000 -1.296 0.898 -1.083 5.141 3.098 Y-89 11.995 1.272 -1.866 0.844 0.111 6.445 4.105 Y-88 11.886 0.000 -0.510 0.822 -1.582 5.205 2.055 Y-87 11.777 1.287 0.684 0.774 -0.332 6.036 3.308 --------------------------------------------------------- * Gamma-ray strength functions for Nb-93 E1: hybrid model(GH)/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= 1.12 (mb) E2: standard lorentzian model(SLO) ER= 13.91 (MeV) EG= 4.99 (MeV) SIG= 2.15 (mb) References 1) O.Iwamoto, J. 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