83-Bi-203 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 8307 -----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 8.03 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.23236E+01 Elastic 8.12120E+00 n,gamma 4.07117E+00 2.67013E+02 n,p 2.01067E-04 1.31534E-02 n,alpha 1.22072E-06 7.96095E-05 ---------------------------------------------------------- (*) 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= 33 (n,nt) 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 5.70 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= 33 (n,nt) 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= 33 (n,nt) 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= 9 Isomeric branching ratios MT=103 (n,p) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /1/. MT= 17 (n,3n) 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=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 Bi-203 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 9/2 - 1 0.883370 11/2 - 2 0.893510 5/2 - 3 0.908630 7/2 - 4 0.932500 13/2 - 5 1.090950 7/2 - 6 1.098120 1/2 + 7 1.123880 9/2 - 8 1.231210 9/2 - 9 1.247790 15/2 - 10 1.248550 13/2 - 11 1.277210 9/2 - 12 1.299100 7/2 - 13 1.312930 3/2 + 14 1.352830 7/2 - 15 1.408800 13/2 - 16 1.479300 9/2 - 17 1.484100 13/2 - 18 1.488130 5/2 + 19 1.494400 15/2 - 20 1.499090 17/2 - 21 1.561100 13/2 + 22 1.575500 17/2 - 23 1.609980 5/2 - 24 1.672700 15/2 - 25 1.714400 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 --------------------------------------------------------- Bi-204 23.713 0.000 -4.969 0.538 -0.550 3.570 0.806 Bi-203 23.616 0.842 -4.190 0.537 0.044 4.650 1.714 Bi-202 23.519 0.000 -3.451 0.514 -0.817 3.582 1.814 Bi-201 23.422 0.846 -2.780 0.376 0.878 2.367 1.927 Pb-203 23.616 0.842 -5.869 0.645 -0.382 6.634 1.536 Pb-202 23.519 1.689 -5.123 0.605 0.581 6.680 2.516 Pb-201 23.422 0.846 -4.256 0.543 0.046 4.708 1.186 Pb-200 23.325 1.697 -3.646 0.376 1.877 3.000 2.154 Pb-199 23.228 0.851 -2.751 0.429 0.586 3.084 1.682 Tl-202 23.519 0.000 -5.850 0.559 -0.361 3.582 2.150 Tl-201 23.422 0.846 -4.911 0.518 0.488 3.959 2.343 Tl-200 23.325 0.000 -4.344 0.481 -0.244 2.623 0.754 Tl-199 23.228 0.851 -3.524 0.465 0.517 3.435 2.032 Tl-198 23.131 0.000 -2.879 0.414 -0.131 1.961 0.865 Tl-197 23.033 0.855 -2.174 0.502 -0.154 4.469 2.073 --------------------------------------------------------- * Gamma-ray strength functions for Bi-204 E1: hybrid model(GH)/10/ ER= 13.78 (MeV) EG= 3.90 (MeV) SIG= 578.39 (mb) M1: standard lorentzian model(SLO) ER= 6.96 (MeV) EG= 4.00 (MeV) SIG= 1.09 (mb) E2: standard lorentzian model(SLO) ER= 10.70 (MeV) EG= 3.66 (MeV) SIG= 5.49 (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)