82-Pb-205 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210507 ----JENDL-5 MATERIAL 8228 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-05 Evaluated with CCONE code by N.Iwamoto 21-11 revised by O.Iwamoto (MF8/MT18) added MF= 1 General information MT=451 Descriptive data and directory MT=452 Average number of neutrons per fission MT=456 Average number of prompt neutrons per fission MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 9.7 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.65548E+01 Elastic 1.18534E+01 n,gamma 4.50180E+00 7.08335E+00 n,alpha 1.01630E-10 2.47734E-10 ---------------------------------------------------------- (*) 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= 18 Fission 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 cross section of 1/v shape was adopted in the resonance region. 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/. The cross section of 1/v shape was adopted in the resonance region. 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= 18 Fission 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=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= 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. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning et al./2/ proton : A.J.Koning and J.P.Delaroche/3/ deuteron: Y.Han et al./4/ triton : A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al. /5/ alpha : V.Avrigeanu/6/ * Level scheme of Pb-205 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 - 1 0.002330 1/2 - 2 0.262830 3/2 - 3 0.576190 3/2 - 4 0.703430 7/2 - 5 0.761430 5/2 - 6 0.803380 1/2 - 7 0.987630 9/2 - 8 0.996480 1/2 - 9 1.013850 13/2 + 10 1.043740 7/2 - 11 1.264730 5/2 - 12 1.374170 1/2 - 13 1.499140 9/2 - 14 1.541000 1/2 + 15 1.575340 9/2 - 16 1.593560 9/2 + 17 1.614320 7/2 - 18 1.618000 1/2 - 19 1.697450 17/2 + 20 1.704980 7/2 - 21 1.748400 1/2 - 22 1.756400 9/2 + 23 1.758630 9/2 + 24 1.764370 7/2 - 25 1.775800 7/2 - 26 1.812050 1/2 - 27 1.817990 1/2 + 28 1.831000 9/2 + 29 1.838000 1/2 + 30 1.842060 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 --------------------------------------------------------- Pb-206 23.779 1.672 -8.393 0.754 0.568 10.482 3.279 Pb-205 26.229 0.838 -7.563 0.676 -0.501 8.286 1.842 Pb-204 23.580 1.680 -6.701 0.739 -0.314 10.333 2.627 Pb-203 23.942 0.842 -5.869 0.673 -0.831 7.670 1.262 Tl-205 22.738 0.838 -7.918 0.781 -0.626 10.200 2.220 Tl-204 24.987 0.000 -7.398 0.715 -1.641 8.369 0.764 Tl-203 22.546 0.842 -6.375 0.730 -0.864 8.589 1.935 Tl-202 23.193 0.000 -5.850 0.564 -0.341 3.582 2.150 Tl-201 22.353 0.846 -4.911 0.564 0.309 4.553 2.343 Hg-204 23.580 1.680 -7.232 0.730 0.170 9.780 2.761 Hg-203 23.942 0.842 -6.530 0.674 -0.466 7.413 1.488 Hg-202 26.229 1.689 -5.927 0.654 -0.338 9.007 1.991 Hg-201 23.749 0.846 -5.262 0.423 1.097 2.363 2.478 Hg-200 23.181 1.697 -4.720 0.662 -0.217 8.262 2.491 Hg-199 23.556 0.851 -4.088 0.628 -1.024 6.861 0.969 Hg-198 22.981 1.706 -3.417 0.599 0.055 7.000 2.400 --------------------------------------------------------- * Gamma-ray strength functions for Pb-206 E1: standard lorentzian model(SLO) ER= 5.40 (MeV) EG= 0.50 (MeV) SIG= 20.00 (mb) ER= 7.20 (MeV) EG= 1.10 (MeV) SIG= 38.00 (mb) ER= 12.80 (MeV) EG= 3.50 (MeV) SIG= 244.00 (mb) ER= 14.00 (MeV) EG= 3.00 (MeV) SIG= 451.40 (mb) M1: standard lorentzian model(SLO) ER= 6.94 (MeV) EG= 4.00 (MeV) SIG= 7.12 (mb) E2: standard lorentzian model(SLO) ER= 10.67 (MeV) EG= 3.64 (MeV) SIG= 5.34 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) A.J.Koning et al., Nucl. Sci. Eng., 156, 357 (2007). 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 6) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 7) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 8) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994)