80-Hg-199 EVAL-Oct15 K.Shibata (JAEA) JNST 53, 1595 (2016) DIST-DEC21 20180723 ----JENDL-5 MATERIAL 8034 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2015-03 Evaluated with CCONE code by K.Shibata (JAEA) /1/ 2018-07 Activation cross sections and MF=3,6/MT=600-849 added. 2020-10 Energies of discrete primary photons were corrected. 21-11 above 20 MeV, JENDL-4.0/HE 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 Resolved and unresolved resonance parameters Resolved resonance region: 1.0e-5 eV - 968 eV Parameters were taken from the JENDL-4.0 evaluation, which is based on the compilation of Mughabghab /2/. Unresolved resonance region: 968 eV - 100 keV The parameters were obtained by fitting to the total and caputure cross sections calculated from CCONE /3/. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- LFS 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 2.2169E+03 Elastic 6.6700E+01 n,gamma 2.1502E+03 4.3939E+02 n,alpha 6.4813E-05 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. MT= 2 Elastic scattering cross section Calculated with CCONE code /3/. Obtained by subtracting non-elastic cross sctions from total cross sections. Below 968 eV, the cross sections should be calculated from resolved resonance parameters. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 17 (n,3n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. Below 968 eV, the cross sections should be calculated from resolved resonance parameters. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. 1/v cross sections were assumed below 968 eV. The thermal (n,a) cross section was obtained by multiplying the thermal capture cross sections by the ratio of the CCONE calculations ( sig_na / sig_capture) at 0.0253 eV. MF= 4 Angular distributions of secondary neutrons MT= 2 Elastic scattering Calculated with CCONE code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. MF= 8 Information on decay data MT=4 (n,n') MT= 16 (n,2n) MT= 17 (n,3n) 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) MF= 9 Isomeric branching ratios MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT=103 (n,p) reaction Calculated with CCONE code /3/. MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT=104 (n,d) reaction Calculated with CCONE code /3/. MT=105 (n,t) reaction Calculated with CCONE code /3/. MT=106 (n,He3) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * 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 : S. Kunieda et al./7/ proton : A.J.Koning and J.P.Delaroche/8/ triton : F.D.Becchetti Jr. and G.W.Greenlees/6/ * Level scheme of Hg-199 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 - c 1 0.158380 5/2 - d 2 0.208210 3/2 - c 3 0.403510 3/2 - d 4 0.413840 5/2 - c 5 0.455460 1/2 - 6 0.492300 3/2 - 7 0.532480 13/2 + 8 0.638000 5/2 - 9 0.667000 5/2 - 10 0.667400 3/2 + 11 0.695000 1/2 - 12 0.699000 7/2 - c 13 0.711400 3/2 + 14 0.736000 3/2 - 15 0.750400 3/2 - 16 0.759000 5/2 - 17 0.822000 5/2 - ----------------------- c: coupled-channel calc. d: DWBA calc. * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Hg-200 23.325 1.697 -4.720 0.629 0.176 7.391 2.274 Hg-199 23.228 0.851 -4.089 0.660 -1.381 7.625 0.822 Hg-198 23.131 1.706 -3.418 0.606 -0.077 7.236 2.110 Hg-197 23.033 0.855 -2.645 0.581 -0.901 6.006 0.904 Au-199 23.228 0.851 -3.848 0.578 -0.431 5.576 1.159 Au-198 23.131 0.000 -3.422 0.599 -1.682 5.338 0.812 Au-197 23.033 0.855 -2.659 0.538 -0.378 5.039 1.231 Pt-197 23.033 0.855 -2.496 0.591 -1.093 6.292 0.965 Pt-196 22.936 1.714 -2.151 0.583 -0.239 7.037 1.992 Pt-195 22.839 0.859 -1.456 0.585 -1.366 6.400 0.875 --------------------------------------------------------- * Gamma-ray strength functions for Hg-200 E1: modified lorentzian model(MLO1)/11/ ER= 13.85 (MeV) EG= 3.94 (MeV) SIG= 559.02 (mb) M1: standard lorentzian model(SLO) ER= 7.01 (MeV) EG= 4.00 (MeV) SIG= 1.75 (mb) E2: standard lorentzian model(SLO) ER= 10.77 (MeV) EG= 3.71 (MeV) SIG= 5.14 (mb) References 1) K.Shibata, J. Nucl. Sci. Technol., 53, 1595 (2016). 2) S.F. Mughabghab, "Neutron Cross Sections," Vol. 1, Part B: Z= 61-100, Academic Press (1984). 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007). 4) V.Avrigeanu et al., Report OUNP-94-02 (1994) , Phys. Rev. C49,2136 (1994). 5) J.M.Lohr and W.Haeberli, Nucl. Phys. A232,381(1974). 6) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 7) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 8) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 9) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965). 10) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994). 11) V.A. Plujko et al., J. Nucl. Sci. Technol.(supp. 2), 811 (2002).