80-Hg-196 EVAL-Mar15 K.Shibata (JAEA) JNST 53, 1595 (2016) DIST-DEC21 20180711 ----JENDL-5 MATERIAL 8025 -----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 - 102.85 eV Parameters were taken from the JENDL-4.0 evaluation, which is based on the compilation of Mughabghab /2/. Unresolved resonance region: 102.85 eV - 400 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 3.1887E+03 Elastic 1.0982E+02 n,gamma 3.0789E+03 4.3010E+02 n,alpha 2.9201E-04 ---------------------------------------------------------- (*) 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 Obtained by subtracting non-elastic cross sctions from total cross sections. Below 102.85 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 102.85 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 102.85 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=102 Capture reaction Calculated with CCONE code /3/. Below 500 keV, the isomeric ratios were adjusted so as to reproduce measured thermal cross sections. MT=103 (n,p) reaction Calculated with CCONE code /3/. MT=107 (n,a) reaction Calculated with CCONE code /3/. MF=10 Nuclide production cross sections MT= 16 (n,2n) 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/. ------------------------------------------------------------------ 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-196 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + c 1 0.425980 2 + c 2 0.958400 1 + 3 1.036650 2 + 4 1.061440 4 + c 5 1.319000 0 + 6 1.390900 2 + 7 1.451100 0 + 8 1.644300 0 + 9 1.695800 3 - d 10 1.757030 5 - d 11 1.774990 4 + 12 1.785150 6 + c 13 1.815200 3 + 14 1.841340 7 - d 15 1.845400 2 + 16 1.922000 2 + 17 1.979000 1 + 18 1.985900 1 + 19 1.988200 4 + 20 2.012600 2 + 21 2.044100 2 + 22 2.058460 6 - 23 2.064350 9 - 24 2.097780 8 - ----------------------- 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-197 23.033 0.855 -2.645 0.581 -0.901 6.006 0.904 Hg-196 22.936 1.714 -2.164 0.531 0.405 5.890 2.098 Hg-195 22.839 0.859 -1.303 0.517 -0.540 4.960 1.005 Hg-194 22.741 1.723 -1.041 0.427 1.165 4.247 2.374 Au-196 22.936 0.000 -2.059 0.591 -2.105 5.550 0.502 Au-195 22.839 0.859 -1.475 0.492 -0.211 4.422 1.560 Au-194 22.741 0.000 -0.842 0.356 -0.104 1.554 0.769 Pt-194 22.741 1.723 -1.159 0.545 -0.056 6.437 1.992 Pt-193 22.644 0.864 -0.352 0.557 -1.327 6.020 0.692 Pt-192 22.546 1.732 -0.214 0.512 0.108 5.960 1.823 --------------------------------------------------------- * Gamma-ray strength functions for Hg-197 E1: modified lorentzian model(MLO1)/11/ ER= 13.90 (MeV) EG= 3.96 (MeV) SIG= 549.67 (mb) M1: standard lorentzian model(SLO) ER= 7.05 (MeV) EG= 4.00 (MeV) SIG= 1.73 (mb) E2: standard lorentzian model(SLO) ER= 10.83 (MeV) EG= 3.75 (MeV) SIG= 5.16 (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).