79-Au-195 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 7919 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-09 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 7.93 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.25434E+01 Elastic 7.92850E+00 n,gamma 4.47828E+00 4.83038E+02 n,p 3.85580E-20 4.16174E-18 n,alpha 3.16350E-12 3.39556E-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= 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= 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 3.64 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= 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= 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= 22 (n,na) reaction Calculated with CCONE code /1/. MT==102 Capture reaction Calculated with CCONE code /1/. MT=103 (n,p) 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= 17 (n,3n) 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/. ------------------------------------------------------------------ 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 Au-195 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 0.061430 1/2 + 2 0.241550 3/2 + 3 0.261790 5/2 + 4 0.318580 11/2 - 5 0.439530 3/2 + 6 0.525640 7/2 - 7 0.549380 7/2 + 8 0.706480 15/2 - 9 0.778220 1/2 + 10 0.818520 9/2 + 11 0.841000 1/2 + 12 0.841230 3/2 + 13 0.878850 13/2 - 14 0.894150 9/2 - 15 0.946830 13/2 + 16 0.955080 9/2 + 17 1.068000 9/2 - 18 1.082950 3/2 + 19 1.106000 5/2 + 20 1.110760 3/2 - 21 1.172440 3/2 + 22 1.250960 3/2 + 23 1.280510 11/2 - 24 1.324640 5/2 + 25 1.335000 1/2 + 26 1.346190 11/2 - 27 1.353610 3/2 + 28 1.366000 17/2 - 29 1.394000 5/2 + 30 1.396630 11/2 + 31 1.404600 13/2 - 32 1.406170 13/2 - 33 1.425000 19/2 - 34 1.433000 5/2 + 35 1.443170 1/2 + 36 1.487010 11/2 - 37 1.490200 13/2 + 38 1.503000 1/2 + 39 1.559600 13/2 - 40 1.585000 7/2 - ----------------------- * 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 --------------------------------------------------------- Au-196 22.936 0.000 -2.057 0.568 -1.787 4.997 1.244 Au-195 22.839 0.859 -1.473 0.457 0.124 3.801 1.781 Au-194 22.741 0.000 -0.840 0.367 -0.166 1.692 0.686 Au-193 22.644 0.864 -0.338 0.384 0.509 2.879 2.012 Pt-195 24.404 0.859 -1.453 0.527 -0.959 5.566 0.971 Pt-194 22.741 1.723 -1.156 0.547 -0.084 6.482 2.275 Pt-193 24.164 0.864 -0.350 0.501 -0.927 5.255 0.907 Pt-192 22.546 1.732 -0.210 0.507 0.167 5.864 1.935 Ir-194 23.564 0.000 -1.010 0.486 -1.277 3.748 0.908 Ir-193 23.681 0.864 -0.504 0.499 -0.744 5.037 0.964 Ir-192 23.376 0.000 -0.033 0.488 -1.554 4.004 0.658 Ir-191 22.448 0.868 0.292 0.496 -0.688 4.884 1.127 Ir-190 22.351 0.000 0.692 0.487 -1.538 3.913 0.891 Ir-189 22.253 0.873 0.874 0.484 -0.656 4.742 1.052 --------------------------------------------------------- * Gamma-ray strength functions for Au-196 E1: hybrid model(GH)/10/ ER= 13.91 (MeV) EG= 3.97 (MeV) SIG= 544.34 (mb) M1: standard lorentzian model(SLO) ER= 7.06 (MeV) EG= 4.00 (MeV) SIG= 1.04 (mb) E2: standard lorentzian model(SLO) ER= 10.85 (MeV) EG= 3.76 (MeV) SIG= 5.04 (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)