77-Ir-186 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210930 ----JENDL-5 MATERIAL 7710 -----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 8.7 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 3.39345E+02 Elastic 9.53784E+00 n,gamma 3.29296E+02 3.32900E+03 n,p 5.13191E-03 5.18915E-02 n,alpha 3.16760E-02 3.20259E-01 ---------------------------------------------------------- (*) 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 1eV 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= 22 (n,na) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /1/. MT= 33 (n,nt) 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 : 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 : L.McFadden and G.R.Satchler/7/ * Level scheme of Ir-186 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5 + 1 0.000800 2 - 2 0.001940 3 + 3 0.054950 2 - 4 0.072700 2 + 5 0.078740 2 + 6 0.103730 4 + 7 0.110900 2 - 8 0.117500 7 + 9 0.121290 2 + 10 0.137300 5 + 11 0.167200 6 + 12 0.182900 2 + 13 0.195280 1 + 14 0.205560 0 + 15 0.206500 1 - 16 0.214000 3 - 17 0.226300 2 + 18 0.238120 1 + 19 0.246500 7 + 20 0.253360 4 - 21 0.260440 1 - 22 0.265310 1 - 23 0.312700 7 - 24 0.325130 2 + 25 0.332010 1 + 26 0.335300 1 - ----------------------- * 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 --------------------------------------------------------- Ir-187 22.057 0.878 1.431 0.510 -1.107 5.341 0.486 Ir-186 21.959 0.000 1.575 0.473 -1.525 3.754 0.335 Ir-185 21.861 0.882 1.619 0.505 -1.048 5.238 0.556 Ir-184 21.763 0.000 1.756 0.432 -1.075 3.032 0.519 Os-186 21.959 1.760 1.016 0.490 0.171 5.710 1.848 Os-185 21.861 0.882 1.235 0.522 -1.164 5.483 0.802 Os-184 21.763 1.769 1.259 0.482 0.254 5.570 2.000 Os-183 21.664 0.887 1.523 0.506 -0.992 5.194 0.850 Os-182 21.566 1.779 1.701 0.470 0.327 5.417 2.014 Re-185 21.861 0.882 1.109 0.472 -0.498 4.493 1.045 Re-184 21.763 0.000 0.988 0.423 -0.824 2.725 0.804 Re-183 21.664 0.887 1.130 0.481 -0.571 4.625 1.127 Re-182 21.566 0.000 1.426 0.401 -0.684 2.431 0.615 Re-181 21.468 0.892 1.742 0.474 -0.605 4.596 0.873 Re-180 21.369 0.000 1.997 0.306 -0.083 1.226 0.615 Re-179 21.271 0.897 2.283 0.404 0.068 3.478 0.817 --------------------------------------------------------- * Gamma-ray strength functions for Ir-187 E1: hybrid model(GH)/10/ ER= 12.43 (MeV) EG= 3.20 (MeV) SIG= 170.69 (mb) ER= 15.06 (MeV) EG= 4.62 (MeV) SIG= 341.39 (mb) M1: standard lorentzian model(SLO) ER= 7.17 (MeV) EG= 4.00 (MeV) SIG= 1.04 (mb) E2: standard lorentzian model(SLO) ER= 11.02 (MeV) EG= 3.87 (MeV) SIG= 4.88 (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) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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)