75-Re-185 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210531 ----JENDL-5 MATERIAL 7525 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-05 Evaluated with CCONE code by N.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: below 500 eV Resolved resonance parameters were taken from Mughabghab/1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.19785E+02 Elastic 7.75193E+00 n,gamma 1.12033E+02 1.73823E+03 n,alpha 5.00389E-07 5.37121E-06 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. MT= 2 Elastic scattering cross section Calculated with CCONE code /2/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 33 (n,nt) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 33 (n,nt) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT=51-91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=750-799 (n,He3) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. 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=102 Capture reaction Calculated with CCONE code /2/. MT=103 (n,p) reaction Calculated with CCONE code /2/. MT=107 (n,a) reaction Calculated with CCONE code /2/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT=105 (n,t) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda/3/ modified 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 : L.McFadden and G.R.Satchler/7/ modified * Level scheme of Re-185 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 + 1 0.125360 7/2 + 2 0.284200 9/2 + 3 0.368300 9/2 - 4 0.475700 11/2 + 5 0.547000 11/2 - 6 0.646130 1/2 + 7 0.697100 13/2 + 8 0.717450 3/2 + 9 0.757500 13/2 - 10 0.768930 5/2 + 11 0.826000 5/2 + 12 0.836000 5/2 + 13 0.874820 3/2 + 14 0.880330 1/2 + 15 0.917000 7/2 + 16 0.931060 3/2 + 17 0.949700 15/2 + 18 0.966000 9/2 + 19 0.994800 15/2 - 20 1.013000 5/2 + 21 1.045000 1/2 - ----------------------- * 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 --------------------------------------------------------- Re-186 21.084 0.000 0.935 0.471 -1.172 3.376 0.689 Re-185 20.803 0.882 1.109 0.501 -0.612 4.762 1.045 Re-184 21.414 0.000 0.988 0.433 -0.868 2.827 0.804 Re-183 20.609 0.887 1.130 0.511 -0.689 4.901 1.127 W-185 21.995 0.882 1.227 0.499 -0.887 5.061 1.120 W-184 21.618 1.769 1.237 0.519 -0.184 6.249 1.808 W-183 21.079 0.887 1.116 0.529 -1.025 5.374 0.631 W-182 21.373 1.779 1.233 0.496 0.169 5.754 2.241 W-181 21.189 0.892 1.441 0.512 -0.927 5.155 0.848 Ta-184 21.414 0.000 1.389 0.432 -0.934 2.879 0.089 Ta-183 20.308 0.887 1.522 0.474 -0.311 4.263 1.030 Ta-182 20.144 0.000 1.180 0.498 -1.345 3.681 0.749 Ta-181 21.722 0.892 1.431 0.474 -0.583 4.592 0.773 Ta-180 21.016 0.000 1.391 0.470 -1.275 3.448 0.830 Ta-179 20.219 0.897 1.889 0.520 -0.925 5.159 0.938 --------------------------------------------------------- * Gamma-ray strength functions for Re-186 E1: standard lorentzian model(SLO) ER= 4.20 (MeV) EG= 1.00 (MeV) SIG= 0.50 (mb) ER= 5.13 (MeV) EG= 0.62 (MeV) SIG= 6.50 (mb) ER= 12.28 (MeV) EG= 3.13 (MeV) SIG= 168.27 (mb) ER= 15.20 (MeV) EG= 4.70 (MeV) SIG= 336.55 (mb) M1: standard lorentzian model(SLO) ER= 7.18 (MeV) EG= 4.00 (MeV) SIG= 0.89 (mb) E2: standard lorentzian model(SLO) ER= 11.04 (MeV) EG= 3.88 (MeV) SIG= 4.64 (mb) References 1) S.F.Mughabghab, Atlas of Neutron Resonances (2006) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 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, (2005) 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)