75-Re-187 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210531 ----JENDL-5 MATERIAL 7531 -----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 Resolved resonance region: below 800 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 8.97799E+01 Elastic 1.33877E+01 n,gamma 7.63922E+01 3.00943E+02 n,alpha 1.06446E-09 1.19273E-08 ---------------------------------------------------------- (*) 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/. 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/ modified deuteron: Y.Han et al./5/ triton : 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-187 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5/2 + 1 0.134240 7/2 + 2 0.206250 9/2 - 3 0.303360 9/2 + 4 0.388630 11/2 - 5 0.508530 11/2 + 6 0.511770 1/2 + 7 0.581990 5/2 + 8 0.589140 3/2 + 9 0.603470 13/2 - 10 0.618370 3/2 + 11 0.625520 1/2 + 12 0.647260 5/2 + 13 0.685800 5/2 - 14 0.718730 5/2 - 15 0.744840 13/2 + 16 0.767800 7/2 + 17 0.772880 3/2 + 18 0.792610 13/2 + 19 0.816560 5/2 + 20 0.817000 7/2 + 21 0.826840 3/2 + 22 0.839550 15/2 - 23 0.842000 7/2 - 24 0.844700 9/2 + 25 0.864560 3/2 + 26 0.879470 5/2 + 27 0.933620 7/2 + 28 0.948000 1/2 + 29 0.960170 5/2 + 30 0.969300 5/2 - 31 0.979000 5/2 + 32 1.000930 7/2 + 33 1.003140 7/2 - 34 1.015130 15/2 + 35 1.034110 11/2 + 36 1.042560 15/2 + ----------------------- * 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-188 21.706 0.000 0.838 0.480 -1.369 3.665 0.575 Re-187 20.998 0.878 1.028 0.528 -0.968 5.306 1.043 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 W-187 22.570 0.878 1.188 0.499 -1.011 5.202 1.114 W-186 21.777 1.760 1.232 0.515 -0.166 6.194 1.738 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 Ta-186 21.612 0.000 1.590 0.396 -0.672 2.400 0.000 Ta-185 20.803 0.882 1.707 0.452 -0.219 4.042 0.890 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 --------------------------------------------------------- * Gamma-ray strength functions for Re-188 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= 12.31 (MeV) EG= 3.14 (MeV) SIG= 170.29 (mb) ER= 15.11 (MeV) EG= 4.65 (MeV) SIG= 340.57 (mb) M1: standard lorentzian model(SLO) ER= 7.16 (MeV) EG= 4.00 (MeV) SIG= 0.89 (mb) E2: standard lorentzian model(SLO) ER= 11.00 (MeV) EG= 3.85 (MeV) SIG= 4.62 (mb) References 1) S.F.Mughabghab, Atlas of Neutron Resonances (2006) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (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)