74-W -185 JAEA EVAL-Aug21 N.Iwamoto DIST-DEC21 20210830 ----JENDL-5 MATERIAL 7440 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-08 Evaluated with CCONE code by N.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 76 eV Resolved resonance parameters were taken from Anufriev et al./1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.05823E+01 Elastic 7.28579E+00 n,gamma 3.29651E+00 1.85763E+02 n,alpha 4.12903E-08 3.55242E-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= 3 Non-elastic 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= 37 (n,4n) 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/. Below 10.1eV the cross section of 1/v shape was adopted. 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= 37 (n,4n) 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= 37 (n,4n) 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=107 (n,a) reaction Calculated with CCONE code /2/. MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 33 (n,nt) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * 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 : L.McFadden and G.R.Satchler/7/ * Level scheme of W-185 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 - 1 0.023550 1/2 - 2 0.065850 5/2 - 3 0.093300 3/2 - 4 0.173700 7/2 - 5 0.187880 5/2 - 6 0.197380 11/2 + 7 0.243620 7/2 - 8 0.302000 9/2 - 9 0.334000 7/2 - 10 0.384000 13/2 + 11 0.390920 9/2 - 12 0.478000 11/2 - 13 0.492000 9/2 - 14 0.570000 11/2 - 15 0.663490 3/2 - 16 0.706000 11/2 - 17 0.716000 9/2 + 18 0.729900 3/2 - 19 0.768220 1/2 - 20 0.774000 1/2 + 21 0.785300 9/2 - 22 0.801000 3/2 + 23 0.822710 3/2 - 24 0.827410 1/2 - 25 0.842000 5/2 + 26 0.888600 5/2 - 27 0.904000 1/2 + 28 0.917550 1/2 + 29 0.921000 7/2 + 30 0.967780 3/2 - 31 0.971000 1/2 + 32 0.979280 1/2 - 33 0.986000 7/2 - 34 1.005590 1/2 - 35 1.013000 1/2 - 36 1.020000 13/2 + 37 1.035790 3/2 - 38 1.041700 5/2 + 39 1.058700 7/2 - 40 1.062500 5/2 + ----------------------- * 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 --------------------------------------------------------- W-186 21.959 1.760 1.232 0.515 -0.217 6.254 1.563 W-185 21.992 0.882 1.227 0.492 -0.804 4.935 1.145 W-184 21.617 1.769 1.237 0.529 -0.319 6.449 1.661 W-183 21.078 0.887 1.116 0.502 -0.694 4.870 0.740 W-182 21.566 1.779 1.233 0.494 0.157 5.757 1.888 Ta-185 21.861 0.882 1.707 0.335 0.630 2.476 1.153 Ta-184 21.763 0.000 1.389 0.422 -0.893 2.785 0.048 Ta-183 20.304 0.887 1.522 0.426 0.158 3.485 1.030 Ta-182 20.140 0.000 1.180 0.490 -1.255 3.536 0.830 Ta-181 21.719 0.892 1.431 0.391 0.267 3.204 1.772 Hf-184 21.763 1.769 2.053 0.544 -0.829 6.992 0.107 Hf-183 21.664 0.887 1.654 0.501 -0.962 5.125 0.069 Hf-182 21.566 1.779 1.737 0.389 1.140 4.093 2.214 Hf-181 21.421 0.892 1.440 0.470 -0.475 4.447 1.210 Hf-180 20.556 1.789 1.590 0.559 -0.557 6.847 1.863 Hf-179 20.792 0.897 1.625 0.514 -0.910 5.135 1.139 Hf-178 20.921 1.799 1.846 0.547 -0.565 6.785 1.986 --------------------------------------------------------- * Gamma-ray strength functions for W-186 E1: hybrid model(GH)/10/ ER= 12.28 (MeV) EG= 3.13 (MeV) SIG= 167.53 (mb) ER= 15.20 (MeV) EG= 4.70 (MeV) SIG= 335.05 (mb) M1: standard lorentzian model(SLO) ER= 7.18 (MeV) EG= 4.00 (MeV) SIG= 1.03 (mb) E2: standard lorentzian model(SLO) ER= 11.04 (MeV) EG= 3.88 (MeV) SIG= 4.52 (mb) References 1) V.A.Anufriev et al., Conf. on Neutron Physics, Kiev, 2-6 Oct. 1983, Vol.3, p.215 (1983) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) 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)