73-Ta-180M EVAL-Oct14 K.Shibata (JAEA) JNST 53, 957 (2016) DIST-DEC21 20180724 ----JENDL-5 MATERIAL 7326 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2014-10 Evaluated with CCONE code by K.Shibata (JAEA) /1/ 2018-07 Activation cross sections and MF=3,6/MT=600-849 added. 2020-10 Energies of discrete primary photons were corrected. MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region: 1.0e-5 eV - 103.0 eV The parameters were taken from the work of Harvey et al./2/ The parameters for the lowest resonance were the same as those for JEFF-3.2. Unresolved resonance region: 103.0 eV - 100 keV The parameters were obtained by fitting to the total and caputure cross sections calculated from CCONE /3/. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- LFS 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 5.6780E+02 Elastic 3.8610E+00 n,gamma 5.6394E+02 1.4428E+03 n,p 2.4030E-15 n,alpha 2.7628E-04 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from total cross sections. Below 103 eV, the cross section should be calculated from resolved resonance parameters. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 17 (n,3n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. Below 103 eV, the cross sections should be calculated from resolved resonance parameters. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. 1/v cross sections were assumed below 103 eV. The thermal (n,p) cross section was obtained by multiplying the thermal capture cross sections by the ratio of the CCONE calculations ( sig_np / sig_capture) at 0.0253 eV. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. 1/v cross sections were assumed below 103 eV. The thermal (n,a) cross section was obtained by multiplying the thermal capture cross sections by the ratio of the CCONE calculations ( sig_na / sig_capture) at 0.0253 eV. MF= 4 Angular distributions of secondary neutrons MT= 2 Elastic scattering Calculated with CCONE code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. MF= 8 Information on decay data MT=4 (n,n') MT= 16 (n,2n) MT= 17 (n,3n) MT= 22 (n,na) MT= 28 (n,np) MT= 32 (n,nd) MT= 41 (n,2np) MT=102 Capture MT=103 (n,p) MT=104 (n,d) MT=105 (n,t) MT=106 (n,He3) MT=107 (n,a) MF= 9 Isomeric branching ratios MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT=103 (n,p) reaction Calculated with CCONE code /3/. MT=107 (n,a) reaction Calculated with CCONE code /3/. MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT=104 (n,d) reaction Calculated with CCONE code /3/. MT=105 (n,t) reaction Calculated with CCONE code /3/. MT=106 (n,He3) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials alpha : E.D.Arthur and P.G.Young/4/ deuteron: J.M.Lohr and W.Haeberli/5/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/6/ neutron : S. Kunieda et al./7/ proton : A.J.Koning and J.P.Delaroche/8/ triton : F.D.Becchetti Jr. and G.W.Greenlees/6/ * Level scheme of Ta-180 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1 + 1 0.039670 2 + 2 0.077100 9 - c 3 0.107850 0 - 4 0.110870 3 + 5 0.130550 1 - 6 0.171280 2 - 7 0.177650 8 + 8 0.185030 4 + 9 0.234480 3 - 10 0.258000 4 + 11 0.280030 10 - c 12 0.310970 5 + 13 0.318350 4 - 14 0.320460 1 + 15 0.356680 7 + 16 0.370980 2 + 17 0.373720 9 + 18 0.416400 6 + 19 0.420000 5 - 20 0.423610 1 - 21 0.425800 4 + 22 0.448000 3 + 23 0.463240 7 - 24 0.478240 2 - 25 0.505210 11 - c 26 0.515560 8 + 27 0.520140 4 + 28 0.544360 3 - 29 0.547790 6 - 30 0.548010 4 + 31 0.549480 3 - 32 0.559630 2 + 33 0.572200 4 + 34 0.574510 6 - 35 0.575570 8 + 36 0.594430 5 + 37 0.594990 10 + 38 0.600410 7 + 39 0.624270 3 + ----------------------- c: coupled-channel calc. * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ta-181 21.468 0.892 1.428 0.481 -0.603 4.644 0.773 Ta-180 21.369 0.000 1.388 0.471 -1.354 3.544 0.624 Ta-179 21.271 0.897 1.887 0.482 -0.700 4.735 0.891 Ta-178 21.172 0.000 1.749 0.394 -0.632 2.315 0.671 Hf-180 21.369 1.789 1.588 0.541 -0.532 6.736 1.630 Hf-179 21.271 0.897 1.623 0.501 -0.867 5.030 1.121 Hf-178 21.172 1.799 1.843 0.545 -0.608 6.823 1.651 Lu-178 21.172 0.000 1.338 0.402 -0.633 2.367 0.475 Lu-177 21.074 0.902 1.751 0.488 -0.689 4.762 1.094 Lu-176 20.975 0.000 1.388 0.470 -1.281 3.445 0.709 --------------------------------------------------------- * Gamma-ray strength functions for Ta-181 E1: generalized lorentzian model(GLO)/11/ ER= 12.30 (MeV) EG= 2.43 (MeV) SIG= 259.00 (mb) ER= 15.23 (MeV) EG= 4.48 (MeV) SIG= 341.00 (mb) ER= 5.50 (MeV) EG= 2.50 (MeV) SIG= 3.00 (mb) M1: standard lorentzian model(SLO) ER= 7.25 (MeV) EG= 4.00 (MeV) SIG= 1.03 (mb) E2: standard lorentzian model(SLO) ER= 11.14 (MeV) EG= 3.94 (MeV) SIG= 4.45 (mb) References 1) K.Shibata, J. Nucl. Sci. Technol., 53, 957 (2016). 2) J.A. Harvey et al, ORNL-5025, 122 (1975). 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007). 4) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980). 5) J.M.Lohr and W.Haeberli, Nucl. Phys. A232,381(1974). 6) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 7) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 8) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 9) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965). 10) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994). 11) J. Kopecky and M. Uhl, Phys. Rev. C 41, 1941 (1990).