52-Te-130 EVAL-Oct13 K.Shibata (JAEA) JNST 52, 490 (2015) DIST-DEC21 20180709 ----JENDL-5 MATERIAL 5255 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2013-10 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 (MLBW formula) : below 30.5 keV Resonance parameters were mainly based on Mughabghab et al. /2/ Some radiation widths were derived from the data of capture area and neutron width given by Mughabghab et al. Neutron orbital angular momentum L was estimated with a method of Bollinger and Thomas/3/. Averaged radiation width was deduced to be 107 meV, and applied to the levels whose radiation width was unknown. The scattering radius of 7.4 fm was taken from Mughabghab et al. A negative resonance was added so as to reproduce the thermal capture cross section given by Mughabghab et al. In JENDL-4.0, the radiation width of the negative resonance was adjusted so as to reproduce the thermal capture cross section measured by Tomandl et al./4/ Unresolved resonance region : 30.5 keV - 300 keV The parameters were obtained by fitting to the total and capture cross sections calculated from CCONE /5/. 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 4.0373E+00 Elastic 3.8511E+00 n,gamma 1.8622E-01 2.4990E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /5/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from total cross sections. 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 /5/. MT= 16 (n,2n) cross section Calculated with CCONE code /5/. MT= 17 (n,3n) cross section Calculated with CCONE code /5/. MT= 22 (n,na) cross section Calculated with CCONE code /5/. MT= 28 (n,np) cross section Calculated with CCONE code /5/. MT= 32 (n,nd) cross section Calculated with CCONE code /5/. MT= 41 (n,2np) cross section Calculated with CCONE code /5/. MT=102 Capture cross section Calculated with CCONE code /5/. Below 30.5 keV, the cross sections should be calculated from RRPs. MT=103,600-649 (n,p) cross section Calculated with CCONE code /5/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /5/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /5/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /5/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /5/. MF= 4 Angular distributions of secondary neutrons MT= 2 Elastic scattering Calculated with CCONE code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT= 17 (n,3n) reaction Calculated with CCONE code /5/. MT= 22 (n,na) reaction Calculated with CCONE code /5/. MT= 28 (n,np) reaction Calculated with CCONE code /5/. MT= 32 (n,nd) reaction Calculated with CCONE code /5/. MT= 41 (n,2np) reaction Calculated with CCONE code /5/. MT=51-91 (n,n') reaction Calculated with CCONE code /5/. MT=102 Capture reaction Calculated with CCONE code /5/. MT=600-649 (n,p) reaction Calculated with CCONE code /5/. MT=650-699 (n,d) reaction Calculated with CCONE code /5/. MT=700-749 (n,t) reaction Calculated with CCONE code /5/. MT=750-799 (n,He3) reaction Calculated with CCONE code /5/. MT=800-849 (n,a) reaction Calculated with CCONE code /5/. 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=102 Capture reaction Calculated with CCONE code /5/. Below 20 keV, the isomeric ratios were modified so as to reproduce the data measured by Eastman and Krane /14/ at thermal energy. MT=107 (n,a) reaction Calculated with CCONE code /5/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT= 28 (n,np) reaction Calculated with CCONE code /5/. MT= 32 (n,nd) reaction Calculated with CCONE code /5/. MT= 41 (n,2np) reaction Calculated with CCONE code /5/. MT=103 (n,p) reaction Calculated with CCONE code /5/. MT=104 (n,d) reaction Calculated with CCONE code /5/. MT=105 (n,t) reaction Calculated with CCONE code /5/. MT=106 (n,He3) reaction Calculated with CCONE code /5/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /5/ ------------------------------------------------------------------ * Optical model potentials alpha : E.D.Arthur and P.G.Young/6/ deuteron: J.M.Lohr and W.Haeberli/7/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/8/ neutron : S. Kunieda et al./9/ proton : A.J.Koning and J.P.Delaroche/10/ triton : F.D.Becchetti Jr. and G.W.Greenlees/8/ * Level scheme of Te-130 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.839490 2 + c 2 1.588260 2 + 3 1.633000 4 + c 4 1.815340 6 + c 5 1.885700 2 + 6 1.964760 0 + 7 1.981550 4 + 8 2.101250 5 - 9 2.138630 3 + 10 2.146410 7 - 11 2.190610 2 + 12 2.282590 2 + 13 2.300220 2 + 14 2.330740 4 + 15 2.404650 6 - 16 2.418000 0 + 17 2.432080 7 - 18 2.435590 4 - 19 2.449480 4 + 20 2.466890 2 + 21 2.527060 3 - 22 2.575200 0 + 23 2.581150 2 + 24 2.607330 1 + 25 2.648570 8 + 26 2.648600 10 + 27 2.689120 1 + 28 2.714970 4 - 29 2.719490 5 + 30 2.729500 3 - d 31 2.736310 4 + 32 2.743140 1 + 33 2.744970 0 + 34 2.765260 4 + 35 2.770840 0 + 36 2.782120 7 - 37 2.789260 0 + 38 2.833350 0 + 39 2.878430 0 + ----------------------- c: coupled-channel calc., d: DWBA calc. * Level density parameters (Gilbert-Cameron model/11/) Energy dependent parameters of Mengoni-Nakajima/12/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Te-131 16.441 1.048 -3.422 0.828 -1.216 8.719 1.952 Te-130 16.337 2.105 -2.610 0.813 -0.401 9.581 2.878 Te-129 16.234 1.057 -1.461 0.737 -1.056 7.086 1.110 Te-128 16.131 2.121 -0.941 0.739 -0.223 8.301 2.749 Sb-130 16.337 0.000 -4.508 0.871 -2.060 8.454 1.097 Sb-129 16.234 1.057 -3.542 0.810 -0.811 8.051 2.263 Sb-128 16.131 0.000 -2.378 0.581 -0.287 2.810 0.833 Sn-128 16.131 2.121 -4.644 0.904 -0.163 11.371 2.642 Sn-127 16.028 1.065 -3.311 0.834 -1.134 8.601 1.243 Sn-126 15.924 2.138 -2.605 0.784 0.189 8.613 2.795 --------------------------------------------------------- * Gamma-ray strength functions for Te-131 E1: modified lorentzian model(MLO1)/13/ ER= 15.28 (MeV) EG= 4.75 (MeV) SIG= 302.66 (mb) M1: standard lorentzian model(SLO) ER= 8.07 (MeV) EG= 4.00 (MeV) SIG= 1.47 (mb) E2: standard lorentzian model(SLO) ER= 12.40 (MeV) EG= 4.54 (MeV) SIG= 2.71 (mb) References 1) K.Shibata, J. Nucl. Sci. Technol., 52, 490 (2015). 2) S.F. Mughabghab, "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 3) L.M. Bollinger and G.E. Thomas, Phys. Rev., 171,1293(1968). 4) I. Tomandl et al., Nucl. Phys., A717, 149 (2003). 5) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007). 6) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980). 7) J.M.Lohr and W.Haeberli, Nucl. Phys. A232,381(1974). 8) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 9) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 10) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 11) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965). 12) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994). 13) V.A. Plujko et al., J. Nucl. Sci. Technol.(supp. 2), 811 (2002). 14) M.C. Eastman, K.S. Krane, Phys. Rev., C77, 024303 (2008).