52-Te-126 EVAL-Oct13 K.Shibata (JAEA) JNST 52, 490 (2015) DIST-DEC21 20180705 ----JENDL-5 MATERIAL 5243 -----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. 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.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 (MLBW formula) : below 30 keV For JENDL-3.1, resonance parameters were based on Mughabghab et al./2/ The levels whose neutron width was unknown were assumed to be p-wave resonances and a reduced neutron width of 35 meV was tentatively given for those levels. Neutron orbital angular momentum L of some resonances was estimated with a method of Bollinger and Thomas/3/. Averaged radiation width was deduced to be 98 meV and applied to the levels whose radiation width was unknown. The scattering radius of 5.6 fm was taken from Mughabghab et al./2/ A negative resonance was added so as to reproduce the thermal capture cross section given by Mughabghab et al. For JENL-3.2, neutron and radiation width were determined from the neutron widths measured by Tellier et al./4/ and the capture area data by Macklin and Winters/5/ in the energy range above 2.7 keV. The average radiation width of 0.070 eV given by Macklin and Winters was applied to the s-wave resonances whose radiation width had not been determined from the experiments. For the p-wave resonances without known radiation width, the value of 0.100 eV was assumed. In JENDL-4, the energy of a negative resoannce was changed to -52 eV from -32 eV so as reproduce the thermal capture cross section measured by Honzatko et al./6/ RRPs remain unchanged from JENDL-4.0 for JENDL-4.0+. Unresolved resonance region : 30 keV - 300 keV The parameters were obtained by fitting to the total and capture cross sections calculated from CCONE /7/. 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 3.8869E+00 Elastic 3.4468E+00 n,gamma 4.4008E-01 7.9187E+00 n,alpha 4.9311E-16 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /7/. 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 /7/. MT= 16 (n,2n) cross section Calculated with CCONE code /7/. MT= 17 (n,3n) cross section Calculated with CCONE code /7/. MT= 22 (n,na) cross section Calculated with CCONE code /7/. MT= 28 (n,np) cross section Calculated with CCONE code /7/. MT= 32 (n,nd) cross section Calculated with CCONE code /7/. MT= 41 (n,2np) cross section Calculated with CCONE code /7/. MT=102 Capture cross section Calculated with CCONE code /7/. Below 30 keV, the cross sections should be calculated from RRPs. MT=103,600-649 (n,p) cross section Calculated with CCONE code /7/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /7/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /7/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /7/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /7/. 1/v cross sections were assumed below 30 keV. The thermal (n,a) cross section was obtained by multiplying the thermal capture cross section 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 /7/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /7/. MT= 17 (n,3n) reaction Calculated with CCONE code /7/. MT= 22 (n,na) reaction Calculated with CCONE code /7/. MT= 28 (n,np) reaction Calculated with CCONE code /7/. MT= 32 (n,nd) reaction Calculated with CCONE code /7/. MT= 41 (n,2np) reaction Calculated with CCONE code /7/. MT=51-91 (n,n') reaction Calculated with CCONE code /7/. MT=102 Capture reaction Calculated with CCONE code /7/. MT=600-649 (n,p) reaction Calculated with CCONE code /7/. MT=650-699 (n,d) reaction Calculated with CCONE code /7/. MT=700-749 (n,t) reaction Calculated with CCONE code /7/. MT=750-799 (n,He3) reaction Calculated with CCONE code /7/. MT=800-849 (n,a) reaction Calculated with CCONE code /7/. 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 /7/. Below 200 keV, the isomeric ratios were adjusted so as to reproduce the meta-stable data measured by Honzatko et al./16/ MT=107 (n,a) reaction Calculated with CCONE code /7/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /7/. MT= 32 (n,nd) reaction Calculated with CCONE code /7/. MT= 41 (n,2np) reaction Calculated with CCONE code /7/. MT=103 (n,p) reaction Calculated with CCONE code /7/. MT=105 (n,t) reaction Calculated with CCONE code /7/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /7/ ------------------------------------------------------------------ * Optical model potentials alpha : E.D.Arthur and P.G.Young/8/ deuteron: J.M.Lohr and W.Haeberli/9/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/10/ neutron : S. Kunieda et al./11/ proton : A.J.Koning and J.P.Delaroche/12/ triton : F.D.Becchetti Jr. and G.W.Greenlees/10/ * Level scheme of Te-126 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.666350 2 + c 2 1.361400 4 + c 3 1.420180 2 + 4 1.776190 6 + c 5 1.873400 0 + 6 2.013170 4 + 7 2.045150 2 + 8 2.113570 4 + 9 2.128390 3 + 10 2.181510 1 + 11 2.184350 2 + 12 2.218200 5 - 13 2.309190 4 + 14 2.350800 6 + 15 2.385810 3 - d 16 2.385980 4 - 17 2.396420 6 + 18 2.421150 2 + 19 2.479730 4 + 20 2.496830 7 - 21 2.503550 2 + 22 2.515210 6 - 23 2.533850 4 - 24 2.577820 3 + 25 2.578500 1 + 26 2.585460 3 + 27 2.588900 3 - 28 2.640400 1 + 29 2.661430 5 - 30 2.678780 2 + 31 2.682030 2 + 32 2.686530 5 - 33 2.704490 6 + 34 2.731130 2 + 35 2.744200 3 + 36 2.765750 8 + 37 2.782720 4 - 38 2.803020 2 + 39 2.811600 7 - ----------------------- c: coupled-channel calc., d: DWBA calc. * Level density parameters (Gilbert-Cameron model/13/) Energy dependent parameters of Mengoni-Nakajima/14/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Te-127 16.028 1.065 0.102 0.681 -0.999 6.359 1.568 Te-126 15.924 2.138 0.364 0.662 0.232 7.099 2.812 Te-125 15.820 1.073 1.249 0.664 -1.161 6.275 1.322 Te-124 15.717 2.155 1.308 0.643 0.178 6.962 2.483 Sb-126 15.924 0.000 -0.622 0.726 -2.250 5.898 0.128 Sb-125 15.820 1.073 -0.073 0.472 0.909 2.998 2.299 Sb-124 15.717 0.000 0.761 0.590 -1.233 3.766 0.804 Sn-124 15.717 2.155 -1.003 0.664 0.824 6.637 3.011 Sn-123 15.613 1.082 -0.022 0.693 -0.917 6.354 1.301 Sn-122 15.509 2.173 0.159 0.609 1.011 5.990 3.036 --------------------------------------------------------- * Gamma-ray strength functions for Te-127 E1: modified lorentzian model(MLO1)/15/ ER= 15.39 (MeV) EG= 4.82 (MeV) SIG= 292.31 (mb) M1: standard lorentzian model(SLO) ER= 8.16 (MeV) EG= 4.00 (MeV) SIG= 1.50 (mb) E2: standard lorentzian model(SLO) ER= 12.53 (MeV) EG= 4.59 (MeV) SIG= 2.76 (mb) References 1) K.Shibata, J. Nucl. Sci. Technol., 52, 490 (2015). 2) S.F. Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 3) L.M. Bollinger and G.E. Thomas, Phys. Rev., 171,1293(1968). 4) H. Tellier and C.M. Newstedd, Proc. 3rd Int. Conf. on Neutron Cross Sections and Technol., Knoxville, March 1971, p.680 (1971). 5) R.L. Macklin and R.R. Winters, ORNL-6561 (1988). 6) J. Honzatko et al., Nucl. Phys., A756, 249 (2005). 7) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007). 8) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980). 9) J.M.Lohr and W.Haeberli, Nucl. Phys. A232,381(1974). 10) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 11) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 12) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 13) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965). 14) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994). 15) V.A. Plujko et al., J. Nucl. Sci. Technol.(supp. 2), 811 (2002). 16) J. Honzatko et al., Nucl. Phys. A756, 249 (2005).