56-Ba-140 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211029 ----JENDL-5 MATERIAL 5655 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-11 Evaluated with CCONE code by N.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 5.6 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 5.60926E+00 Elastic 3.95533E+00 n,gamma 1.57061E+00 7.13210E-01 n,alpha 5.00810E-10 2.28181E-10 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 24 (n,2na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 33 (n,nt) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was taken from Halperin et al./2/. Below 5.5keV the 1/v cross section was assumed. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. 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=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=10 Nuclide production reactions MT= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : 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 Ba-140 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.602360 2 + 2 1.130590 4 + 3 1.510670 2 + 4 1.660300 6 + 5 1.802890 3 - 6 1.823790 0 + 7 1.951600 3 + 8 1.993650 2 + 9 2.138230 3 + 10 2.152100 5 - 11 2.204200 3 + 12 2.237240 2 + 13 2.309510 2 + 14 2.320510 3 + 15 2.429520 1 + 16 2.468300 8 + 17 2.521810 2 + 18 2.663800 0 + 19 2.692000 4 - 20 2.704040 1 + 21 2.722900 7 - 22 2.782070 3 + 23 2.787550 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 --------------------------------------------------------- Ba-141 17.465 1.011 -0.695 0.614 -0.435 5.417 1.765 Ba-140 17.363 2.028 -1.374 0.611 0.887 6.123 2.788 Ba-139 17.526 1.018 -2.229 0.673 -0.471 6.097 2.250 Ba-138 16.505 2.043 -3.135 0.742 0.612 7.734 2.991 Ba-137 17.022 1.025 -2.244 0.595 0.405 4.429 2.439 Cs-140 17.363 0.000 -1.379 0.725 -2.447 6.421 0.232 Cs-139 17.261 1.018 -1.845 0.715 -1.035 7.002 1.215 Cs-138 17.159 0.000 -2.919 0.720 -1.548 5.647 0.556 Cs-137 17.057 1.025 -3.804 0.701 0.130 5.844 2.150 Xe-139 17.261 1.018 -2.123 0.656 -0.251 5.667 1.684 Xe-138 17.159 2.043 -2.931 0.748 0.175 8.346 2.710 Xe-137 22.191 1.025 -3.900 0.581 -0.034 5.355 2.230 Xe-136 16.954 2.058 -4.832 0.840 0.297 9.984 2.869 Xe-135 21.627 1.033 -3.800 0.531 0.494 4.203 2.169 Xe-134 16.749 2.073 -2.821 0.780 -0.067 8.919 2.654 --------------------------------------------------------- * Gamma-ray strength functions for Ba-141 E1: enhanced generalized lorentzian model(EGLO)/10/ ER= 13.94 (MeV) EG= 3.99 (MeV) SIG= 112.23 (mb) ER= 15.62 (MeV) EG= 4.95 (MeV) SIG= 224.47 (mb) M1: standard lorentzian model(SLO) ER= 7.88 (MeV) EG= 4.00 (MeV) SIG= 0.66 (mb) E2: standard lorentzian model(SLO) ER= 12.10 (MeV) EG= 4.42 (MeV) SIG= 3.00 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) J.Halperin et al., ORNL Reports, No.4164, 1 (1967) 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) J.Kopecky et al., Phys. Rev. C 47, 312 (1993)