56-Ba-129 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211029 ----JENDL-5 MATERIAL 5622 -----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 5.1 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.26329E+01 Elastic 3.28158E+00 n,gamma 1.91499E+01 1.55166E+03 n,p 1.61040E-02 1.30645E+00 n,alpha 1.71072E-02 1.32548E+00 ---------------------------------------------------------- (*) 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= 41 (n,2np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 1.5eV 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/. MT=108 (n,2a) cross section Calculated with CCONE code /1/. MT=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) 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= 41 (n,2np) 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=108 (n,2a) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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= 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. MT=108 (n,2a) reaction Decay chain is given in the decay data file. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MF=10 Nuclide production reactions MT= 4 (n,n') 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=106 (n,He3) 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-129 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 + 1 0.008420 7/2 + 2 0.110570 3/2 + 3 0.182040 9/2 - 4 0.253760 3/2 + 5 0.263100 9/2 + 6 0.278570 1/2 + 7 0.278810 11/2 - 8 0.318380 3/2 - 9 0.318400 5/2 + 10 0.457020 3/2 + 11 0.459290 3/2 + 12 0.467300 7/2 + 13 0.542270 5/2 + 14 0.544740 11/2 + 15 0.617810 3/2 + 16 0.628800 3/2 + 17 0.643600 13/2 - 18 0.656700 3/2 + 19 0.659970 5/2 + 20 0.667770 3/2 + 21 0.711920 1/2 + 22 0.787070 3/2 - 23 0.797400 15/2 - 24 0.799600 3/2 + 25 0.806840 9/2 + 26 0.849440 1/2 + 27 0.864100 13/2 + 28 0.883430 13/2 - 29 0.888650 1/2 + 30 0.896000 3/2 + 31 0.906700 3/2 - 32 0.911380 5/2 - 33 0.928590 1/2 + ----------------------- * 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-130 16.337 2.105 1.716 0.584 0.482 6.237 2.475 Ba-129 16.234 1.057 2.329 0.647 -1.511 6.419 0.929 Ba-128 16.131 2.121 2.104 0.569 0.596 6.033 2.670 Ba-127 16.028 1.065 2.544 0.615 -1.101 5.827 0.991 Cs-129 16.234 1.057 1.827 0.633 -1.143 6.026 0.755 Cs-128 16.131 0.000 2.160 0.541 -1.259 3.490 0.375 Cs-127 16.028 1.065 2.303 0.618 -1.050 5.807 0.872 Cs-126 15.924 0.000 2.429 0.569 -1.576 3.934 0.596 Xe-128 16.131 2.121 1.122 0.679 -0.357 7.703 2.554 Xe-127 16.028 1.065 1.786 0.652 -1.288 6.277 1.119 Xe-126 15.924 2.138 1.783 0.649 -0.150 7.264 2.515 Xe-125 15.820 1.073 2.340 0.651 -1.402 6.325 1.126 Xe-124 15.717 2.155 2.176 0.596 0.418 6.392 2.625 Xe-123 15.613 1.082 2.645 0.628 -1.147 5.928 1.260 --------------------------------------------------------- * Gamma-ray strength functions for Ba-130 E1: enhanced generalized lorentzian model(EGLO)/10/ ER= 13.74 (MeV) EG= 3.88 (MeV) SIG= 102.20 (mb) ER= 16.23 (MeV) EG= 5.33 (MeV) SIG= 204.41 (mb) M1: standard lorentzian model(SLO) ER= 8.09 (MeV) EG= 4.00 (MeV) SIG= 0.69 (mb) E2: standard lorentzian model(SLO) ER= 12.44 (MeV) EG= 4.55 (MeV) SIG= 3.16 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) 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) J.Kopecky et al., Phys. Rev. C 47, 312 (1993)