56-Ba-133 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211029 ----JENDL-5 MATERIAL 5634 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-11 Evaluated with CCONE code by N.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 resonance parameters Resolved resonance region : below 145 eV Resolved resonance parameters were taken from Masyanov and Anufriev/1/. Average gamma width was assumed to be 124meV. The parameters of negative resonance were adjusted so as to reproduce an assumed thermal capture cross section. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 5.11910E+00 Elastic 2.38925E+00 n,gamma 2.72980E+00 1.25145E+02 n,p 5.08900E-11 2.39338E-09 n,alpha 4.27868E-05 1.92311E-03 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. MT= 2 Elastic scattering cross section Calculated with CCONE code /2/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. The thermal cross section was derived from Shibata/3/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. MT=111 (n,2p) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=750-799 (n,He3) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. 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=111 (n,2p) reaction Decay chain is given in the decay data file. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT=106 (n,He3) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./4/ proton : A.J.Koning and J.P.Delaroche/5/ deuteron: Y.Han et al./6/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : Y.Xu et al./7/ alpha : L.McFadden and G.R.Satchler/8/ * Level scheme of Ba-133 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 + 1 0.012330 3/2 + 2 0.288250 11/2 - 3 0.291190 5/2 + 4 0.302400 3/2 + 5 0.539800 1/2 + 6 0.577560 7/2 + 7 0.630570 5/2 + 8 0.676490 3/2 + 9 0.791100 7/2 - 10 0.858500 3/2 + 11 0.862800 7/2 + 12 0.883390 9/2 + 13 0.887140 5/2 + 14 0.901800 13/2 - 15 0.923960 5/2 + 16 0.968970 15/2 - 17 0.969400 3/2 + 18 1.021580 3/2 + 19 1.066800 5/2 + 20 1.111200 7/2 - 21 1.112350 3/2 + 22 1.211790 3/2 + 23 1.247700 1/2 + 24 1.271300 7/2 - 25 1.283960 3/2 - 26 1.329320 5/2 + 27 1.329500 7/2 - 28 1.352760 7/2 + 29 1.375650 11/2 + ----------------------- * 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 --------------------------------------------------------- Ba-134 16.786 2.073 -0.011 0.673 -0.112 7.535 2.600 Ba-133 16.836 1.041 0.807 0.613 -0.756 5.620 1.376 Ba-132 16.543 2.089 1.014 0.603 0.427 6.434 2.505 Ba-131 16.286 1.048 1.694 0.632 -1.101 5.987 0.974 Cs-133 16.646 1.041 -0.173 0.651 -0.772 5.968 1.219 Cs-132 16.543 0.000 0.506 0.627 -1.754 4.628 0.426 Cs-131 16.441 1.048 1.038 0.663 -1.311 6.459 0.775 Cs-130 16.337 0.000 1.471 0.560 -1.307 3.690 0.432 Xe-132 16.643 2.089 -1.149 0.687 0.267 7.401 2.670 Xe-131 18.471 1.048 -0.175 0.604 -0.818 5.805 1.046 Xe-130 16.036 2.105 0.154 0.678 0.067 7.360 2.705 Xe-129 15.930 1.057 0.966 0.685 -1.348 6.615 1.089 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 --------------------------------------------------------- * Gamma-ray strength functions for Ba-134 E1: enhanced generalized lorentzian model(EGLO)/11/ ER= 15.20 (MeV) EG= 4.70 (MeV) SIG= 317.81 (mb) M1: standard lorentzian model(SLO) ER= 8.01 (MeV) EG= 4.00 (MeV) SIG= 0.66 (mb) E2: standard lorentzian model(SLO) ER= 12.31 (MeV) EG= 4.50 (MeV) SIG= 3.09 (mb) References 1) S.M.Masyanov, V.A.Anufriev, Soviet Atomic Energy, 69, 799 (1990) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) Y.Han et al., Phys. Rev. C 74,044615(2006) 7) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 8) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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 et al., Phys. Rev. C 47, 312 (1993)