58-Ce-134 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5819 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-09 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 7.09 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 9.26056E+00 Elastic 6.34869E+00 n,gamma 2.79388E+00 1.16441E+02 n,p 1.48510E-11 6.35062E-10 n,alpha 6.52039E-07 2.70302E-05 ---------------------------------------------------------- (*) 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= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 44 (n,n2p) 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 15.82 eV 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=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MT=115 (n,pd) 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= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 44 (n,n2p) 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MT=115 (n,pd) 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= 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= 44 (n,n2p) 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. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT==102 Capture reaction Calculated with CCONE code /1/. MT=107 (n,a) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 16 (n,2n) 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/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : global OMP, 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 : M.Avrigeanu and V.Avrigeanu/7/ * Level scheme of Ce-134 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.409200 2 + 2 0.965660 2 + 3 1.048680 4 + 4 1.382700 3 + 5 1.533500 0 + 6 1.572500 2 - 7 1.643470 4 + 8 1.775000 2 - 9 1.812000 4 + 10 1.863100 6 + 11 1.903800 1 - 12 1.964400 2 + 13 1.989100 3 + 14 2.027300 4 + 15 2.050000 5 + 16 2.158600 3 - 17 2.170300 5 + 18 2.174400 5 - 19 2.206300 2 + 20 2.246800 5 - 21 2.260900 4 + 22 2.272000 3 + 23 2.303800 6 + 24 2.313700 2 - 25 2.338700 4 + 26 2.359100 6 - 27 2.361400 6 + 28 2.373300 4 - 29 2.474100 6 - 30 2.545200 3 + 31 2.565800 7 - 32 2.654900 4 + 33 2.706600 7 - ----------------------- * 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 --------------------------------------------------------- Ce-135 16.852 1.033 1.371 0.513 0.089 4.118 1.145 Ce-134 16.749 2.073 1.541 0.537 0.875 5.551 2.707 Ce-133 16.646 1.041 2.190 0.558 -0.523 4.969 1.116 Ce-132 16.543 2.089 2.024 0.541 0.771 5.676 2.957 La-134 16.749 0.000 1.312 0.515 -0.932 3.080 0.920 La-133 16.646 1.041 1.770 0.547 -0.287 4.686 1.469 La-132 16.543 0.000 2.118 0.367 -0.049 1.295 1.166 La-131 16.441 1.048 2.311 0.576 -0.701 5.240 0.743 Ba-133 16.836 1.041 0.807 0.552 -0.119 4.590 1.830 Ba-132 16.543 2.089 1.014 0.563 0.841 5.770 3.069 Ba-131 16.286 1.048 1.694 0.586 -0.576 5.200 1.565 Ba-130 16.337 2.105 1.716 0.585 0.469 6.256 2.318 Ba-129 16.234 1.057 2.329 0.611 -1.053 5.776 1.258 Ba-128 16.131 2.121 2.104 0.535 0.933 5.510 1.710 --------------------------------------------------------- * Gamma-ray strength functions for Ce-135 E1: hybrid model(GH)/10/ ER= 13.69 (MeV) EG= 3.85 (MeV) SIG= 107.87 (mb) ER= 16.04 (MeV) EG= 5.21 (MeV) SIG= 215.74 (mb) M1: standard lorentzian model(SLO) ER= 7.99 (MeV) EG= 4.00 (MeV) SIG= 0.91 (mb) E2: standard lorentzian model(SLO) ER= 12.28 (MeV) EG= 4.49 (MeV) SIG= 3.30 (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) M.Avrigeanu and V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 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) S.Goriely, Phys. Lett. B436, 10 (1998)