58-Ce-138 EVAL-Oct21 nakayama DIST-DEC21 20211005 ----JENDL-5 MATERIAL 5831 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2021-10 Evaluated with CCONE code by nakayama MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Below 100eV Scattering radius only. AP is assumed to be 5.085 fm. Unresolved resonance region: 100 - 400 keV The parameters were obtained by fitting to the total and caputure cross sections calculated from CCONE /1/. The unresolved parameters should be used only for self- shielding calculation. 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= 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= 29 (n,n2a) cross section Calculated with CCONE code /1/. MT= 30 (n,2n2a) 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= 34 (n,nHe3) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) cross section Calculated with CCONE code /1/. MT= 44 (n,n2p) cross section Calculated with CCONE code /1/. MT= 45 (n,npa) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. Connected with 1/v component at E = 100 eV. Normarized so as to reproduce the experimental thermal capture cross section by Torrel et al. /2/. 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/. Connected with 1/v component at E = 100 eV. 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=109 (n,3a) 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/. MT=116 (n,pt) cross section Calculated with CCONE code /1/. MT=117 (n,da) cross section Calculated with CCONE code /1/. MT=155 (n,ta) cross section Calculated with CCONE code /1/. MT=191 (n,pHe3) cross section Calculated with CCONE code /1/. MT=193 (n,He3a) cross section Calculated with CCONE code /1/. MT=197 (n,3p) 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= 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= 25 (n,3na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 29 (n,n2a) reaction Calculated with CCONE code /1/. MT= 30 (n,2n2a) 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= 34 (n,nHe3) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT= 44 (n,n2p) reaction Calculated with CCONE code /1/. MT= 45 (n,npa) 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=109 (n,3a) 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=116 (n,pt) reaction Calculated with CCONE code /1/. MT=117 (n,da) reaction Calculated with CCONE code /1/. MT=155 (n,ta) reaction Calculated with CCONE code /1/. MT=191 (n,pHe3) reaction Calculated with CCONE code /1/. MT=193 (n,He3a) reaction Calculated with CCONE code /1/. MT=197 (n,3p) 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= 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= 29 (n,n2a) reaction Decay chain is given in the decay data file. MT= 30 (n,2n2a) 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= 34 (n,nHe3) 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= 44 (n,n2p) reaction Decay chain is given in the decay data file. MT= 45 (n,npa) 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=109 (n,3a) 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. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MT=117 (n,da) reaction Decay chain is given in the decay data file. MT=155 (n,ta) reaction Decay chain is given in the decay data file. MT=191 (n,pHe3) reaction Decay chain is given in the decay data file. MT=193 (n,He3a) reaction Decay chain is given in the decay data file. MT=197 (n,3p) 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=108 (n,2a) reaction Calculated with CCONE code /1/. MT=109 (n,3a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 30 (n,2n2a) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 34 (n,nHe3) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT= 44 (n,n2p) reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. MT=106 (n,He3) 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=116 (n,pt) reaction Calculated with CCONE code /1/. MT=197 (n,3p) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S. Kunieda et al./3/ proton : S. Kunieda et al./3/ deuteron: Y.Han et al./4/ triton : F.D.Becchetti Jr. and G.W.Greenlees/5/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/5/ alpha : E.D.Arthur and P.G.Young/6/ * Level scheme of Ce-138 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.788740 2 + 2 1.476930 0 + 3 1.510580 2 + 4 1.826480 4 + 5 2.129170 7 - 6 2.136820 4 + 7 2.177260 3 + 8 2.217330 5 - 9 2.236540 2 + 10 2.293700 6 + 11 2.339850 0 + 12 2.393830 3 - 13 2.396080 6 + 14 2.443680 4 + 15 2.470990 1 + 16 2.471460 4 + ----------------------- * Level density parameters (Gilbert-Cameron model/7/) Energy dependent parameters of Mengoni-Nakajima/8/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ce-139 17.261 1.018 -1.121 0.512 0.627 3.564 2.016 Ce-138 18.017 2.043 -0.415 0.607 0.559 6.610 2.471 Ce-137 17.057 1.025 0.462 0.547 -0.033 4.478 1.477 Ce-136 16.954 2.058 0.739 0.500 1.357 4.829 2.595 La-138 17.159 0.000 -1.494 0.586 -0.833 3.561 0.642 La-137 17.057 1.025 -0.450 0.587 -0.130 4.879 1.171 La-136 16.954 0.000 0.209 0.610 -1.582 4.405 0.484 La-135 16.852 1.033 0.811 0.590 -0.514 5.227 1.171 Ba-137 17.057 1.025 -2.244 0.509 0.961 3.146 2.750 Ba-136 16.954 2.058 -1.401 0.655 0.596 6.800 2.934 Ba-135 16.852 1.033 -0.469 0.542 0.322 4.091 2.075 Ba-134 16.749 2.073 -0.011 0.676 -0.128 7.565 2.379 Ba-133 16.646 1.041 0.807 0.561 -0.154 4.672 1.830 Ba-132 16.543 2.089 1.014 0.563 0.841 5.770 3.069 --------------------------------------------------------- * Gamma-ray strength functions for Ce-139 E1: enhanced generalized lorentzian model(EGLO)/9/ ER= 15.07 (MeV) EG= 4.63 (MeV) SIG= 334.96 (mb) M1: standard lorentzian model(SLO) ER= 7.91 (MeV) EG= 4.00 (MeV) SIG= 0.66 (mb) E2: standard lorentzian model(SLO) ER= 12.16 (MeV) EG= 4.44 (MeV) SIG= 3.24 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.Torrel and K.S.Krane, Phys. Rev. C 86 034340 (2012). 3) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 4) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 6) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980) 7) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 8) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 9) J. Kopecky et al., Phys. Rev. C 47, 312 (1993)