58-Ce-136 EVAL-Oct21 nakayama DIST-DEC21 20211005 ----JENDL-5 MATERIAL 5825 -----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 Resolved resonace region: below 880eV The evaluated values by Mughabghab /2/ were adopted. The parameters of negative and first resonances were modified so as to reproduce the experimental thermal capture cross sections and resonance integral by Torrel et al /3/. Unresolved resonance region: 880 - 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= 23 (n,n3a) 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/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. Connected with 1/v component at E = 880 eV. 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/. Connected with 1/v component at E = 880 eV. 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=114 (n,d2a) cross section Calculated with CCONE code /1/. MT=115 (n,pd) 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= 23 (n,n3a) 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= 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=114 (n,d2a) 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= 23 (n,n3a) 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=114 (n,d2a) 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 Taken from JENDL/AD-2017 /4/. MT=103 (n,p) 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= 34 (n,nHe3) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=116 (n,pt) reaction Calculated with CCONE code /1/. MT=155 (n,ta) reaction Calculated with CCONE code /1/. MT=158 (n,nda) 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./5/ proton : S. Kunieda et al./5/ deuteron: Y.Han et al./6/ triton : F.D.Becchetti Jr. and G.W.Greenlees/7/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/7/ alpha : E.D.Arthur and P.G.Young/8/ * Level scheme of Ce-136 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.552200 2 + 2 1.076300 0 + 3 1.092090 2 + 4 1.314150 4 + 5 1.553000 3 + 6 1.978500 5 - 7 2.067190 1 - 8 2.154950 2 + 9 2.214000 6 + 10 2.307100 7 - 11 2.366500 6 + 12 2.424900 6 - 13 2.451450 2 + 14 2.517320 3 + 15 2.594800 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 --------------------------------------------------------- Ce-137 17.057 1.025 0.462 0.547 -0.033 4.478 1.477 Ce-136 15.767 2.058 0.739 0.550 1.219 5.224 2.595 Ce-135 16.852 1.033 1.371 0.528 -0.050 4.350 1.036 Ce-134 16.749 2.073 1.541 0.578 0.452 6.220 2.050 La-136 16.954 0.000 0.209 0.548 -0.975 3.372 1.076 La-135 16.852 1.033 0.811 0.649 -1.192 6.282 0.828 La-134 16.749 0.000 1.312 0.594 -1.716 4.345 0.336 La-133 16.646 1.041 1.770 0.547 -0.287 4.686 1.469 Ba-135 16.852 1.033 -0.469 0.563 0.146 4.421 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 0.632 -0.911 5.887 1.112 Ba-132 16.543 2.089 1.014 0.611 0.330 6.586 2.069 Ba-131 16.441 1.048 1.694 0.579 -0.548 5.138 1.565 Ba-130 16.337 2.105 1.716 0.585 0.469 6.256 2.318 --------------------------------------------------------- * Gamma-ray strength functions for Ce-137 E1: enhanced generalized lorentzian model(EGLO)/11/ ER= 13.92 (MeV) EG= 3.98 (MeV) SIG= 109.77 (mb) ER= 15.80 (MeV) EG= 5.06 (MeV) SIG= 219.55 (mb) M1: standard lorentzian model(SLO) ER= 7.95 (MeV) EG= 4.00 (MeV) SIG= 0.67 (mb) E2: standard lorentzian model(SLO) ER= 12.22 (MeV) EG= 4.47 (MeV) SIG= 3.27 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.F.Mughabghab, "Atlas of Neutron Resonances", 6th edition, Elsevier (2018). 3) S.Torrel and K.S.Krane, Phys. Rev. C 86 034340 (2012). 4) K.Shibata et al., JAEA-Conf 2016-004, 47 (2016). 5) S. Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 6) Y.Han et al., Phys. Rev. C 74,044615(2006) 7) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 8) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980) 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)