57-La-138 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211029 ----JENDL-5 MATERIAL 5725 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 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 330 eV Resolved resonance parameters were taken from JENDL-4.0. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 6.94648E+01 Elastic 1.23811E+01 n,gamma 5.70837E+01 3.71153E+02 n,p 3.02966E-09 8.17156E-07 n,alpha 6.50059E-06 5.97677E-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= 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= 33 (n,nt) 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/. 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/. 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= 33 (n,nt) 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=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= 33 (n,nt) 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. MF= 9 Isomeric branching ratios MT=107 (n,a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions 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= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT=104 (n,d) 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/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./2/ proton : A.J.Koning and J.P.Delaroche/3/ deuteron: Y.Han et al./4/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al./5/ alpha : L.McFadden and G.R.Satchler/6/ * Level scheme of La-138 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5 + 1 0.072570 3 + 2 0.116170 2 + 3 0.161180 3 + 4 0.192190 2 + 5 0.230410 4 + 6 0.292980 1 + 7 0.413310 3 + 8 0.479340 4 + 9 0.510450 3 + 10 0.518680 4 + 11 0.642340 2 + 12 0.737690 2 - 13 0.738700 4 - 14 0.823370 3 - 15 0.836000 7 - 16 0.842790 3 + 17 0.888000 2 - 18 0.900600 4 - 19 0.929000 4 - 20 0.936900 5 - 21 0.947790 4 - 22 0.961400 6 - 23 1.033000 0 - 24 1.057880 2 + 25 1.067000 8 - 26 1.096000 2 + 27 1.102600 3 + 28 1.150000 5 - 29 1.155000 3 - 30 1.178000 2 + 31 1.200300 6 + 32 1.228500 1 + 33 1.243000 4 - 34 1.255000 9 - 35 1.267000 5 - ----------------------- * 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 --------------------------------------------------------- La-139 15.882 1.018 -2.218 0.755 -0.752 6.961 1.963 La-138 17.159 0.000 -1.494 0.600 -0.947 3.786 1.267 La-137 17.057 1.025 -0.450 0.627 -0.539 5.593 1.174 La-136 16.954 0.000 0.209 0.670 -2.292 5.540 0.437 Ba-138 16.505 2.043 -3.135 0.742 0.612 7.734 2.991 Ba-137 17.022 1.025 -2.244 0.595 0.405 4.429 2.439 Ba-136 16.940 2.058 -1.401 0.707 0.013 7.847 2.695 Ba-135 16.759 1.033 -0.469 0.649 -0.672 5.878 1.299 Cs-137 17.057 1.025 -3.804 0.701 0.130 5.844 2.150 Cs-136 17.960 0.000 -2.918 0.375 0.409 0.615 0.518 Cs-135 16.583 1.033 -1.814 0.658 -0.178 5.532 1.358 Cs-134 16.819 0.000 -0.895 0.710 -2.268 5.945 0.689 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 --------------------------------------------------------- * Gamma-ray strength functions for La-139 E1: hybrid model(GH)/9/ ER= 15.07 (MeV) EG= 4.63 (MeV) SIG= 333.25 (mb) M1: standard lorentzian model(SLO) ER= 7.91 (MeV) EG= 4.00 (MeV) SIG= 0.88 (mb) E2: standard lorentzian model(SLO) ER= 12.16 (MeV) EG= 4.44 (MeV) SIG= 3.13 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 6) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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) S.Goriely, Phys. Lett. B436, 10 (1998)