55-Cs-129 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5513 -----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 7.01 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.27292E+01 Elastic 6.20851E+00 n,gamma 6.35721E+00 3.24014E+02 n,p 7.57911E-06 3.86125E-04 n,alpha 1.06623E-08 5.45239E-07 ---------------------------------------------------------- (*) 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= 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/. The thermal cross section was derived from Shibata/2/. Below 4.24 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/. 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= 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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= 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. 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. MF= 9 Isomeric branching ratios MT==102 Capture reaction Calculated with CCONE code /1/. MT=103 (n,p) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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 Cs-129 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 + 1 0.006550 5/2 + 2 0.135570 3/2 + 3 0.188930 7/2 + 4 0.209060 5/2 + 5 0.220740 3/2 + 6 0.426470 9/2 + 7 0.551650 7/2 + 8 0.553960 3/2 + 9 0.554950 5/2 + 10 0.575440 11/2 - 11 0.603360 7/2 + 12 0.648420 11/2 + 13 0.690280 9/2 + 14 0.755170 7/2 + 15 0.879100 3/2 - 16 0.969150 7/2 + 17 0.991910 7/2 + 18 1.023840 15/2 - 19 1.032140 13/2 + 20 1.150000 13/2 - 21 1.156180 5/2 - 22 1.164920 3/2 - 23 1.231000 11/2 + 24 1.255630 7/2 + 25 1.279400 15/2 + 26 1.339200 13/2 + 27 1.609350 1/2 + ----------------------- * 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 --------------------------------------------------------- Cs-130 16.337 0.000 1.471 0.596 -1.681 4.276 1.480 Cs-129 16.234 1.057 1.827 0.515 0.104 4.105 1.609 Cs-128 16.131 0.000 2.160 0.405 -0.214 1.662 0.188 Cs-127 16.028 1.065 2.303 0.529 -0.096 4.379 1.043 Xe-129 15.930 1.057 0.966 0.651 -0.933 5.986 1.336 Xe-128 16.131 2.121 1.122 0.634 0.186 6.888 3.353 Xe-127 16.028 1.065 1.786 0.619 -0.891 5.699 1.283 Xe-126 15.924 2.138 1.783 0.626 0.132 6.852 3.189 I-128 16.030 0.000 0.637 0.636 -1.751 4.630 1.325 I-127 16.028 1.065 1.070 0.628 -0.750 5.666 1.443 I-126 15.924 0.000 1.622 0.590 -1.555 4.069 0.800 I-125 15.820 1.073 1.884 0.599 -0.626 5.312 1.443 I-124 15.717 0.000 2.318 0.561 -1.405 3.707 0.880 I-123 15.613 1.082 2.415 0.574 -0.454 4.973 1.493 --------------------------------------------------------- * Gamma-ray strength functions for Cs-130 E1: hybrid model(GH)/10/ ER= 13.73 (MeV) EG= 3.87 (MeV) SIG= 101.74 (mb) ER= 16.24 (MeV) EG= 5.34 (MeV) SIG= 203.47 (mb) M1: standard lorentzian model(SLO) ER= 8.09 (MeV) EG= 4.00 (MeV) SIG= 0.92 (mb) E2: standard lorentzian model(SLO) ER= 12.44 (MeV) EG= 4.55 (MeV) SIG= 3.04 (mb) References 1) O.Iwamoto, J. 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