54-Xe-129MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5441 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 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 8.11500E+00 Elastic 6.20851E+00 Inelas 5.72179E-03 5.94332E-01 n,gamma 1.79996E+00 1.21938E+02 n,p 2.60360E-15 1.81281E-13 n,alpha 1.99120E-10 1.55507E-08 ---------------------------------------------------------- (*) 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= 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 19.00 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/. 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= 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= 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=10 Nuclide production reactions MT= 4 (n,n') 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=106 (n,He3) 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 Xe-129 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 + 1 0.039580 3/2 + 2 0.236140 11/2 - 3 0.274280 9/2 - 4 0.318180 3/2 + 5 0.321710 5/2 + 6 0.411500 1/2 + 7 0.442200 5/2 + 8 0.518700 7/2 + 9 0.525260 5/2 + 10 0.572680 5/2 + 11 0.588530 3/2 + 12 0.624450 7/2 - 13 0.665420 7/2 + 14 0.692960 3/2 - 15 0.771110 13/2 - 16 0.822160 9/2 + 17 0.823050 3/2 - 18 0.823310 15/2 - 19 0.868050 7/2 + 20 0.904320 3/2 + 21 0.908620 9/2 + 22 0.946030 1/2 + 23 0.985700 1/2 - 24 0.995700 1/2 + 25 1.022310 7/2 + 26 1.032000 13/2 - 27 1.059570 7/2 + 28 1.089480 11/2 + 29 1.194500 9/2 + 30 1.194600 3/2 + 31 1.197110 5/2 + 32 1.229900 9/2 - 33 1.241200 3/2 + 34 1.336120 11/2 - ----------------------- * 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 --------------------------------------------------------- Xe-130 16.036 2.105 0.154 0.645 0.445 6.744 2.931 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 I-129 16.234 1.057 -0.106 0.623 -0.353 5.320 1.483 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 Te-128 16.131 2.121 -0.942 0.710 0.130 7.701 3.210 Te-127 16.636 1.065 0.101 0.643 -0.774 5.906 1.704 Te-126 15.858 2.138 0.363 0.652 0.367 6.893 3.225 Te-125 16.486 1.073 1.248 0.601 -0.665 5.437 1.436 Te-124 15.194 2.155 1.307 0.687 -0.128 7.497 3.383 Te-123 15.600 1.082 1.993 0.624 -0.869 5.683 1.515 --------------------------------------------------------- * Gamma-ray strength functions for Xe-130 E1: hybrid model(GH)/10/ ER= 15.31 (MeV) EG= 4.77 (MeV) SIG= 303.65 (mb) M1: standard lorentzian model(SLO) ER= 8.09 (MeV) EG= 4.00 (MeV) SIG= 0.90 (mb) E2: standard lorentzian model(SLO) ER= 12.44 (MeV) EG= 4.55 (MeV) SIG= 2.93 (mb) References 1) O.Iwamoto, J. 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