55-Cs-132 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 5522 -----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 7.06 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.90055E+01 Elastic 6.29285E+00 n,gamma 1.24604E+01 5.06073E+02 n,p 5.60903E-04 2.30958E-02 n,alpha 1.50058E-02 3.85861E-03 ---------------------------------------------------------- (*) 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/. The thermal cross section was derived from Shibata/2/. Below 2.64 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= 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=10 Nuclide production reactions MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT=104 (n,d) 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 Cs-132 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 2 + 1 0.086200 3 + 2 0.108300 4 + 3 0.136000 4 + 4 0.153000 4 - 5 0.183600 4 + 6 0.185900 5 + 7 0.213000 10 - 8 0.240100 5 - 9 0.270000 3 - 10 0.291000 13 - 11 0.311700 7 - 12 0.327000 13 - 13 0.352000 13 - 14 0.379300 8 - 15 0.400000 6 - 16 0.426000 16 - 17 0.505000 7 - 18 0.521000 12 - 19 0.537600 8 - 20 0.551000 13 - 21 0.787800 9 - 22 0.980000 9 - 23 1.081500 10 - 24 1.131300 9 + 25 1.214700 10 - 26 1.281900 10 + 27 1.474600 11 - 28 1.683500 11 + 29 1.729200 10 + 30 1.826100 11 - 31 1.835200 11 + 32 1.891200 11 + 33 1.933900 12 - 34 1.982000 12 + 35 1.987900 12 + 36 2.089400 12 - 37 2.201600 12 + 38 2.316000 13 - 39 2.368700 13 + 40 2.395700 14 + ----------------------- * 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-133 16.646 1.041 -0.173 0.650 -0.759 5.947 1.173 Cs-132 16.543 0.000 0.506 0.605 -1.518 4.247 3.666 Cs-131 16.441 1.048 1.038 0.594 -0.499 5.214 1.458 Cs-130 16.337 0.000 1.471 0.596 -1.681 4.276 1.480 Xe-132 16.643 2.089 -1.149 0.655 0.620 6.771 3.156 Xe-131 18.471 1.048 -0.175 0.529 -0.017 4.463 1.722 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 I-131 16.441 1.048 -1.641 0.694 -0.564 6.233 2.235 I-130 17.375 0.000 -0.684 0.614 -1.463 4.381 0.762 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 --------------------------------------------------------- * Gamma-ray strength functions for Cs-133 E1: hybrid model(GH)/10/ ER= 15.23 (MeV) EG= 4.72 (MeV) SIG= 313.43 (mb) M1: standard lorentzian model(SLO) ER= 8.03 (MeV) EG= 4.00 (MeV) SIG= 0.89 (mb) E2: standard lorentzian model(SLO) ER= 12.34 (MeV) EG= 4.51 (MeV) SIG= 3.00 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 4) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 5) Y.Han et al., Phys. Rev. C 74,044615(2006) 6) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 7) M.Avrigeanu and V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 8) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 9) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 10) S.Goriely, Phys. Lett. B436, 10 (1998)