27-Co- 60 JAEA EVAL-Jan21 N.Iwamoto DIST-DEC21 20210131 ----JENDL-5 MATERIAL 2728 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2021-01 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 and unresolved resonance parameters Resolved resonance region (MLBW formula) : below 3.0 keV The resonance parameters were adopted from the measured results of Anufriev et al./1/. The thermal capture cross section was fixed to be 2 b/2/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 6.40820E+00 Elastic 4.40190E+00 n,gamma 2.00628E+00 3.17876E+00 n,p 2.22510E-16 5.11930E-11 n,alpha 2.56030E-16 2.93905E-16 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. MT= 2 Elastic scattering cross section Obtained by subtracting the sum of the partial cross sections from the total cross section. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 17 (n,3n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 24 (n,2na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 33 (n,nt) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. Below 3keV the cross section of 1/v shape was adopted. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. Below 3keV the cross section of 1/v shape was adopted. MT=112 (n,pa) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /3/. MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 24 (n,2na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 33 (n,nt) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. 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. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT=106 (n,He3) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./4/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/5/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/5/ alpha : V.Avrigeanu/6/ * Level scheme of Co-60 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5 + 1 0.058590 2 + 2 0.277200 4 + 3 0.288400 3 + 4 0.435710 5 + 5 0.506200 3 + 6 0.542820 2 + 7 0.614550 3 + 8 0.738800 1 + 9 0.785710 4 + 10 0.940000 4 - 11 1.003910 3 - 12 1.005800 4 + 13 1.131980 2 - 14 1.150700 2 + 15 1.207830 5 + 16 1.216450 6 + 17 1.216850 4 + 18 1.341860 3 + 19 1.379740 6 + 20 1.380970 3 + 21 1.451210 4 + 22 1.508300 3 + 23 1.510000 7 + 24 1.515800 4 + 25 1.565940 2 - 26 1.639840 4 + 27 1.669000 3 - 28 1.686210 1 + 29 1.709680 1 + 30 1.749290 3 + 31 1.787620 5 + 32 1.800220 6 - 33 1.808630 3 - 34 1.830800 4 + 35 1.833230 2 + 36 1.852710 4 + 37 1.877150 2 - 38 1.888900 4 + 39 1.924290 2 - 40 1.981200 4 - ----------------------- * 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 --------------------------------------------------------- Co-61 8.850 1.536 0.494 1.057 -0.931 8.140 3.104 Co-60 8.494 0.000 -0.608 1.181 -2.621 7.896 1.981 Co-59 8.617 1.562 -1.233 1.371 -2.901 13.397 3.140 Co-58 8.500 0.000 -2.321 1.430 -4.099 13.110 1.925 Fe-60 8.734 3.098 1.189 1.031 0.568 9.393 4.053 Fe-59 9.026 1.562 0.279 0.992 -0.368 7.294 2.856 Fe-58 7.911 3.151 -0.530 1.402 -1.184 14.190 4.353 Fe-57 8.384 1.589 -1.312 1.336 -2.068 12.210 2.988 Mn-59 8.617 1.562 2.391 0.698 1.109 4.411 1.239 Mn-58 8.500 0.000 1.105 1.097 -2.930 6.979 0.817 Mn-57 8.383 1.589 0.838 1.113 -1.234 8.597 2.772 Mn-56 8.108 0.000 -0.645 1.272 -3.114 8.915 1.780 Mn-55 8.148 1.618 -1.124 1.448 -3.248 14.184 3.080 --------------------------------------------------------- * Gamma-ray strength functions for Co-61 E1: hybrid model(GH)/9/ ER= 16.62 (MeV) EG= 5.58 (MeV) SIG= 34.29 (mb) ER= 19.28 (MeV) EG= 7.41 (MeV) SIG= 68.57 (mb) M1: standard lorentzian model(SLO) ER= 10.42 (MeV) EG= 4.00 (MeV) SIG= 1.70 (mb) E2: standard lorentzian model(SLO) ER= 16.00 (MeV) EG= 5.38 (MeV) SIG= 1.32 (mb) References 1) V.A.Anufriev et al., Soviet Atomic Energy, 46, 57 (1979) 2) C.H.Hogg, L.D.Weber, Idaho Nuclear Corp. Reports No.1024 (1966) 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 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)