27-Co- 58MJAEA EVAL-Jan21 N.Iwamoto DIST-DEC21 20210131 ----JENDL-5 MATERIAL 2723 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-01 Evaluated with CCONE code by N.Iwamoto 21-08 MF8/MT4 was added 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 6.65 fm. Thermal capture cross section was taken from the data of Kondurov et al./1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.67958E+05 Elastic 5.60659E+00 Inelas 1.42561E+03 6.16948E+02 n,gamma 1.36051E+05 5.87838E+04 n,p 3.04576E+04 1.31599E+04 n,alpha 1.25141E+01 5.40699E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. 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 /2/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 33 (n,nt) cross section Calculated with CCONE code /2/. MT= 34 (n,nHe3) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT= 44 (n,n2p) cross section Calculated with CCONE code /2/. MT= 45 (n,npa) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. Below 308eV the cross section of 1/v shape was adopted. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. Below 308eV the cross section of 1/v shape was adopted. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. Below 308eV the cross section of 1/v shape was adopted. MT=108 (n,2a) cross section Calculated with CCONE code /2/. MT=111 (n,2p) cross section Calculated with CCONE code /2/. MT=112 (n,pa) cross section Calculated with CCONE code /2/. MT=115 (n,pd) cross section Calculated with CCONE code /2/. MT=116 (n,pt) cross section Calculated with CCONE code /2/. MT=117 (n,da) cross section Calculated with CCONE code /2/. MT=155 (n,ta) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT=51-91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=108 (n,2a) reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. MT=112 (n,pa) reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=750-799 (n,He3) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. 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= 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= 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=108 (n,2a) 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=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/4/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/4/ triton : folding OMP, A.J.Koning and J.P.Delaroche/4/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/4/ alpha : V.Avrigeanu/5/ * Level scheme of Co-58 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 2 + 1 0.024950 5 + 2 0.053150 4 + 3 0.111760 3 + 4 0.365660 3 + 5 0.373930 5 + 6 0.457500 4 + 7 0.885630 3 + 8 1.040120 3 + 9 1.044260 4 + 10 1.050190 1 + 11 1.075500 6 + 12 1.133000 1 - 13 1.184630 5 + 14 1.236550 2 + 15 1.351510 5 + 16 1.353470 2 + 17 1.369000 1 + 18 1.376880 1 + 19 1.418120 5 + 20 1.424000 3 + 21 1.424600 6 + 22 1.434900 1 + 23 1.513320 3 + 24 1.522570 2 + 25 1.524400 3 + 26 1.548810 5 + 27 1.554740 3 + 28 1.605620 3 + 29 1.669900 3 + 30 1.729240 1 + 31 1.740500 5 + 32 1.749350 4 + 33 1.757200 1 + 34 1.778000 5 + 35 1.813300 0 + 36 1.828000 0 - 37 1.843000 3 + 38 1.865800 2 + 39 1.867700 1 + 40 1.925000 2 + ----------------------- * Level density parameters (Gilbert-Cameron model/6/) Energy dependent parameters of Mengoni-Nakajima/7/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- 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 Co-57 8.383 1.589 -2.987 1.499 -2.598 16.370 3.469 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 Fe-56 8.265 3.207 -2.152 1.512 -1.767 17.770 4.683 Fe-55 8.368 1.618 -2.981 1.412 -1.461 14.103 3.860 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 Mn-54 8.029 0.000 -2.202 1.355 -2.644 10.264 2.355 Mn-53 7.911 1.648 -2.189 1.478 -2.250 14.498 3.710 --------------------------------------------------------- * Gamma-ray strength functions for Co-59 E1: hybrid model(GH)/8/ ER= 17.11 (MeV) EG= 5.89 (MeV) SIG= 32.86 (mb) ER= 19.21 (MeV) EG= 7.35 (MeV) SIG= 65.72 (mb) M1: standard lorentzian model(SLO) ER= 10.53 (MeV) EG= 4.00 (MeV) SIG= 1.76 (mb) E2: standard lorentzian model(SLO) ER= 16.18 (MeV) EG= 5.40 (MeV) SIG= 1.36 (mb) References 1) I.A.Kondurov et al. Atomnaya Energiya, 24, 533 (1968) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 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) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 6) A.Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 7) A.Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 8) S.Goriely, Phys. Lett. B436, 10 (1998)