28-Ni- 58 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210531 ----JENDL-5 MATERIAL 2825 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-05 Evaluated with CCONE code by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF32/MT151) Added (MF33/MT1-115, MF34/MT2) Evaluated with CCONE-KALMAN MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters Resolved resonance region: below 812 keV Resolved resonance parameters were taken from ENDF/B-VIII.0/#b8//. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.92677E+01 Elastic 2.50410E+01 n,gamma 4.22662E+00 1.98267E+00 n,p 1.56733E-09 9.49032E-10 n,alpha 2.28157E-05 1.07891E-05 ---------------------------------------------------------- (*) 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= 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= 44 (n,n2p) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. Background cross section was taken from ENDF/B-VIII.0/#b8//. 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=108 (n,2a) 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/. MT=115 (n,pd) 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= 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= 44 (n,n2p) 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=108 (n,2a) 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=115 (n,pd) 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= 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= 44 (n,n2p) 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. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=103 (n,p) reaction Calculated with CCONE code /1/. MF=32 Covariances of resonance parameters MT=151 Resonance parameters Data were taken from ENDF-B-VIII.0. MF=33 Covariances of neutron cross sections Covariances were given to all the cross sections by using KALMAN code and the covariances of model parameters used in the cross-section calculations. Data below 812 keV were taken from ENDF-B-VIII.0. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda/2/ modified proton : glabal OMP, A.J.Koning and J.P.Delaroche/3/ modified deuteron: Y.Han et al./4/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al./5/ alpha : L.McFadden and G.R.Satchler/6/ modified * Level scheme of Ni-58 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.454210 2 + 2 2.459210 4 + 3 2.775420 2 + 4 2.902150 1 + 5 2.942560 0 + 6 3.037860 2 + 7 3.263660 2 + 8 3.269100 2 + 9 3.273700 2 + 10 3.420550 3 + 11 3.450900 1 - 12 3.524000 4 + 13 3.531100 0 + 14 3.593710 2 + 15 3.620090 4 + 16 3.775000 3 + 17 3.870000 2 - 18 3.898800 2 + 19 3.943600 1 - 20 4.020000 2 - 21 4.105900 4 + 22 4.108400 2 + 23 4.260000 2 + 24 4.294700 4 + 25 4.347900 2 + 26 4.358700 3 - 27 4.383000 5 + 28 4.404300 4 + 29 4.449600 2 + 30 4.474600 3 - 31 4.518300 2 + 32 4.538000 0 + 33 4.574100 1 + ----------------------- * 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 --------------------------------------------------------- Ni-59 9.206 1.562 -3.082 1.348 -1.838 14.306 3.339 Ni-58 8.500 3.151 -4.040 1.590 -1.523 21.404 4.574 Ni-57 8.383 1.589 -5.294 1.521 -0.582 18.253 4.606 Co-58 8.075 0.000 -2.321 1.515 -4.457 14.134 1.925 Co-57 8.383 1.589 -2.987 1.506 -2.704 16.579 3.469 Co-56 8.265 0.000 -4.376 1.514 -2.810 15.527 1.115 Fe-57 8.315 1.589 -1.312 1.366 -2.315 12.701 3.059 Fe-56 8.265 3.207 -2.152 1.503 -1.634 17.526 4.683 Fe-55 8.333 1.618 -2.981 1.428 -1.607 14.443 3.860 Fe-54 8.029 3.266 -3.371 1.524 -0.278 17.953 5.506 --------------------------------------------------------- * Gamma-ray strength functions for Ni-59 E1: hybrid model(GH)/9/ ER= 18.45 (MeV) EG= 6.81 (MeV) SIG= 99.03 (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= 1.46 (mb) References #b8) D.A.Brown et al., Nucl. Data Sheets, 148, 1 (2018) 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54, (2005) 6) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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)