28-Ni- 56 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210531 ----JENDL-5 MATERIAL 2819 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-05 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 6.4 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 5.39697E+00 Elastic 5.19460E+00 n,gamma 1.37481E-02 2.75671E-02 n,p 1.48759E-01 3.51357E-01 n,alpha 6.93340E-10 2.16124E-09 ---------------------------------------------------------- (*) 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= 44 (n,n2p) 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/. The cross section of 1/v shape was adopted in the resonance region. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. The cross section of 1/v shape was adopted in the resonance region. 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/. The cross section of 1/v shape was adopted in the resonance region. 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= 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= 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=107 (n,a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production cross sections MT=105 (n,t) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al/2/ modified proton : A.J.Koning and J.P.Delaroche/3/ deuteron: Y.Han et al./4/ triton : A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al. /5/ alpha : L.McFadden and G.R.Satchler/6/ * Level scheme of Ni-56 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 2.700600 2 + 2 3.923600 4 + 3 3.956600 0 + 4 4.932000 0 - 5 4.935500 3 + 6 5.003700 0 + 7 5.315700 6 + 8 5.352500 2 + 9 5.483700 4 + 10 5.665100 5 + 11 5.799000 4 - 12 5.988100 4 + 13 6.011000 1 - 14 6.236000 2 + 15 6.326400 4 + 16 6.405800 4 + 17 6.431900 4 + 18 6.522100 5 - 19 6.554600 2 + 20 6.588600 3 + 21 6.650500 6 + 22 6.654800 0 + 23 6.730000 2 + ----------------------- * 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-57 8.672 1.589 -5.294 1.466 -0.373 17.441 4.606 Ni-56 7.910 3.207 -6.255 1.647 1.256 23.071 6.730 Ni-55 8.433 1.618 -4.443 1.341 0.605 12.666 4.046 Co-56 7.910 0.000 -4.376 1.584 -3.052 16.448 1.115 Co-55 7.433 1.618 -4.761 1.815 -3.278 23.461 3.942 Co-54 7.677 0.000 -4.775 1.665 -3.273 18.371 2.390 Fe-55 8.333 1.618 -2.981 1.428 -1.607 14.443 3.860 Fe-54 7.676 3.266 -3.371 1.604 -0.626 19.028 5.506 Fe-53 8.192 1.648 -3.333 1.481 -1.691 15.652 3.463 Fe-52 7.440 3.328 -3.653 1.529 1.063 16.529 6.564 --------------------------------------------------------- * Gamma-ray strength functions for Ni-57 E1: hybrid model(GH)/9/ ER= 18.60 (MeV) EG= 6.92 (MeV) SIG= 94.39 (mb) M1: standard lorentzian model(SLO) ER= 10.65 (MeV) EG= 4.00 (MeV) SIG= 1.82 (mb) E2: standard lorentzian model(SLO) ER= 16.37 (MeV) EG= 5.43 (MeV) SIG= 1.51 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 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[11], 2005 (2011) 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)