28-Ni- 59 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210531 ----JENDL-5 MATERIAL 2828 -----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 Resolved resonance region: below 10 keV Resolved resonance parameters were taken from JENDL-4.0/1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 9.18101E+01 Elastic 2.30465E+00 n,gamma 7.55970E+01 1.19909E+02 n,p 1.44799E+00 2.33415E+00 n,alpha 1.24558E+01 1.92356E+01 ---------------------------------------------------------- (*) 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 Calculated with CCONE code /2/. 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= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) 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=102 Capture cross section Calculated with CCONE code /2/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. Pointwise resonance cross sections below 10 keV were taken from JENDL-4.0/1/. 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/. Pointwise resonance cross sections below 10 keV were taken from JENDL-4.0/1/. 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/. 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= 44 (n,n2p) 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=115 (n,pd) reaction Calculated with CCONE code /2/. MT=116 (n,pt) 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= 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. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MF=10 Nuclide production cross sections MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT=104 (n,d) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda/3/ modified 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 : L.McFadden and G.R.Satchler/7/ * Level scheme of Ni-59 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 - 1 0.339420 5/2 - 2 0.464980 1/2 - 3 0.877950 3/2 - 4 1.188790 5/2 - 5 1.301410 1/2 - 6 1.337890 7/2 - 7 1.679700 5/2 - 8 1.695000 7/2 + 9 1.734720 3/2 - 10 1.739240 9/2 - 11 1.746100 7/2 - 12 1.767450 9/2 - 13 1.947930 7/2 - 14 2.330000 5/2 - 15 2.414970 3/2 - 16 2.428000 5/2 + 17 2.480000 5/2 + 18 2.530400 9/2 - 19 2.535500 5/2 - 20 2.553400 7/2 - 21 2.627070 7/2 - 22 2.640000 1/2 - 23 2.681400 5/2 - 24 2.692000 5/2 + 25 2.705020 11/2 - 26 2.713000 5/2 + 27 2.893620 3/2 - 28 3.025830 1/2 + 29 3.037500 7/2 - 30 3.054330 9/2 + 31 3.061000 7/2 - 32 3.125430 7/2 - 33 3.132000 9/2 - 34 3.164000 7/2 - 35 3.181630 3/2 - 36 3.196000 5/2 - 37 3.296700 5/2 - 38 3.308100 5/2 - 39 3.320000 3/2 - 40 3.339400 9/2 - ----------------------- * 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 --------------------------------------------------------- Ni-60 8.535 3.098 -2.246 1.460 -1.494 16.998 4.399 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 Co-59 8.617 1.562 -1.233 1.366 -2.837 13.285 3.140 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 Fe-58 7.852 3.151 -0.530 1.435 -1.487 14.731 4.348 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-60 E1: hybrid model(GH)/10/ ER= 18.38 (MeV) EG= 6.76 (MeV) SIG= 101.30 (mb) M1: standard lorentzian model(SLO) ER= 10.47 (MeV) EG= 4.00 (MeV) SIG= 1.72 (mb) E2: standard lorentzian model(SLO) ER= 16.09 (MeV) EG= 5.39 (MeV) SIG= 1.44 (mb) References 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) Y.Han et al., Phys. Rev. C 74,044615(2006) 6) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54, (2005) 7) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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)