28-Ni- 60 JAEA EVAL-May21 N.Iwamoto DIST-DEC21 20210531 ----JENDL-5 MATERIAL 2831 -----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 MT=151 Resolved and unresolved resonance parameters Resolved resonance region: below 800 keV Resolved resonance parameters were taken from ENDF/B-VIII.0/#8//. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 3.50062E+00 Elastic 1.09959E+00 n,gamma 2.40101E+00 1.23259E+00 n,alpha 1.71085E-09 7.68461E-10 ---------------------------------------------------------- (*) 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=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=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=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=10 Nuclide production cross sections MT=103 (n,p) reaction Calculated with CCONE code /1/. MT=105 (n,t) 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 800 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 : global 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-60 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.332520 2 + 2 2.158640 2 + 3 2.284870 0 + 4 2.505770 4 + 5 2.626080 3 + 6 3.119700 4 + 7 3.124020 2 + 8 3.186020 2 + 9 3.194020 1 + 10 3.269380 2 + 11 3.318700 0 + 12 3.381000 2 - 13 3.393500 2 + 14 3.588100 0 + 15 3.619550 3 + 16 3.622900 2 - 17 3.670710 4 + 18 3.702000 4 + 19 3.730670 2 + 20 3.736100 2 + 21 3.875000 2 + 22 3.887800 2 + 23 3.895000 2 + 24 3.925800 3 + 25 4.007900 2 + 26 4.020450 1 + 27 4.035000 2 + 28 4.039670 3 - 29 4.078540 2 + 30 4.116000 2 + 31 4.165410 5 + 32 4.191000 3 - 33 4.265130 6 + 34 4.294500 4 + 35 4.300000 5 - 36 4.319000 2 + 37 4.334700 1 + 38 4.341000 0 + 39 4.355700 1 + 40 4.399400 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-61 9.232 1.536 -1.253 1.170 -1.308 10.187 2.905 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 Co-60 8.489 0.000 -0.608 1.192 -2.726 8.086 1.981 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 Fe-59 8.956 1.562 0.279 1.067 -1.008 8.388 2.570 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 --------------------------------------------------------- * Gamma-ray strength functions for Ni-61 E1: hybrid model(GH)/9/ ER= 17.09 (MeV) EG= 5.88 (MeV) SIG= 34.51 (mb) ER= 18.98 (MeV) EG= 7.19 (MeV) SIG= 69.02 (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= 1.42 (mb) References #8) D.A.Brown et al., Nucl. 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