29-Cu- 63 EVAL-Dec19 nakayama DIST-DEC21 20191219 ----JENDL-5 MATERIAL 2925 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 19-12 Evaluated with CCONE code by S. Nakayama 20-10 Energies of discrete primary photons were corrected. 21-10 JENDL-5b3 (MF,MT)=(2,151),(3,1),(3,2),(3,102),(4,2) were revised. (MF,MT)=(3,34),(6,34),(8,34),(10,34) were deleted. 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved resonance parameters Taken from JEFF-3.3 /1/. Resonance pameters of negative and first resonances were changed so as to reproduce the experimental capture cross section around 100 eV by Weigand et al. /2/. MF= 3 Neutron cross sections MT= 1 Total cross section The data of JENDL-4.0 /3/ were decreased by about 5% in the energy region in 100 keV - 5 MeV. MT= 2 Elastic scattering cross section Made from (n,tot) - (n,rea) MT=4,51-91 (n,n') cross section Calculated with CCONE code /4/. MT= 16 (n,2n) cross section Calculated with CCONE code /4/. MT= 22 (n,na) cross section Calculated with CCONE code /4/. MT= 24 (n,2na) cross section Calculated with CCONE code /4/. MT= 28 (n,np) cross section Calculated with CCONE code /4/. MT= 29 (n,n2a) cross section Calculated with CCONE code /4/. MT= 32 (n,nd) cross section Calculated with CCONE code /4/. MT= 33 (n,nt) cross section Calculated with CCONE code /4/. MT= 41 (n,2np) cross section Calculated with CCONE code /4/. MT= 44 (n,n2p) cross section Calculated with CCONE code /4/. MT= 45 (n,npa) cross section Calculated with CCONE code /4/. MT=102 Capture cross section Calculated with CCONE code /4/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /4/. Connected with 1/v component at E = 402 eV. MT=104,650-699 (n,d) cross section Calculated with CCONE code /4/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /4/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /4/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /4/. Connected with 1/v component at E = 402 eV. MT=108 (n,2a) cross section Calculated with CCONE code /4/. MT=109 (n,3a) cross section Calculated with CCONE code /4/. MT=111 (n,2p) cross section Calculated with CCONE code /4/. MT=112 (n,pa) cross section Calculated with CCONE code /4/. MT=115 (n,pd) cross section Calculated with CCONE code /4/. MT=116 (n,pt) cross section Calculated with CCONE code /4/. MT=117 (n,da) cross section Calculated with CCONE code /4/. MT=155 (n,ta) cross section Calculated with CCONE code /4/. MT=191 (n,pHe3) cross section Calculated with CCONE code /4/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Taken from JEFF-3.3 /1/ below 400 keV. Calculated with CCONE code /4/ above 400 keV. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /4/. MT= 22 (n,na) reaction Calculated with CCONE code /4/. MT= 24 (n,2na) reaction Calculated with CCONE code /4/. MT= 28 (n,np) reaction Calculated with CCONE code /4/. MT= 29 (n,n2a) reaction Calculated with CCONE code /4/. MT= 32 (n,nd) reaction Calculated with CCONE code /4/. MT= 33 (n,nt) reaction Calculated with CCONE code /4/. MT= 41 (n,2np) reaction Calculated with CCONE code /4/. MT= 44 (n,n2p) reaction Calculated with CCONE code /4/. MT= 45 (n,npa) reaction Calculated with CCONE code /4/. MT=51-91 (n,n') reaction Calculated with CCONE code /4/. MT=102 Capture reaction Calculated with CCONE code /4/. MT=108 (n,2a) reaction Calculated with CCONE code /4/. MT=109 (n,3a) reaction Calculated with CCONE code /4/. MT=111 (n,2p) reaction Calculated with CCONE code /4/. MT=112 (n,pa) reaction Calculated with CCONE code /4/. MT=115 (n,pd) reaction Calculated with CCONE code /4/. MT=116 (n,pt) reaction Calculated with CCONE code /4/. MT=117 (n,da) reaction Calculated with CCONE code /4/. MT=155 (n,ta) reaction Calculated with CCONE code /4/. MT=191 (n,pHe3) reaction Calculated with CCONE code /4/. MT=600-649 (n,p) reaction Calculated with CCONE code /4/. MT=650-699 (n,d) reaction Calculated with CCONE code /4/. MT=700-749 (n,t) reaction Calculated with CCONE code /4/. MT=750-799 (n,He3) reaction Calculated with CCONE code /4/. MT=800-849 (n,a) reaction Calculated with CCONE code /4/. MF= 8 Information on decay data MT=4 (n,n') 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= 24 (n,2na) 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= 29 (n,n2a) 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= 33 (n,nt) 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= 45 (n,npa) 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=109 (n,3a) 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. MT=117 (n,da) reaction Decay chain is given in the decay data file. MT=155 (n,ta) reaction Decay chain is given in the decay data file. MT=191 (n,pHe3) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=107 (n,a) reaction Calculated with CCONE code /4/. MF=10 Nuclide production cross sections MT= 24 (n,2na) reaction Calculated with CCONE code /4/. MT=111 (n,2p) reaction Calculated with CCONE code /4/. MT=116 (n,pt) reaction Calculated with CCONE code /4/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /4/ ------------------------------------------------------------------ * Optical model potentials neutron : Hao et al. /5/ with modifications /6/ proton : global OMP, A.J.Koning and J.P.Delaroche/7/ deuteron: H.An and Y. C. Cai/8/ triton : F.D.Becchetti Jr. and G.W.Greenlees/9/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/9/ alpha : V.Avrigeanu/10/ * Level scheme of Cu-63 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 - 1 0.669930 1/2 - 2 0.962020 5/2 - 3 1.326760 7/2 - 4 1.412160 5/2 - 5 1.547000 3/2 - 6 1.860630 7/2 - 7 1.952030 5/2 + 8 2.012920 3/2 - 9 2.062450 1/2 - 10 2.081320 5/2 - 11 2.092130 7/2 - 12 2.207840 9/2 - 13 2.336540 5/2 - 14 2.337400 5/2 + 15 2.404660 7/2 - 16 2.430370 5/2 - 17 2.497190 3/2 - 18 2.503500 5/2 - 19 2.505080 9/2 + 20 2.511060 1/2 + 21 2.535830 5/2 - 22 2.547280 9/2 - 23 2.617950 3/2 - 24 2.630650 3/2 - 25 2.672930 5/2 - 26 2.676840 11/2 - 27 2.678430 7/2 - 28 2.682270 3/2 - 29 2.696660 3/2 - 30 2.716470 5/2 - 31 2.764090 3/2 - 32 2.776360 3/2 - 33 2.780230 3/2 - 34 2.808100 3/2 - 35 2.810000 1/2 - 36 2.818870 7/2 - 37 2.832370 7/2 - 38 2.836750 5/2 + 39 2.847000 7/2 - 40 2.857900 1/2 - ----------------------- * Gamma-ray strength functions for Cu-64 E1: enhanced generalized lorentzian model(EGLO)/11/ ER= 16.78 (MeV) EG= 5.68 (MeV) SIG= 36.93 (mb) ER= 18.84 (MeV) EG= 7.08 (MeV) SIG= 73.86 (mb) M1: standard lorentzian model(SLO) ER= 10.25 (MeV) EG= 4.00 (MeV) SIG= 1.01 (mb) E2: standard lorentzian model(SLO) ER= 15.75 (MeV) EG= 5.34 (MeV) SIG= 1.46 (mb) References 1) A.J.M.Plompen et al., Eur. Phys. J. A 56, 181 (2020) 2) M.Weigand et al., Phys. Rev. C 96, 015808 (2017) 3) K.Shibata et al., J. Nucl. Sci. Technol., 48, 1 (2011) 4) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 5) L.Hao et al., J. Phys. G 35, 095103 (2008) 6) S.Nakayama. J. Nucl. Sci. Technol., 55, 614 (2018) 7) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 8) H.An and Y. C. Cai, Phys. Rev. C 73,054605(2006) 9) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 10) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 11) J. Kopecky et al., Phys. Rev. C 47, 312 (1993)