29-Cu- 65 EVAL-Dec19 nakayama DIST-DEC21 20191218 ----JENDL-5 MATERIAL 2931 -----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. 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/. MF= 3 Neutron cross sections MT= 1 Total cross section The data of JENDL-4.0 /2/ 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 /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 17 (n,3n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 24 (n,2na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 29 (n,n2a) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 33 (n,nt) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT= 45 (n,npa) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. MT=108 (n,2a) cross section Calculated with CCONE code /3/. MT=111 (n,2p) cross section Calculated with CCONE code /3/. MT=112 (n,pa) cross section Calculated with CCONE code /3/. MT=115 (n,pd) cross section Calculated with CCONE code /3/. MT=117 (n,da) cross section Calculated with CCONE code /3/. MT=155 (n,ta) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Taken from JEFF-3.3 /1/ below 400 keV. Calculated with CCONE code /3/ above 400 keV. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 24 (n,2na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 29 (n,n2a) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 33 (n,nt) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT= 45 (n,npa) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=108 (n,2a) reaction Calculated with CCONE code /3/. MT=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MT=115 (n,pd) reaction Calculated with CCONE code /3/. MT=117 (n,da) reaction Calculated with CCONE code /3/. MT=155 (n,ta) reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. 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= 17 (n,3n) 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= 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=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=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. MF=10 Nuclide production cross sections MT= 24 (n,2na) reaction Calculated with CCONE code /3/. MT=107 (n,a) reaction Calculated with CCONE code /3/. MT=108 (n,2a) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : Hao et al. /4/ with modifications /5/ proton : global OMP, A.J.Koning and J.P.Delaroche/6/ deuteron: H.An and Y. C. Cai/7/ triton : F.D.Becchetti Jr. and G.W.Greenlees/8/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/8/ alpha : V.Avrigeanu/9/ * Level scheme of Cu-65 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 - 1 0.770640 1/2 - 2 1.115560 5/2 - 3 1.481830 7/2 - 4 1.623430 5/2 - 5 1.725000 3/2 - 6 2.094340 7/2 - 7 2.107440 5/2 - 8 2.212840 1/2 - 9 2.278500 7/2 - 10 2.329050 3/2 - 11 2.406600 9/2 + 12 2.525740 9/2 + 13 2.533040 5/2 - 14 2.533900 9/2 + 15 2.593400 5/2 - 16 2.620000 1/2 + 17 2.643500 3/2 + 18 2.649670 5/2 - 19 2.654900 3/2 - 20 2.669000 3/2 - 21 2.752800 7/2 + 22 2.839000 7/2 + 23 2.862770 3/2 + 24 2.866890 3/2 - 25 2.874470 3/2 - 26 2.894490 3/2 + 27 2.902470 5/2 + 28 2.947600 5/2 - 29 2.977000 7/2 + 30 2.990000 9/2 + 31 2.996900 11/2 - 32 3.036000 5/2 + 33 3.079000 1/2 - 34 3.079690 3/2 + 35 3.086000 3/2 - 36 3.116000 1/2 - 37 3.120200 3/2 - 38 3.127000 1/2 + 39 3.132000 7/2 - 40 3.143000 7/2 - ----------------------- * Gamma-ray strength functions for Cu-66 E1: enhanced generalized lorentzian model(EGLO)/10/ ER= 17.96 (MeV) EG= 6.47 (MeV) SIG= 115.18 (mb) M1: standard lorentzian model(SLO) ER= 10.15 (MeV) EG= 4.00 (MeV) SIG= 0.97 (mb) E2: standard lorentzian model(SLO) ER= 15.59 (MeV) EG= 5.32 (MeV) SIG= 1.43 (mb) References 1) A.J.M.Plompen et al., Eur. Phys. J. A 56, 181 (2020) 2) K.Shibata et al., J. Nucl. Sci. Technol. 48, 1 (2011) 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) L.Hao et al., J. Phys. G 35, 095103 (2008) 5) S.Nakayama. J. Nucl. Sci. Technol., 55, 614 (2018) 6) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 7) H.An and Y. C. Cai, Phys. Rev. C 73,054605(2006) 8) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 9) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 10) J. Kopecky et al., Phys. Rev. C 47, 312 (1993)