Evaluation of Complete Neutron Nuclear Data for 63Cu

Cu is a very important structure material in nuclear fusion engineering. The evaluated neutron nuclear data include total, elastic, non-elastic, total inelastic, inelastic cross sections to 17 discrete levels, inelastic continuum, (n,2n), (n,n’α)+(n.αn’), (n,n’p)+(n,pn’), (n,p), (n,d), (n,t), (n,~3He), (n,α),(n,2p) and capture cross sections. The angular distributions of secondary neutron, the double differential cross sections (DDCS), the gamma-ray production data and the resonance parameters are also included. The data are given in the energy range 10eV to 20 MeV. The evaluation is based on both experimental data measured up to 1998 and calculated data with program UNF. The evaluated data have been adopted into CENDL-3 in ENDF/B-6 format.