Evaluation of complete neutron nuclear data for natural nickel

The present work has been done for CENDL-2 (Chinese Evaluation Nuclear Data Library, Second Version) in China and supersedes the CENDL-1, MAT 1280 evaluated by Ma Gonggui (CNDC-8510). Complete neutron nuclear data for natural nickel were evaluated based on both experimental data measured up to 1989 and theoretical calculated with program MUP2. The following neutron production data are given for Ni in the energy range of 1 x 10-'5 eV to 20 MeV in ENDF/B-4 format (MAT = 2280). The cross sections included total, elastic, nonelastic, total inelastic, inelastic cross sections to 21 discrete levels, inelastic continuum, (n,2n), (n,3n), (n,n' α) + (n,αn'), (n,n'p) + (n,pn'), (n,p), (n,d), (n,t), (n,3He), (n,α) and capture cross sections. Extracted data for μ, ξ and γ are also included. Angular distributions and energy spectra of secondary neutron are also given