  We present calculations of neutron thermal cross sections, Westcott factors,
resonance integrals, Maxwellian-averaged cross sections and astrophysical
reaction rates for 843 ENDF materials using data from the major evaluated
nuclear libraries and European activation file. Extensive analysis of
newly-evaluated neutron reaction cross sections, neutron covariances, and
improvements in data processing techniques motivated us to calculate nuclear
industry and neutron physics quantities, produce s-process Maxwellian-averaged
cross sections and astrophysical reaction rates, systematically calculate
uncertainties, and provide additional insights on currently available
neutron-induced reaction data. Nuclear reaction calculations are discussed and
new results are presented.
