Core nuclear reaction database containing evaluated cross sections, spectra, angular distributions, fission product yields, photo-atomic and thermal scattering law data, with emphasis on neutron induced reactions. The database contains nuclear reaction data (neutron cross-sections and others) from main regional and national evaluated data libraries (ENDF/B-7.1, USA; JEFF-3.2, NEA; CENDL-3.1, China; JENDL-4.0u2, Japan; and BROND-2, Russia), all in ENDF format and related data processing computer codes for data preparation for neutron transport and shielding calculations for nuclear reactors and many other applications. .