Simulation of thermal neutron transport processes directly from the evaluated nuclear data files

The main idea of the method proposed in this paper is to directly extract the required information for Monte-Carlo calculations from nuclear data files. The method being developed allows to directly utilize the data obtained from libraries and seems to be the most accurate technique. Direct simulation of neutron scattering in thermal energy range using file 7 ENDF-6 format in terms of code system BRAND has been achieved. Simulation algorithms have been verified using the criterion χ2. (orig.)