Comparison of the Material Attenuation Characteristics in Modern Evaluated Nuclear Data Libraries Based on the Numerical Simulation of Ionizing Radiation Transport

Currently, there are a large number of evaluated nuclear data (END) libraries, which are the basis of neutronic calculations. Ultimately, the nuclear facility safety and economics depend on the reliability of the downloaded information. When choosing the tools for modeling and substantiating radiation safety, a specialist needs to have on hand reliable calculation methods and END libraries (neutronic constants). This work compares the calculation results of a number of simple theoretical spherical models of various radii using the modern END libraries, such as ROSFOND, ENDF/B-VII.1, JEFF-3.2, and JENDL-4.0. Calculations and comparisons are made for the total flux and differential neutron and gamma-ray photon leakage spectrum from the surface of spheres of various thicknesses and various materials with a californium neutron source in the center.