The Process of Cross Section Generation for Reactor Core Simulations

Abstract

Reactor core safety analysis is a complex problem and needs processed input data and cannot be performed without it. For this purpose several nuclear programs exist. A suitable nuclear programs as well as the motivation of the generation are given in this study. This article also summarizes methods and steps needed for the homogenized cross-section generation and provides basic instruction and settings needed to provide these simulations and accomplished this research and gives basic instruction and information about problems and programs which can occur during the cross-section generation. Finally, there is proposed cross-sections structure suitable for safety analysis with reactor core simulator PARCS.