Review of Worldwide Reactor-Physics Codes and Their Applicability to CANDU® and ACR-1000® Analysis

Abstract

This paper reviews and summarizes the current stochastic (Monte Carlo) codes and deterministic codes used in reactor-physics analysis, with particular emphasis on those aspects relevant to CANDU® and ACR-1000® analysis. The review concentrates on the main features of each reactor-physics toolset with respect to state-of-the-art reactor-physics and numerical modelling aspects, as well as to new methodologies. Where relevant, the applicability of these codes to CANDU and ACR-1000 analysis is covered as well.