Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors

摘要

The aim of this study is to validate the reactor physics lattice transport code DRAGON5 and the Monte Carlo code OpenMC by neutronic analysis of critical experiments of light water cores. In this work the analysis of integral parameters of five light water reactor critical experiments TRX-1, TRX-2, BAPL-1, BAPL-2, and BAPL-3 is achieved based on evaluated nuclear data library ENDF/B-VII.1. BAPL and TRX experiments provide experimental buckling and are suitable benchmark lattices for validating the deterministic reactor physics lattice transport code DRAGON5 and the stochastic OpenMC code as well as evaluating nuclear data library. The integral parameters of the abovementioned critical experiments are calculated using DRAGON5 and OpenMC codes. To assess our calculation scheme the calculated integral parameters are compared to the measured values as well as the earlier published MCNP results based on the Chinese evaluated nuclear data library CENDL-3.0. Our calculations led to results in good agreement with the experiment and the earlier MCNP calculation results. Therefore, this study reveals the potential validation of the reactor physics lattice transport code DRAGON5 and the Monte Carlo code OpenMC using ENDF/B-VII.1 nuclear data library.