Application of continuous-energy Monte Carlo code as a cross-section generator of BWR core calculations

A continuous-energy Monte Carlo code is newly applied for the assembly calculations of actual BWR core analysis. Few-groups cross-sections and related constants (kinetic parameters) were generated by the continuous-energy Monte Carlo code MVP-BURN, and were tabulated for a core simulator. The commercial BWR, HAMAOKA-3 (1100MWe:BWR-5), was analyzed by a coupled neutronic-thermalhydraulic core simulator based on modified one-group diffusion theory using these assembly constants. The calculated core parameters showed good agreement with the results of the on-line core monitoring system of HAMAOKA-3. Consequently, it was confirmed that the present method is applicable to BWR core production calculations. The present method is a particularly attractive candidate for the analysis of advanced BWR fuel assemblies with exotic geometry and high Gd content, due to the features of the continuous-energy Monte Carlo code, i.e., high accuracy and generalized geometry treatment.