Polynomial interpolation cross-section parameterization method with the RMC Monte Carlo code

Abstract

Due to the generality and flexibility of Monte Carlo methods in geometric modeling and the challenge for traditional deterministic transport methods in dealing with stochastic media, it is necessary to develop a cross-sectional library generation function using a Monte Carlo method as an interface for full core calculations. In this study, we proposed a cross-sectional parameterization method based on the RMC code for the generation of a few-group cross-sectional library. To perform realistic core calculations, a few-group neutron cross-sectional library of functions of burnup and thermal-hydraulic parameters was prepared in advance. The results of nodal diffusion code CORCA3D full core calculations with RMC B1 corrected cross-sectional sets agree well with those of RMC continuous-energy calculations. Meanwhile, with the consideration of T-H feedback, the results of the CORCA3D full core calculations show good agreement with RMC full core calculations, with a maximum difference in the critical boron concentration of 17 ppm.