Simulation of SN transport equation for hexagonal-z reactor using the COMSOL Multiphysics software

Abstract

Detailed neutron transport simulation has undergone much investigation in advanced reactor engineering, where the adaptability of complex geometrics and the simplicity of computational implementation are of great significance. In this paper, a detailed neutron transport module (DNTM) based on the COMSOL Multiphysics platform is developed for hexagonal-z reactor conditions. The multi-group, multidimensional neutron transport SN equation is discretized using the least-squares finite element method and is embedded in COMSOL using the weak form partial differential equation interface without the necessity for additional coding. The proposed DNTM’s feasibility and accuracy are demonstrated through the analysis of three neutron transport benchmarks, encompassing various energy groups, dimensions, and scales. All the numerical results show good agreement with the reference values, indicating that the proposed DNTM in COMSOL can be used to solve the neutron transport process in the hexagonal-z reactor accurately and reliably. This approach may contribute a simple and practical high-fidelity neutronics solving tool and an effective direction to realize multi-physics tight coupling simulations.