Research on Multi-Scale Coupling Program Based on Lead Bismuth Fast Reactor

Abstract With the increasing emphasis on the refinement of reactor thermal hydraulic calculations, research on multi-scale coupled models of nuclear reactor thermal hydraulic has also developed. This article utilizes the self-developed lead bismuth system analysis program SACLER, combined with the mature commercial CFD software FLUENT, to develop a coupled program suitable for 1D/3D calculations of lead bismuth fast reactors. In order to ensure the accuracy of the developed coupling program, the calculation function of the developed coupling program was first verified through a simple circular tube case. The coupling program matches well with the data calculated by SACLER and FLUENT respectively, with temperature and flow rate errors within 10%. Subsequently, the response of the coupling program to the thermal hydraulic phenomena of the lead bismuth reactor under transient operating conditions was explored, and the transient experiment on the NACIE facility was simulated. The calculation results showed that the coupling program was in good agreement with the experimental results and could effectively simulate the changes in transient thermal hydraulic parameters.