Numerical Simulation and Analysis of Simplified Reactor Subchannel

Abstract

In the reactor, the cooling effect of the core directly affects the safety. In this paper, the thermal hydraulic simulation and analysis of the simplified channel in the reactor core are carried out by using the COMSOL Multiphysics software. In the software, the solid fluid heat transfer module and the radiation module between the surfaces are used. The temperature distribution and radiation intensity variation of the fuel rod are obtained. The influence of coolant specific heat capacity, flow velocity and the increase of radius due to expansion of the fuel rod on the heat transfer effect in the simplified channel model of the fuel rod is discussed in this paper.This work provides a useful reference for optimization of reactor thermal design.