Calculation of Heat-Bearing Agent's Steady Flow in Fuel Bundle

[摘要] This paper introduces the result of studying the heat exchange in the fuel bundle of the nuclear reactor's fuel magazine. The article considers the fuel bundle of the infinite number of fuel elements, fuel elements are considered in the checkerboard fashion (at the tops of a regular triangle a fuel element is a plain round rod. The inhomogeneity of volume energy release in the rod forms the inhomogeneity of temperature and velocity fields, and pressure. Computational methods for studying hydrodynamics in magazines and cores with rod-shape fuel elements are based on a significant simplification of the problem: using basic (averaged) equations, isobaric section hypothesis, porous body model, etc. This could be explained by the complexity of math description of the three-dimensional fluid flow in the multi-connected area with the transfer coefficient anisotropy, curved boundaries and technical computation difficulties. Thus, calculative studying suggests itself as promising and important. There was developed a method for calculating the heat-mass exchange processes of inter-channel fuel element motions, which allows considering the contribution of natural convection to the heat-mass exchange based on the Navier-Stokes equations and Boussinesq approximation.

[发布机构] Department of Mechanics and Mathematical Modeling, Far Eastern Federal University, Sukhanova St., 8, Vladivostok; 690090, Russia^1;Institute of Applied Math, Far Eastern Department of RAS, Radio St., 7, Vladivostok; 690041, Russia^2

[学科分类] 土木及结构工程学

[关键词] Boussinesq approximations;Curved boundary;Energy release;Infinite numbers;Inhomogeneities;Isobaric sections;Mass-exchange process;Transfer coefficient