Reactor Core Sub-Assembly Simulations Using a Stabilized Finite Element Method

Abstract

This paper presents a methodology for solving thermal-hydraulic flows that are prototypical to nuclear reactors, using a stabilized finite element method. The discrete equations are solved using a fully-coupled algebraic multigrid preconditioned Newton-Krylov iterative solver. The prototype problem of interest is a spatially evolving flow through a 3x3 rod bundle geometry including spacer grid and mixing vanes, which is modeled using large eddy simulation at different spatial resolutions. The results demonstrate trends towards convergence of mean values in the far field (as mesh resolution increases), though, the flow field just downstream of the mixing vanes will require greater resolution to capture, than is presented here.