Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors
J. Bakosi, M.A. Christon, R.B. Lowrie, L.A. Pritchett-Sheats, R.R., Nourgaliev

TL;DR
This study uses implicit large-eddy simulations to analyze turbulent flow in nuclear reactor rod bundles, aiming to understand flow-induced vibrations causing grid-to-rod fretting and to validate computational methods against experimental data.
Contribution
It demonstrates the viability of implicit large-eddy simulation for accurately predicting hydrodynamic forces in nuclear fuel assemblies, aiding GTRF analysis.
Findings
Flow simulations match experimental data.
Mesh refinement impacts turbulence statistics.
Hydrodynamic forces are key to GTRF wear.
Abstract
The grid-to-rod fretting (GTRF) problem in pressurized water reactors is a flow-induced vibration problem that results in wear and failure of the fuel rods in nuclear assemblies. In order to understand the fluid dynamics of GTRF and to build an archival database of turbulence statistics for various configurations, implicit large-eddy simulations of time-dependent single-phase turbulent flow have been performed in 3x3 and 5x5 rod bundles with a single grid spacer. To assess the computational mesh and resolution requirements, a method for quantitative assessment of unstructured meshes with no-slip walls is described. The calculations have been carried out using Hydra-TH, a thermal-hydraulics code developed at Los Alamos for the Consortium for Advanced Simulation of Light water reactors, a United States Department of Energy Innovation Hub. Hydra-TH uses a second-order implicit incremental…
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