Evaluation of RANS vs. LES Simulation of Fluid Flow through 3x3 Rod Bundle with a Simple Spacer Grid as a Precursor to Coupled Fluid-Structure Interaction Simulations

Landon Brockmeyer, Nadish Saini, Adrian Tentner, Elia Merzari

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Scopus citations

Abstract

Fluid flow through rod bundles with spacer grids is one of the most commonly studied phenomena in CFD nuclear engineering. The mixing of flow between subchannels and the pressure drop through the bundle are fundamental quantities useful for comparing and evaluating CFD methods. Less commonly observed and compared are the forces exerted onto the structure by the fluid. The present study seeks to evaluate the use of RANS fluid flow simulations for predicting the structural response to fluid flow. RANS simulations, both with and without wall-functions, are benchmarked against LES simulations of fluid flow at a Reynold's number of 15,000 through a 3x3 fuel rod bundle with a simple spacer grid. Velocity line-plots and pressure drop are compared. Additionally, the distribution of forces on the spacer grid and fuel rods are collected as a function of time and space. The RANS methods are evaluated using the frequency and magnitude of the fluctuating forces on various portions of the structure as compared to LES. This evaluation of the force behavior of the RANS models gives insight into how well they may perform in planned coupled fluid-structure interaction simulations, as well as what flow behavior features the RANS models may be missing.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages366-378
Number of pages13
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period8/20/238/25/23

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Instrumentation

Fingerprint

Dive into the research topics of 'Evaluation of RANS vs. LES Simulation of Fluid Flow through 3x3 Rod Bundle with a Simple Spacer Grid as a Precursor to Coupled Fluid-Structure Interaction Simulations'. Together they form a unique fingerprint.

Cite this