Full-Core Computational Fluid Dynamics Simulations Using NekRS

Dillon Shaver, Jun Fang, Haomin Yuan, Misun Min, Elia Merzari, Yu Hsiang Lan

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

1 Scopus citations

Abstract

With the ever-increasing availability of computing power, the size and fidelity of possible simulations in nuclear engineering has been expanding. With each increase, the complexity of phenomena that can be analyzed and better understood also grows. The field of computational fluid dynamics is no different. Simulations of full assemblies that were considered “hero-class” calculations only a few years ago, are now commonplace. It was only a matter of time until full-core-scale simulations became possible. Recent efforts driven jointly by the U.S. Department of Energy's Exascale Computing Project (ECP) and Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program have enabled these simulations. In this paper, we describe the application of computational fluid dynamics to perform full-core large eddy simulations (LES) of pebble bed reactors, Reynolds-averaged Navier-Stokes simulations of a light water small modular reactor, LES of a molten salt fast reactor and LES for a liquid metal microreactor. Additionally, we describe the physical insights gained from each simulation and how the results are being used to drive the next generation of nuclear engineering simulation tools.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1290-1301
Number of pages12
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

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