Building a Multiscale Framework: An Overview of the NEAMS thermal-hydraulics Integrated Research Project

Elia Merzari, Arsen Iskhakov, Igor Bolotnov, Nam Dinh, Emilio Baglietto, Annalisa Manera, Dillon Shaver, Yassin Hassan

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

1 Scopus citations

Abstract

GPU-based supercomputing enables a significant advancement in Computational Fluid Dynamics (CFD) capabilities for nuclear reactors. Pre-exascale GPU-based supercomputers such as ORNL's Summit allow for the first time to perform full core CFD calculations with URANS and LES approaches. Key to this has been the development of NekRS, a novel GPU-oriented variant of Nek5000, an open-source spectral element code in development at Argonne National Laboratory. NekRS delivers peak performance for key kernels on the GPUs and good scaling performance even on CPU architectures. Recent performance measurements showed that NekRS, when running on GPUs, outperforms the CPUs by 40x. This manuscript focuses on how these calculations and novel high-resolution experimental data improve the fidelity of traditional approaches such as systems analysis codes, subchannel codes, and Reynolds-Averaged Navier-Stokes. Supercomputing simulation alone cannot impact design and safety analysis without a suitable multiscale framework. An ongoing IRP project led by Penn State is pursuing novel methods for scale bridging. We discuss details of the project, and, in particular, we review some recent progress centered on four industry-driven challenge problems.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages4436-4449
Number of pages14
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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