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Comparative Thermal Performance of Downdraft and Updraft Forced Convection in a Representative 3×3 PWR Fuel Assembly

  • Oak Ridge National Laboratory

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1105-1120
Number of pages16
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023 → Aug 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
Period8/20/23 → 8/25/23

ASJC Scopus Subject Areas

  • Nuclear Energy and Engineering
  • Instrumentation

Keywords

  • 3×3
  • CFD
  • coefficient
  • downdraft
  • intensity

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