High Fidelity Simulation of the Light-to-dense Stratification Transient in the HiRJET Facility

Cheng Kai Tai, Haomin Yuan, Elia Merzari, Igor A. Bolotnov

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

1 Scopus citations

Abstract

Density stratification in a large enclosure is a crucial phenomenon to the heat transfer and the sustainable passive heat removal of a sodium fast reactor during reactivity transients. However, the engineering models are shown to have unsatisfactory performance in predicting the propagation of the stratified front. To support the model development, this work conducted direct numerical simulation using NekRS to study the long stratification transient in the HiRJET experimental facility, which is composed of a box with jets attached to the walls. We consider the transient where the light fluid is injected to the tank containing a denser fluids. Regions with 95% density of the tank fluid and locations with the largest density gradient along the direction of gravity are marked as the mixing zone and the stratified front. Upon the injection, the jet of light fluid bent upward and impinges the top wall of the enclosure. In the early stage of the transient, the stratified front is highly turbulent and blended in the mixing zone. After the initial accumulation, the mixing front shrunk and deviated from the gradually smoothed stratified front towards the leading edge of mixing. Discussions on the potential discrepancies and the assessment of the code's ability to capture long transient are also provided.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1233-1246
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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