Modelling thermal stratification in upper plenum of sodium fast reactor using systems code SAS4A/SASSYS-1 and using CFD

Sundar Namala, Rizwan-Uddin, Tyler Sumner

Research output: Contribution to conferencePaperpeer-review

Abstract

The Gallium thermal-hydraulic facility (GaTE) has been developed [1] to study stratification in the upper plenum of sodium fast reactors during loss of flow transients and in conditions when natural convection becomes an important process to ensure the safety of the reactor. The effects of stratification need to be understood and modelled accurately to predict the response of the reactor during these transients. As a part of this study, the current work focuses on building an accurate model of the GaTE facility using the fast reactor systems analysis code SAS4A/SASSYS-1 [2] and simulate some relevant transient scenarios. The results are compared with experimental data as well as with results obtained using high fidelity computational fluid dynamics (CFD) codes like Star-CCM+. The present study also serves as a validation test for the stratification model in the systems code SAS4A/SASSYS-1.

Original languageEnglish (US)
Pages4854-4863
Number of pages10
StatePublished - 2019
Event18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States
Duration: Aug 18 2019Aug 23 2019

Conference

Conference18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
Country/TerritoryUnited States
CityPortland
Period8/18/198/23/19

Keywords

  • Flow transients
  • Mixing
  • Outlet plenum
  • Sodium fast reactor
  • Stratification

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Instrumentation

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