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 language | English (US) |
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Pages | 4854-4863 |
Number of pages | 10 |
State | Published - 2019 |
Event | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States Duration: Aug 18 2019 → Aug 23 2019 |
Conference
Conference | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
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Country/Territory | United States |
City | Portland |
Period | 8/18/19 → 8/23/19 |
Keywords
- Flow transients
- Mixing
- Outlet plenum
- Sodium fast reactor
- Stratification
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Instrumentation