Gas Ingress during Side Vessel Break: Experiments and Numerical Simulations with a Simplified Pool-type Scaled Water Model

M. Faruoli, M. Delsipee, Ph Planquart, G. Scheveneels, B. Yamaji

Research outputpeer-review

Abstract

In the safety analysis of a pool-type liquid metal cooled reactor, the scenario of a large break of the reactor vessel is evaluated. Among the different possibilities the fall of the full bottom of the reactor vessel is analyzed as a bounding case for possible ingress of gas. It is analysed whether gas from the surroundings might enter the system and, more specifically, enter the core. The presence of gas would interrupt the cooling of the core region. A water model has been designed and studied both experimentally and numerically in several conditions, to evaluate the amount of gas entering from the side break of the vessel, taking into account different falling heights of the bottom of the vessel and to validate the ability of CFD to correctly reproduce the phenomena observed. The experimental data obtained with water with the simplified configuration were compared with a predictions by a CFD model with a 2D-axisymmetric domain. This confirmed the ability of CFD model to correctly predict the phenomena.

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages2534-2548
Number of pages15
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event2023 - NURETH: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Washington Hilton, Washington D.C.
Duration: 20 Aug 202325 Aug 2023
https://www.ans.org/meetings/nureth20/

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference2023 - NURETH
Abbreviated titleNURETH-20
Country/TerritoryUnited States
CityWashington D.C.
Period2023-08-202023-08-25
Internet address

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Instrumentation

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