| Objective | This facility is utilized to investigate the influence of specific factors, such as pressure, velocity, temperatures, mixture composition, and more, on the rate of condensation and the flow of local species. By manipulating and controlling these factors in experimental setups, researchers can gain insights into the mechanisms and behaviours associated with condensation processes. | This facility is employed to probe interconnected phenomena, encompassing the combined effects of gas injection and the process of condensation, natural circulation and stratification, distribution and the effects of depletion, the distribution of condensate on walls, the creation of fog, and the dynamic thermal response of heat-conducting walls. By scrutinizing these interconnected phenomena in a regulated experimental environment, researchers can acquire insights into the complex dynamics and behaviours that transpire during severe accidents in nuclear reactors. | This facility is employed to reproduce mixing and stratification phenomena observed in scenarios involving the combination of steam with air and steam with helium. It encompasses the sequential injection of steam-helium into an air-filled facility to scrutinize the effects of the concurrent presence of air and helium gas on flow conduct. Additionally, the facility is used to investigate the independent and interconnected impacts of the steam jet on the disruption of stratification. It also allows for studying the influence of safety components and the abrupt opening of hatches that serve as barriers between the two volumes on flow transport. By conducting experiments in this facility, researchers can gain valuable insights into the complex interactions and behaviours of different gases in various scenarios, enhancing our understanding of flow dynamics during severe accidents in nuclear reactors. | The facility is utilized to validate the accuracy of thermal-hydraulic codes on a large scale. It allows researchers to investigate the interactions of various phenomena, such as steam condensation, stratification, turbulence, and buoyancy forces. By comparing the experimental results obtained from the facility with the predictions of the thermal-hydraulic codes, researchers can verify the reliability and accuracy of these codes in simulating and predicting complex thermal-hydraulic behaviours during severe accidents in nuclear reactors. |
