In order to gain more insights into the system depressurization and entrainment behavior after actuation of the fourth-stage (ADS-4) valves during a loss-of-coolant-accident, the ADS-4 Depressurization and Entrainment TEst Loop (ADETEL) scaled to AP1000 was constructed to simulate the accident scenario with air-water and steam-water. A brief scaling analysis with emphasis on related thermal hydraulic processes was presented. Entrainment phenomena at vertical up tee branch were observed and analyzed. Preliminary test data of onset of entrainment and entrainment rate were collected with air-water tests and relevant conclusions were obtained.
Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line
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Sun, D, Liu, J, Tian, W, Qiu, S, Su, G, Zhang, P, & Ma, Y. "Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 2A: Thermal Hydraulics. Prague, Czech Republic. July 7–11, 2014. V02AT09A031. ASME. https://doi.org/10.1115/ICONE22-30265
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