Although no one would like to see, a severe nuclear reactor accident may result in reactor core melting, the fuel melt dropping into water in the reactor vessel, and then interacting with coolant into steam explosion. Steam explosion is a result of very rapid and intense heat transfer and violent interaction between the high temperature melt and low temperature coolant. The timescale for heat transfer is shorter than that for pressure relief, resulting in the formation of shock waves and/or the production of missiles at a later time during the expansion of coolant steam explosion. Steam explosion may endanger the reactor vessel and surrounding structures. During a severe reactor accident scenario, steam explosion is an important risk, even though its probability to occur is pretty low, since it could lead to large releases of radioactive material, and destroy the containment integrity. This study provides a comprehensive review of vapor explosion experiments, especially the most recent ones. In this review, fist, small to intermediate scale experiments related to premixing, triggering and propagation stages are reviewed and summarized in tables. Then the intermediate to large scale experiments using prototypic melt are reviewed and summarized. The recent OECD/SERENA2 project including KROTOS and TROI facilities’ work is also discussed. The studies on steam explosion are vital for reactor severe accident management, and will lead to improved reactor safety.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5785-4
PROCEEDINGS PAPER
In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches
Pei Shen,
Pei Shen
City University of Hong Kong, Hong Kong, China
Search for other works by this author on:
Wenzhong Zhou
Wenzhong Zhou
City University of Hong Kong, Hong Kong, China
Search for other works by this author on:
Pei Shen
City University of Hong Kong, Hong Kong, China
Wenzhong Zhou
City University of Hong Kong, Hong Kong, China
Paper No:
ICONE25-67176, V007T11A017; 16 pages
Published Online:
October 17, 2017
Citation
Shen, P, & Zhou, W. "In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events. Shanghai, China. July 2–6, 2017. V007T11A017. ASME. https://doi.org/10.1115/ICONE25-67176
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