A defense-in-depth feature for advanced light water reactors to cope with beyond design basis accidents is the ability to cool and stabilize ex-vessel core melt debris. Several international experimental programs have investigated core-concrete interactions and debris cooling of ex-vessel core melts. These experimental programs have identified various phenomena which affect melt coolability and may enhance it. One such phenomenon, melt eruptions, occurs when gas from the underlying decomposing concrete entrains melt up through and onto a solidified crust, which separates the molten melt from the cooling water. Previous modeling and experimental work have shown this cooling mechanism can have a large impact on melt coolability. Previous melt eruption models are reviewed and a new synthesis model is proposed. Reviewing past experimental evidence and modeling efforts indicate the geometry of the flow area impacts the amount of melt ejected. To understand the potential flow area available for melt eruptions, past experimental evidence is reviewed, a steady state analysis of flow area is performed and non-steady state considerations are discussed.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4930-9
PROCEEDINGS PAPER
Towards Understanding Melt Eruption Phenomena During Molten Corium Concrete Interactions
Kevin R. Robb,
Kevin R. Robb
University of Wisconsin-Madison, Madison, WI
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Michael L. Corradini
Michael L. Corradini
University of Wisconsin-Madison, Madison, WI
Search for other works by this author on:
Kevin R. Robb
University of Wisconsin-Madison, Madison, WI
Michael L. Corradini
University of Wisconsin-Madison, Madison, WI
Paper No:
ICONE18-30116, pp. 855-864; 10 pages
Published Online:
April 8, 2011
Citation
Robb, KR, & Corradini, ML. "Towards Understanding Melt Eruption Phenomena During Molten Corium Concrete Interactions." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 2. Xi’an, China. May 17–21, 2010. pp. 855-864. ASME. https://doi.org/10.1115/ICONE18-30116
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