This paper documents the analytical evaluation of a reactor cavity structure subjected to ex-vessel steam explosion loading. The ex-vessel steam explosion may occur during a severe accident scenario after beyond-design-basis earthquake event when the molten core of the failed vessel begins to drop into a flooded reactor cavity area. This causes an impulse load on the reactor cavity that can impose greater demand on the structural components. The structural integrity and leak-tightness of the reactor cavity structure were evaluated using a detailed finite element analysis model. For selected critical loading cases, local damage in close proximity to the explosion locations was visible in the reactor cavity structure. While localized damage was present, the explosion loading cases did not affect the overall stability of the structure and the strain at the liner location was low enough to prevent any tearing of the liner or leakage.
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ASME 2016 Pressure Vessels and Piping Conference
July 17–21, 2016
Vancouver, British Columbia, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5046-6
PROCEEDINGS PAPER
Evaluation of Reactor Cavity Structure for Ex-Vessel Steam Explosion Loading
Michael R. Davieau,
Michael R. Davieau
Sargent & Lundy, LLC, Chicago, IL
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Phuong Hoang,
Phuong Hoang
Sargent & Lundy, LLC, Chicago, IL
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John B. McLean,
John B. McLean
Sargent & Lundy, LLC, Chicago, IL
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Robert W. Hooks
Robert W. Hooks
Sargent & Lundy, LLC, Chicago, IL
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Gunup Kwon
Sargent & Lundy, LLC, Chicago, IL
Michael R. Davieau
Sargent & Lundy, LLC, Chicago, IL
Phuong Hoang
Sargent & Lundy, LLC, Chicago, IL
John B. McLean
Sargent & Lundy, LLC, Chicago, IL
Robert W. Hooks
Sargent & Lundy, LLC, Chicago, IL
Paper No:
PVP2016-63092, V008T08A014; 7 pages
Published Online:
December 1, 2016
Citation
Kwon, G, Davieau, MR, Hoang, P, McLean, JB, & Hooks, RW. "Evaluation of Reactor Cavity Structure for Ex-Vessel Steam Explosion Loading." Proceedings of the ASME 2016 Pressure Vessels and Piping Conference. Volume 8: Seismic Engineering. Vancouver, British Columbia, Canada. July 17–21, 2016. V008T08A014. ASME. https://doi.org/10.1115/PVP2016-63092
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