During a hypothetical Severe Accident (SA), core damage is to be expected due to insufficient core cooling. If the lack of core cooling persists, the degradation of the core can continue and could lead to the presence of corium in the lower plenum. There, the thermo-mechanical attack of the lower head by the corium could eventually lead to vessel failure and corium release to the reactor cavity pit. In this paper, it is described how the international state-of-the-art knowledge has been applied in combination with plant-specific data in order to obtain a custom Severe Accident Management (SAM) approach and hardware adaptations for existing NPPs. Also the interest of Tractebel Engineering in future SA research projects related to this topic will be addressed from the viewpoint of keeping the analysis up-to-date with the state-of-the art knowledge.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Ex-Vessel Coolability Analysis for a Belgian NPP
Jarne R. Verpoorten,
Jarne R. Verpoorten
Tractebel Engineering, Brussels, Belgium
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Miche`le Auglaire,
Miche`le Auglaire
Tractebel Engineering, Brussels, Belgium
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Frank Bertels
Frank Bertels
Tractebel Engineering, Brussels, Belgium
Search for other works by this author on:
Jarne R. Verpoorten
Tractebel Engineering, Brussels, Belgium
Miche`le Auglaire
Tractebel Engineering, Brussels, Belgium
Frank Bertels
Tractebel Engineering, Brussels, Belgium
Paper No:
ICONE17-75456, pp. 551-561; 11 pages
Published Online:
February 25, 2010
Citation
Verpoorten, JR, Auglaire, M, & Bertels, F. "Ex-Vessel Coolability Analysis for a Belgian NPP." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 551-561. ASME. https://doi.org/10.1115/ICONE17-75456
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