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Effect of Corium Non-homogeneity on Nordic BWR Vessel Failure Mode and Timing
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0003-3132-7252
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0002-0683-9136
2015 (engelsk)Konferansepaper, Publicerat paper (Fagfellevurdert)
Abstract [en]

Corium melt fragmentation and cooling in a deep pool of water under reactor pressure vessel are employed as severe accident mitigation strategy in a Nordic-type BWR. Core debris relocated to the lower head inflict significant thermal and mechanical loads on the vessel structures. The mode and timing of the vessel failure, mass and superheat of the ejected melt determine ex-vessel accident progression and risks of steam explosion and formation of a non-coolable debris bed. In this work we consider the effect of in-vessel debris non-homogeneity on the mode of vessel failure. The heat-up, re-melting, melt pool formation, and heat transfer of the debris bed are predicted with the Phase-change Effective Convectivity Model (PECM) implemented in FLUENT® code. Then the obtained thermal load on the vessel wall and structures is used as boundary conditions for a thermo-structural analysis of the BWR lower head using the ANSYS® code. In this paper, a corium debris bed is considered inside vessel lower head inducing thermal load on the wall and structures. The debris bed thermal properties axial distribution is taken as a function of material composition, which is extracted from MELCOR® simulations of core failure and debris bed formation inside the lower plenum. A flat and a concave configuration of the debris bed are considered and results of simulations are compared with those for a homogenous debris bed of the same mass-averaged thermal properties.

sted, utgiver, år, opplag, sider
2015.
Emneord [en]
Severe Accident, BWR Lower Head Failure, Thermo-Mechanical Creep Analysis
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-164897OAI: oai:DiVA.org:kth-164897DiVA, id: diva2:806453
Konferanse
2015 International Congress on Advances in Nuclear Power Plants (ICAPP2015)
Merknad

QS 2015

Tilgjengelig fra: 2015-04-20 Laget: 2015-04-20 Sist oppdatert: 2015-11-17bibliografisk kontrollert

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Villanueva, WalterKudinov, Pavel

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