Core melt stabilization concepts for existing and future LWRs and associated R&D needs
2015 (English)In: International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, Vol. 9, 7578-7592 p.Conference paper (Refereed)Text
In the event of a severe accident with core melting in a NPP the stabilization of the molten corium is an important mitigation issue, as it can avoid late containment failure caused by basemat penetration, overpressure, or severe damage of internal structures. The related failure modes may result in significant long-term radiological consequences and high related costs. Because of this, the licensing framework of several countries now includes the request to implement mitigative core melt stabilization measures. This does not only apply to new builds but also to existing LWR plants. The paper gives an overview of the ex-vessel core melt stabilization strategies developed during the last decades. These strategies are based on a variety of physical principles like: melt fragmentation in a deep water pool or during molten core concrete interaction with top-flooding, water injection from the bottom (COMET concept), and retention in an outside-cooled crucible structure. The provided overview covers the physical background and functional principles of these concepts, as well as their status of validation and, if applicable, the remaining open issues and R&D needs. For concepts based on melt retention inside a cooled crucible that reached sufficient maturity to be implemented in current Gen-III+ designs, like the VVER-1000/1200 and the EPR™, more detailed descriptions are provided, which include key aspects of the related technical realization. The paper is compiled using contributions from the main developers of the individual concepts.
Place, publisher, year, edition, pages
2015. Vol. 9, 7578-7592 p.
Core catcher, LWR, Severe accident mitigation
IdentifiersURN: urn:nbn:se:kth:diva-187404ScopusID: 2-s2.0-84964068542ISBN: 978-151081184-3OAI: oai:DiVA.org:kth-187404DiVA: diva2:930711
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015; Chicago; United States
QC 201605252016-05-252016-05-232016-05-25Bibliographically approved