The effective convectivity model for simulation of molten metal layer heat transfer in a boiling water reactor lower head
2009 (English)In: International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009, Atomic Energy Society of Japan , 2009, Vol. 2, 1523-1537 p.Conference paper (Refereed)
The paper is concerned with development of models for assessment of Control Rod Guide Tube (CRGT) cooling efficiency in Severe Accident Management (SAM) for a Boiling Water Reactor (BWR). In case of core melt relocation under a certain accident condition, there is a potential of stratified (with a metal layer atop) melt pool formation in the lower plenum. For simulations of molten metal layer heat transfer we are developing the Effective Convectivity Model (ECM) and Phase-change ECM (PECM). The models are based on the concept of effective convectivity previously developed for simulations of decay-heated melt pool heat transfer. The PECM platform takes into account mushy zone convection heat transfer and compositional convection that enables simulations of non-eutectic binary mixture solidification and melting. The ECM and PECM are validated against various heat transfer experiments for both eutectic and non-eutectic mixtures, and benchmarked against CFD-generated data including the local heat transfer characteristics. The PECM is applied to heat transfer simulation of a stratified heterogeneous debris pool in the presence of CRGT cooling. The PECM simulation results show no focusing effect in the metal layer on top of a debris pool formed in the BWR lower plenum and apparent efficacy of the CRGT cooling which can be served as an effective SAM measure to protect the vessel wall from thermal attacks and mitigate the consequences of a severe accident.
Place, publisher, year, edition, pages
Atomic Energy Society of Japan , 2009. Vol. 2, 1523-1537 p.
Accidents, Binary mixtures, Boiling water reactors, Cooling, Debris, Eutectics, Heat convection, Lakes, Liquid metals, Metals, Mixtures, Nuclear power plants, Solidification, Accident conditions, Boiling water reactor (BWR), Control rod guide tubes, Heat transfer simulation, Modeling for simulations, Molten metal layers, Severe accident management, Solidification and melting, Heat transfer
IdentifiersURN: urn:nbn:se:kth:diva-164543ScopusID: 2-s2.0-84907988397ISBN: 9781617386084OAI: oai:DiVA.org:kth-164543DiVA: diva2:806336
International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009, Shinjuku, Tokyo, Japan, 10 May 2009 through 14 May 2009
QC 201504202015-04-202015-04-172015-06-18Bibliographically approved