Corium retention for high power reactors by an in-vessel core catcher in combination with External Reactor Vessel Cooling

• Published in: Nuclear engineering and design 2004-05, Vol.230 (1), p.293-309
• Main Authors: Rempe, J.L., Knudson, D.L., Condie, K.G., Suh, K.Y., Cheung, F.-B., Kim, S.-B.
• Format: Article
• Language: English
• Subjects: accident; ACCIDENTS; Applied sciences; CONTAINMENT; Controled nuclear fusion plants; CORE CATCHERS; CORIUM; corium retention; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; inadequate cooling; Installations for energy generation and conversion: thermal and electrical energy; KAERI; MANAGEMENT; NUCLEAR ENERGY; Nuclear fuels; NUCLEAR POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; reactor; REACTOR ACCIDENTS; REACTOR VESSELS; REMOVAL; RETENTION; SAFETY; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2003.11.031

If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel lower head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe Pressurized Water Reactor (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for in-vessel retention (IVR), resulted in the United States Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing Light Water Reactors (LWRs). Accordingly, IVR of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors. However, it is not clear that currently-proposed methods to achieve ERVC will provide sufficient heat removal for higher power reactors. A US–Korean International Nuclear Energy Research Initiative (INERI) project has been initiated in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) will determine if IVR is feasible for reactors up to 1500 MWe. This paper summarizes results from the first year of this 3-year project.