In-vessel retention of molten corium: Lessons learned and outstanding issues

Joy L. Rempe, K. Y. Suh, Fan-bill B. Cheung, S. B. Kim

    Research output: Contribution to journalArticle

    80 Scopus citations

    Abstract

    In-vessel retention (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 (LWRs). 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 accident. If it is possible to ensure that the vessel 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 advanced 600 MW (electric) pressurized water reactor (AP600) designed by Westinghouse, which relied upon external reactor vessel cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission approving the design without requiring that certain features common to existing LWRs, such as containment sprays, be safety related. Clearly, ERVC offers the potential to reduce the AP600s construction and operating costs. However, it is not clear that the ERVC proposed for the AP600 could provide sufficient heat removal for higher-power reactors [up to 1500 MW(electric)] without additional enhancements. This paper reviews efforts made and results reported regarding the enhancement of IVR in LWRs. Where appropriate, the paper identifies what additional data or analyses are needed to demonstrate that there is sufficient margin for successful IVR in high-power thermal reactors.

    Original languageEnglish (US)
    Pages (from-to)210-267
    Number of pages58
    JournalNuclear Technology
    Volume161
    Issue number3
    DOIs
    StatePublished - Jan 1 2008

    All Science Journal Classification (ASJC) codes

    • Nuclear and High Energy Physics
    • Nuclear Energy and Engineering
    • Condensed Matter Physics

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