Detailed analysis of late-phase core-melt progression for the evaluation of in-vessel corium retention

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

    Research output: Contribution to journalArticle

    12 Citations (Scopus)

    Abstract

    Detailed analyses ofa late-phase melt progression in the advanced power reactor (APR)1400 were completed to identify the melt and the thermal-hydraulic states of the in-vessel materials in the reactor vessel lower plenum at the time of reactor vessel failure to evaluate the candidate strategies for an in-vessel corium retention (IVR). Initiating events considered included high-pressure transients of a total loss of feed water (LOFW) and a station blackout (SBO) and low-pressure transients of a 0.0009-m2 small, 0.0093-m2 medium, and 0.0465-m2 large-break loss-of-coolant accident (LOCA) without safety injection. Best-estimate simulations for these low-probability events with conservative accident progression assumptions that lead to reactor vessel failure were performed by using the SCDAP/RELAP5/MOD3.3 computer code. The SCDAP /RELAP5/MOD3.3 results have shown that the pressurizer surge line failed before the reactor vessel failure, which results in a rapid decrease of the in-vessel pressure and a delay of the reactor vessel failure time of ∼40 min in the high-pressure sequences of the total LOFW and the SBO transients. In all the sequences, ∼80 to 90% of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure. The maximum value of the volumetric heat source in the corium pool was estimated as 1.9 to 3.7 MW/m3. The corium temperature was ∼2800 to 3400 K at the time of reactor vessel failure. The highest volumetric heat source sequence is predicted for the 0.0465-m2 large-break LOCA without safety injection in the APR1400, because this sequence leads to an early reactor vessel failure.

    Original languageEnglish (US)
    Pages (from-to)270-281
    Number of pages12
    JournalNuclear Technology
    Volume156
    Issue number3
    DOIs
    StatePublished - Jan 1 2006

    Fingerprint

    progressions
    vessels
    Loss of coolant accidents
    reactors
    evaluation
    Pressure vessels
    Water
    accidents
    Accidents
    blackout
    loss of coolant
    Hydraulics
    heat sources
    safety
    Hot Temperature
    stations
    injection
    power reactors
    pressure vessels
    Temperature

    All Science Journal Classification (ASJC) codes

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

    Cite this

    Park, R. J. ; Kim, S. B. ; Suh, K. Y. ; Rempe, Joy L. ; Cheung, Fan-bill B. / Detailed analysis of late-phase core-melt progression for the evaluation of in-vessel corium retention. In: Nuclear Technology. 2006 ; Vol. 156, No. 3. pp. 270-281.
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    abstract = "Detailed analyses ofa late-phase melt progression in the advanced power reactor (APR)1400 were completed to identify the melt and the thermal-hydraulic states of the in-vessel materials in the reactor vessel lower plenum at the time of reactor vessel failure to evaluate the candidate strategies for an in-vessel corium retention (IVR). Initiating events considered included high-pressure transients of a total loss of feed water (LOFW) and a station blackout (SBO) and low-pressure transients of a 0.0009-m2 small, 0.0093-m2 medium, and 0.0465-m2 large-break loss-of-coolant accident (LOCA) without safety injection. Best-estimate simulations for these low-probability events with conservative accident progression assumptions that lead to reactor vessel failure were performed by using the SCDAP/RELAP5/MOD3.3 computer code. The SCDAP /RELAP5/MOD3.3 results have shown that the pressurizer surge line failed before the reactor vessel failure, which results in a rapid decrease of the in-vessel pressure and a delay of the reactor vessel failure time of ∼40 min in the high-pressure sequences of the total LOFW and the SBO transients. In all the sequences, ∼80 to 90{\%} of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure. The maximum value of the volumetric heat source in the corium pool was estimated as 1.9 to 3.7 MW/m3. The corium temperature was ∼2800 to 3400 K at the time of reactor vessel failure. The highest volumetric heat source sequence is predicted for the 0.0465-m2 large-break LOCA without safety injection in the APR1400, because this sequence leads to an early reactor vessel failure.",
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    Detailed analysis of late-phase core-melt progression for the evaluation of in-vessel corium retention. / Park, R. J.; Kim, S. B.; Suh, K. Y.; Rempe, Joy L.; Cheung, Fan-bill B.

    In: Nuclear Technology, Vol. 156, No. 3, 01.01.2006, p. 270-281.

    Research output: Contribution to journalArticle

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