VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete

Tuomo Sevon (Corresponding Author), C. Journeau, L. Ferry

    Research output: Contribution to journalArticleScientificpeer-review

    14 Citations (Scopus)

    Abstract

    In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.

    This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.

    This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol% solid fraction when the concrete test section broke, leading to significant spreading.
    Original languageEnglish
    Pages (from-to)224-229
    Number of pages5
    JournalAnnals of Nuclear Energy
    Volume59
    DOIs
    Publication statusPublished - 2013
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Hematite
    Concretes
    Experiments
    Paramagnetic resonance
    Pressure vessels
    Molten materials
    Accidents
    Silica
    Temperature

    Keywords

    • MCCI
    • molten core-concrete interaction
    • severe accident

    Cite this

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    title = "VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete",
    abstract = "In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol{\%} solid fraction when the concrete test section broke, leading to significant spreading.",
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    language = "English",
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    journal = "Annals of Nuclear Energy",
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    VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete. / Sevon, Tuomo (Corresponding Author); Journeau, C.; Ferry, L.

    In: Annals of Nuclear Energy, Vol. 59, 2013, p. 224-229.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete

    AU - Sevon, Tuomo

    AU - Journeau, C.

    AU - Ferry, L.

    PY - 2013

    Y1 - 2013

    N2 - In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol% solid fraction when the concrete test section broke, leading to significant spreading.

    AB - In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol% solid fraction when the concrete test section broke, leading to significant spreading.

    KW - MCCI

    KW - molten core-concrete interaction

    KW - severe accident

    U2 - 10.1016/j.anucene.2013.04.016

    DO - 10.1016/j.anucene.2013.04.016

    M3 - Article

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    SP - 224

    EP - 229

    JO - Annals of Nuclear Energy

    JF - Annals of Nuclear Energy

    SN - 0306-4549

    ER -