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

Tuomo Sevón (Corresponding Author), Christophe Journeau, Lionel Ferry

    Research output: Contribution to journalArticleScientificpeer-review

    17 Citations (Scopus)


    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
    JournalAnnals of Nuclear Energy
    Publication statusPublished - 2013
    MoE publication typeA1 Journal article-refereed


    • MCCI
    • molten core-concrete interaction
    • severe accident


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