Progress on ruthenium release and transport under air ingress conditions

Ari Auvinen (Corresponding Author), G. Brillant, N. Davidovich, R. Dickson, G. Ducros, Y. Dutheillet, P. Giordano, M. Kunstar, Teemu Kärkelä, M. Mladin, Y. Pontillon, C. Seropian, N. Ver

    Research output: Contribution to journalArticleScientificpeer-review

    23 Citations (Scopus)

    Abstract

    A particular concern in the event of a hypothetical severe accident is the potential release of highly radiotoxic fission product (FP) isotopes of ruthenium. The highest risk for a large quantity of these isotopes to reach the containment arises from air ingress following vessel melt-through. One work package (WP) of the source term topic of the EU 6th Framework Network of Excellence project SARNET is producing and synthesizing information on ruthenium release and transport with the aim of validating or improving the corresponding modelling in the European ASTEC severe accident analysis code. The WP includes reactor scenario studies that can be used to define conditions for new experiments.

    The experimental database currently being reviewed includes the following programmes:
    • AECL experiments conducted on fission product release in air; results are relevant to CANDU loss of end-fitting accidents;

    • VERCORS tests on FP release and transport conducted by CEA in collaboration with IRSN and EDF; additional tests may potentially be conducted in more oxidizing conditions in the VERDON facility;

    • RUSET tests by AEKI investigating ruthenium transport with and without other FP simulants;

    • Experiments by VTT on ruthenium transport and speciation in highly oxidizing conditions.

    In addition to the above, at IRSN and at ENEA modelling of fission product release and of fuel oxidation is being pursued, the latter being an essential boundary condition influencing ruthenium release.

    Reactor scenario studies have been carried out at INR, EDF and IRSN: calculations of air ingress scenarios with respectively ICARE/CATHARE V2; SATURNE-MAAP; and ASTEC codes provided first insights of thermal-hydraulic conditions that the fuel may experience after lower head vessel failure.

    This paper summarizes the status of this work and plans for the future.
    Original languageEnglish
    Pages (from-to)3418-3428
    Number of pages11
    JournalNuclear Engineering and Design
    Volume238
    Issue number12
    DOIs
    Publication statusPublished - 2008
    MoE publication typeA1 Journal article-refereed

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