Evaluation of an effective diameter to study quenching and dry-out of complex debris bed

N. Chikhi (Corresponding Author), O. Coindreau, L.X. Li, W.M. Ma, Veikko Taivassalo, Eveliina Takasuo, S. Leininger, R. Kulenovic, E. Laurien

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    41 Citations (Scopus)


    Many of the current research works performed in the SARNET-2 WP5 deal with the study of the coolability of debris beds in case of severe nuclear power plant accidents. One of the difficulties for modeling and transposition of experimental results to the real scale and geometry of a debris bed in a reactor is the difficulty to perform experiments with debris beds that are representative for reactor situations. Therefore, many experimental programs have been performed using beds made of multi-diameter spheres or non-spherical particles to study the physical phenomena involved in debris bed coolability and to evaluate an effective diameter. This paper first establishes the ranges of porosity and particle size distribution that might be expected for in-core debris beds and ex-vessel debris beds. Then, the results of pressure drop and dry-out heat flux (DHF) measurements obtained in various experimental setups, POMECO, DEBRIS, COOLOCE/STYX and CALIDE/PRELUDE, are presented. The issues of particle size distribution and non-sphericity are also investigated. It is shown that the experimental data obtained in "simple" debris beds are relevant to describe the behavior of more complex beds. Indeed, for several configurations, it is possible to define an "effective" diameter suitable for evaluating (with the porosity) some model parameters as well as correlations for the pressure drop across the bed, the steam flow rate during quenching and the DHF.
    Original languageEnglish
    Pages (from-to)24-41
    JournalAnnals of Nuclear Energy
    Publication statusPublished - 2014
    MoE publication typeA1 Journal article-refereed
    Event6th European Review meeting on Severe Accident Research, ERMSAR-2013 - Avignon, France
    Duration: 2 Oct 20134 Oct 2013
    Conference number: 6


    • nuclear reactors
    • severe accidents
    • debris bed coolability
    • quenching
    • dry-out heat flux
    • effective diameter


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