Experimental and numerical analysis of single pump failure in a HLM reactor

Philippe Planquart, Katrien Van Tichelen

    Research outputpeer-review


    Water modeling of the primary circuit of a new reactor provides useful information on the thermal-hydraulics of the reactors and provides quantitative data for validation of numerical simulation. The accidental scenario of a single
    pump failure in a pool type reactor driven by two pumps is characterized by different thermal zones in the upper plenum [1] which makes this case particular interesting for the validation of CFD. Results of validation of this transient
    test case are presented showing a good comparison between CFD and measurements. Additional work is currently performed on the uncertainty quantification of both the numerical and experimental approaches.
    Original languageEnglish
    Title of host publicationTransactions
    PublisherAmerican Nuclear Society
    Number of pages2
    StatePublished - Nov 2020
    Event2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020 - Virtual, Online
    Duration: 16 Nov 202020 Nov 2020

    Publication series

    NameTransactions of the American Nuclear Society
    PublisherAmerican Nuclear Society
    ISSN (Print)0003-018X


    Conference2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020
    Country/TerritoryUnited States
    CityVirtual, Online

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering
    • Safety, Risk, Reliability and Quality

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