Improved thermal hydraulic analyses of nuclear reactor and containment (THARE): APROS CCFL model validation

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    Abstract

    The upper tie plate countercurrent flow limitation correlation of APROS was validated against experimental data obtained at a full-scale test facility representing the upper tie plate of the VVER-440 fuel channel. Water and air treated as non-condensable gas were used as the fluids in the simulation. Values for the free parameters of the CCFL correlation were first defined, and then two experiments with different pressures were simulated. The simulation results show good agreement with the experimental results for the mass flow rates for which a quasi-stationary state could be established in the simulation software.
    Original languageEnglish
    Title of host publicationSAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010
    Subtitle of host publicationInterim Report
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages182-190
    ISBN (Electronic)978-951-38-7267-0
    ISBN (Print)978-951-38-7266-3
    Publication statusPublished - 2009
    MoE publication typeNot Eligible

    Publication series

    SeriesVTT Tiedotteita - Research Notes
    Number2466
    ISSN1235-0605

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