Modeling of PANDA isolation condenser experiments with MELCOR and Apros

Tuomo Sevón (Corresponding Author), Seppo Hillberg

    Research output: Contribution to journal › Article › Scientific › peer-review

    Abstract

    Modeling methods were developed for passive cooling systems, in which steam condenses in vertical tubes. Isolation condenser experiments performed in the PANDA facility were calculated with two computer codes: the severe accident code MELCOR, and the process simulation software Apros. Both pure steam tests and tests with steam–non-condensable gas mixtures were calculated. Recommendations are given for MELCOR users regarding an appropriate nodalization, flow path definition, and heat transfer parameters. With proper model parameters and nodalization, both MELCOR and Apros codes are able to calculate the operation of the passive cooling system well.

    Original languageEnglish
    Article number107014
    JournalAnnals of Nuclear Energy
    Volume136
    DOIs
    Publication statusPublished - Feb 2020
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Cooling systems
    Steam
    Gas mixtures
    Accidents
    Experiments
    Heat transfer

    Keywords

    • Apros
    • Condensation
    • MELCOR
    • Passive nuclear safety

    Cite this

    Sevón, Tuomo ; Hillberg, Seppo. / Modeling of PANDA isolation condenser experiments with MELCOR and Apros. In: Annals of Nuclear Energy. 2020 ; Vol. 136.
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    Sevón, T & Hillberg, S 2020, 'Modeling of PANDA isolation condenser experiments with MELCOR and Apros', Annals of Nuclear Energy, vol. 136, 107014. https://doi.org/10.1016/j.anucene.2019.107014

    Modeling of PANDA isolation condenser experiments with MELCOR and Apros. / Sevón, Tuomo (Corresponding Author); Hillberg, Seppo.

    In: Annals of Nuclear Energy, Vol. 136, 107014, 02.2020.

    Research output: Contribution to journal › Article › Scientific › peer-review

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    Sevón T, Hillberg S. Modeling of PANDA isolation condenser experiments with MELCOR and Apros. Annals of Nuclear Energy. 2020 Feb;136. 107014. https://doi.org/10.1016/j.anucene.2019.107014

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