Fracture assessment of reactor circuit (FRAS): Simulation of thermal striping in a HDR experiment

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    Abstract

    Computational Fluid Dynamics (CFD) calculations of thermal striping in a HDR (Heißdampfreaktor) experiment were performed with the commercial Star-CD code. In the experiment, temperature fluctuations caused by instability between layers of cold and hot water flowing in a horizontal pipe were studied. Large-Eddy Simulation (LES) with the Smagorinsky sub-grid scale model was mainly used for turbulence modelling. The vortex method was implemented and validated for simple pipe flow in order to have realistic turbulent inlet conditions for LES. Different geometries and meshes for simulating the experiment were tested. Results obtained with realistic geometry seemed qualitatively correct but the magnitude of temperature fluctuations was too low. This could be connected to too coarse mesh in the model.
    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
    Pages395-402
    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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    Cite this

    Timperi, A. (2009). Fracture assessment of reactor circuit (FRAS): Simulation of thermal striping in a HDR experiment. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report (pp. 395-402). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2466