Experiments on the effects of a spacer grid in air-water two-phase flow

J. Wheeler, T. Worosz, Seungjin Kim

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    Abstract

    Understanding the effects of spacer grids on the coolant flow through a nuclear reactor core is required for best-estimate design and analysis of the plant. The impact of a spacer grid on twophase flows is of particular importance because the geometric effects of the grid can alter the two-phase flow structure and consequently, the mass, momentum, and energy transfer characteristics. Therefore, a scaled separate-effects test facility is constructed to investigate the effects of a spacer grid on the hydrodynamics of air-water two-phase flow through a rod bundle. The test facility is scaled to maintain hydrodynamic and geometric similarity to single- and twophase flows in a conventional pressurized water reactor and to facilitate detailed local measurements of two-phase flow parameters around the simulant fuel rods with a four-sensor conductivity probe. This paper presents measurements of local time-averaged two-phase flow parameters acquired upstream and downstream of the spacer grid with the conductivity probe in a representative subchannel of a 1×3 rod bundle for eight flow conditions. Characteristic features of the development of the two-phase flow parameters along the test section are discussed.

    Original languageEnglish (US)
    Title of host publicationEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting
    PublisherAmerican Nuclear Society
    Pages289-301
    Number of pages13
    ISBN (Electronic)9781632668509
    StatePublished - Jan 1 2014
    EventEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting - Reno, United States
    Duration: Jun 15 2014Jun 19 2014

    Publication series

    NameEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting

    Other

    OtherEmbedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting
    CountryUnited States
    CityReno
    Period6/15/146/19/14

    All Science Journal Classification (ASJC) codes

    • Nuclear and High Energy Physics
    • Geotechnical Engineering and Engineering Geology
    • Nuclear Energy and Engineering

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