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Filtering by: Subject Pressurized water reactors -- Critical heat flux -- Measurement Remove constraint Subject: Pressurized water reactors -- Critical heat flux -- Measurement Degree Level Master's Remove constraint Degree Level: Master's

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  • Blowdown transient critical heat flux

    Creator:
    Moussaoui, Musa A.
    Abstract:
    Occurring in the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is the primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is unclear whether the use of steady-state CHF correlations can accurately predict the gross thermal-hydraulic perturbations of a blowdown in a large...
    Resource Type:
    Masters Thesis
    Full Text:
    Reactor CFD Computational Fluid Dynamics CHF Critical Heat Flux CODA Coolant

  • A New Approach of Computational Fluid Dynamics Studying Power Transient Critical Heat Flux

    Creator:
    Chen, Tsung-Wen
    Abstract:
    Power transient boiling has been studied for decades, however, the mechanistic understanding of phenomena which occur during such an event remains incomplete. Due to a dearth of systematic researches, the information of studied phenomenon, detailed physics and applicable hypothesis are very limited. Transient critical heat flux (CHF) is paramount in...
    Resource Type:
    Masters Thesis
    Full Text:
    . Title: A New Approach of Computational Fluid Dynamics Studying Power Transient Critical Heat Flux

  • Assessment of level swell measurements in the OSU APEX Test Facility

    Creator:
    Ellis, Christopher P.
    Abstract:
    The purposes of this paper are to present the results of an experimental effort to measure the level swell in an air/water system and to generate a methodology for determining the volume-averaged void fraction within the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility. The results were then...
    Resource Type:
    Masters Thesis
    Full Text:
    rat ing conditions within a conven ti onal Pressuri zed Water Reactor (PWR). the core is completely