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Filtering by: Subject Pressurized water reactors -- Critical heat flux -- Measurement Remove constraint Subject: Pressurized water reactors -- Critical heat flux -- Measurement Decade 2020-2029 Remove constraint Decade: 2020-2029

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  • Out-of-pile blowdown critical heat flux experiment

    Creator:
    Moussaoui, Musa A.
    Abstract:
    In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is not yet determined whether the use of steady-state CHF methods can accurately predict transient CHF under the conditions of a blowdown due...
    Resource Type:
    Dissertation
    Full Text:
    . Title: Out-of-Pile Blowdown Critical Heat Flux Experiment Abstract approved

  • 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