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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 Name Master of Science (M.S.) Remove constraint Degree Name: Master of Science (M.S.) Language English [eng] Remove constraint Language: English [eng] Subject Nuclear reactor accidents Remove constraint Subject: Nuclear reactor accidents

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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