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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 Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering

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  • Critical heat flux estimation for annular channel geometry

    Creator:
    Pagh, Richard T.
    Abstract:
    Critical Heat Flux (CHF) is an important safety parameter for the design of nuclear reactors. The most commonly used predictive tool for determination of CHF is a look-up table developed using tube data with an average hydraulic test diameter of 8 mm. There exist in the world today nuclear reactors...
    Resource Type:
    Dissertation
    Full Text:
    Critical heat flux estimation for annular channel geometry

  • 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

  • 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

  • The Development of a Mechanistic Critical Heat Flux Correlation

    Creator:
    Luitjens, Jeffrey M.
    Abstract:
    A mechanistic based critical heat flux (CHF) correlation has been developed derived from a mass, momentum, and energy balance at a nucleation site for water. The trigger mechanism for the CHF condition is postulated to be related to the maximum boiling frequency on a heated surface. It is observed that...
    Resource Type:
    Dissertation
    Full Text:
    The Development of a Mechanistic Critical Heat Flux