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Filtering by: Subject Nuclear fuels -- Fluid dynamics Remove constraint Subject: Nuclear fuels -- Fluid dynamics Resource Type Dissertation Remove constraint Resource Type: Dissertation

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  • Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

    Creator:
    Lee, Dongyoung
    Abstract:
    There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive...
    Resource Type:
    Dissertation
    Full Text:
    integral PWR, which consists of nuclear fuel, control rod drives, SG, pressurizer and reactor coolant

  • Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor

    Creator:
    Gradecka, Malwina
    Abstract:
    Since High Temperature Gas-cooled Reactors are being considered as most promising design of upcoming IV Gen reactors, thus key research areas were identified to address safety aspects of this design. Number of simulations and experiments need to be conducted in this field. In this study thermal-hydraulics aspects of coolant flow...
    Resource Type:
    Dissertation
    Full Text:
    production of synthetic fuels. To satisfy future demand for transportation fuel, nuclear process heat may

  • A study of buoyant backflow in vertical injection lines

    Creator:
    King, John Barry
    Abstract:
    In the event of a small break loss of coolant accident (SBLOCA) in a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to compensate for the coolant loss. When this flow rate is less than a critical value, however, the hot fluid in the cold...
    Resource Type:
    Dissertation
    Full Text:
    a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to

  • A general theory of flooding implementing the cuspoid catastrophe

    Creator:
    Lafi, Abd Y.
    Abstract:
    The flooding phenomenon can be defined as the maximum attainable flow condition beyond which the well defined countercurrent flow pattern can no longer exist. Thus the countercurrent flow limit (CCFL) or the flooding limit may be thought of as the flow condition at which the strong interaction between the two...
    Resource Type:
    Dissertation
    Full Text:
    catastrophe AN ABSTRACT OF THE THESIS OF Abd Y. Lafi for the degree of Doctor of Philosophy in Nuclear

  • Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe

    Creator:
    Welter, Kent B.
    Abstract:
    Under simulated accident conditions, tees in the primary coolant loop of a Pressurized Water Reactor (PWR) can deviate from their original design purpose and become separators that effectively remove core heat sink capacity. This method of primary coolant removal is a phenomelogical subset of phase separation known as liquid entrainment,...
    Resource Type:
    Dissertation
    Full Text:
    degree of Doctor of Philosophy in Nuclear Engineering presented on September 25, 2002. Title: Liquid