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Filtering by: Subject Pressurized water reactors -- Corrosion Remove constraint Subject: Pressurized water reactors -- Corrosion Committee Member Wu, Qiao Remove constraint Committee Member: Wu, Qiao

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  • The study of cold leg thermal stratification in APEX-CE

    Creator:
    Antoine, Stephanie Y. L. Antoine
    Abstract:
    This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a precursor leading to a Pressurized Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory...
    Resource Type:
    Masters Thesis
    Full Text:
    Loop Water in Pressurized Water Reactor Cold Legs" [10], Sun et al. studied the phenomenon of

  • Pressure losses across a 180 degree turn in the AP1000 cooling annulus

    Creator:
    Nelson, Roy K.
    Abstract:
    A one-sixth scaled facility was constructed at Oregon State University to determine the pressure losses around Westinghouse's AP1000 Passive Containment Cooling System. An explanation of the AP1000 Passive Containment Cooling System is given. This study examined the pressure loss and loss coefficient around the 180 degree turn of the Passive...
    Resource Type:
    Masters Thesis
    Full Text:
    pressurized water reactor (AP1000) under nominal conditions. Regulators and Designers need to ask how well

  • 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:
    boiling phenomenon under the Pressurized Water Reactor (PWR) condition. Since the direct application of

  • Comprehensive Characterization of Motion of a Helical Coil Due to Flow Induced Vibration

    Creator:
    Harmon, Paul L.
    Abstract:
    Mechanical vibrations compromise the integrity of key components of thermal power plants. Without careful design, strong resonances during steady state operation can wear these components to the point of failure, leading to an unsafe situation that may force a plant to shut down. The purpose of this research is to...
    Resource Type:
    Masters Thesis
    Full Text:
    pressurized water reactor (PWR) at San Onofre, California is currently being decommissioned due to leakage