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Filtering by: Creator Snook, James R. Remove constraint Creator: Snook, James R. Committee Member Liburdy, James Remove constraint Committee Member: Liburdy, James Committee Member Wu, Qiao Remove constraint Committee Member: Wu, Qiao

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  • Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

    Creator:
    Goodrich, Sam S.
    Abstract:
    In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
    Resource Type:
    Dissertation
    Full Text:
    Wade R. Marcum In recent years, the global nuclear industry has placed a greater emphasis on

  • Predicting mechanical instability of a cylindrical plate under axial flow conditions

    Creator:
    Marcum, Wade R.
    Abstract:
    Five U.S. high performance research reactors (HPRRs) are currently part of an international nonproliferation program with the objective of ultimately converting their highly enriched uranium (HEU) fuel to a new high density, low enriched uranium (LEU) fuel while still maintaining their reactor kinetic and thermal hydraulic performance. A uranium-molybdenum (U-Mo)...
    Resource Type:
    Dissertation
    Full Text:
    DISSERTATION OF Wade R. Marcum for the degree of Doctor of Philosophy in Nuclear Engineering presented on

  • An experimental study of laminarization induced by acceleration and curvature

    Creator:
    Jackson, R. Brian
    Abstract:
    The Generation IV Very High Temperature Reactor (VHTR) design is being actively studied in various countries for application due to its inherent passive safe design, higher thermal efficiencies, and proposed capability of providing high temperature process heat. The pebble bed core is one of two core designs used in gas...
    Resource Type:
    Dissertation
    Full Text:
    ABSTRACT OF THE DISSERTATION OF R. Brian Jackson for the degree of Doctor of Philosophy in Nuclear

  • 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:
    the downcorner side [m] Q Flow rate {m3/s] R Cold leg diameter [m] V Velocity [mis] w Cross