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Filtering by: Committee Member Deborah, Pence V. Remove constraint Committee Member: Deborah, Pence V. Advisor Wu, Qiao Remove constraint Advisor: Wu, Qiao

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  • Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification

    Creator:
    Abel, Kent C.
    Abstract:
    The next generation of nuclear safety analysis computer codes will require detailed modeling of two-phase fluid flow. The most complete and fundamental model used for these calculations is known as the two-fluid model. It is the most accurate of the two-phase models since it considers each phase independently and links...
    Resource Type:
    Dissertation
    Full Text:
    V. Pence, Dr. Brian Woods and Dr. Vinod Narayanan, for their valuable comments and their time. I

  • 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:
    appreciation to Dr. Andrew Klein, Dr. Brian Woods, Dr. Deborah Pence, Dr. Kenneth Krane and Dr. Vinod

  • 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:
    point. • Points III-V (for a heat flux controlled surface): At point III where CHF occurs, an unstable

  • Quantified PIRT and uncertainty quantification for computer code validation

    Creator:
    Luo, Hu
    Abstract:
    This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more and more attentions in recent years. U.S. Nuclear Regulatory Commission (NRC) requires the use of realistic best estimate (BE) computer code to follow the rigorous...
    Resource Type:
    Dissertation
    Full Text:
    appreciation to Dr. Jose Reyes, Dr. Brian Woods, Dr. Deborah Pence, Dr. Weidong Wang and Dr. Julia Zhang for