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Filtering by: Alternative title ssim FG 7 Remove constraint Alternative title ssim: FG 7 Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian Degree Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering

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  • Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

    Creator:
    Nes, Razvan
    Abstract:
    An important improvement in the area of reactor core neutronic modeling is the development and use of the methods based on "quasi-diffusion" (QD) low-order equations. This family of methods takes into account the transport exactly using "functionals" computed by solving transport equations, and is amenable to solution with a variety...
    Resource Type:
    Dissertation
    Full Text:
    Razvan Nes for the degree of Doctor of Philosophy in Nuclear Engineering presented on October 7, 2013

  • On the mechanism transition of power transient critical heat flux

    Creator:
    Yan, Yikuan
    Abstract:
    The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
    Resource Type:
    Dissertation
    Full Text:
    fg g g g q h       −  =     (2.4) Kutateladze [7] was successful in producing

  • 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:
    Mixture Pressure and Body Force Π Values ........................... 75 Figure 4-7 Primary Loop Mixture

  • 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:
    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 The Boiling Process 7 2.1 Nucleation in a Pure Liquid (Bulk Boiling

  • Phase distribution parameter determination by neutron radiography

    Creator:
    Skinner, Jesse B.
    Abstract:
    A phase distribution parameter has been added to the one-dimensional two-phase horizontal flow conservation equations. The phase distribution parameter was incorporated into the conservation equations in an attempt to add stability and remove correlation switching by incorporating gravity. Determination of the phase distribution parameter requires an average void fraction profile...
    Resource Type:
    Masters Thesis
    Full Text:
    ................................................................................................. 96 7 Bibliography

  • Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

    Creator:
    Yoshiura, Ramon K.
    Abstract:
    The development of nuclear fuel and materials requires is a continuous effort to investigate the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or other conceivable damage mechanics acquired during normal operation or accident scenarios throughout its lifetime. As in-core fuel property measurement techniques advance to support in...
    Resource Type:
    Dissertation
    Full Text:
    the degree of Doctor of Philosophy in Nuclear Engineering presented on June 7, 2021. Title: Dynamic

  • Development of a Rapid Power Transient Critical Heat Flux Model

    Creator:
    Brown, Emory G.
    Abstract:
    The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...
    Resource Type:
    Dissertation
    Full Text:
    in Nuclear Engineering presented on June 7, 2021. Title: Development of a Rapid Power Transient

  • 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:
    2.3: Flow map for horizontal flow (Mandhane et al., 1974) .......................................... 7