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Filtering by: Creator French, Rod A. Remove constraint Creator: French, Rod A. Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian Degree Name Doctor of Philosophy (Ph.D.) Remove constraint Degree Name: Doctor of Philosophy (Ph.D.)

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  • 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
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    development of nuclear fuel and materials requires is a continuous e�ort to investigate the acute and

  • A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

    Creator:
    Reynolds, Aaron J.
    Abstract:
    Circulating fuel reactor (CFR) kinetics are characterized by delayed neutron precursor (DNP) drift in addition to the neutronic and thermal hydraulic phenomena typical of other reactor types. This environment can be computationally challenging to model, given that the multiphysics phenomena generally have non-linear interdependencies requiring the use of iterative solution...
    Resource Type:
    Dissertation
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    : A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics Abstract approved

  • 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
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    PWR fuel rod during a RIA is a perfect example of this complication. 1.1 Motivation One scenario

  • 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
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    The Development of a Mechanistic Critical Heat Flux

  • 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
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    heat loss from vertical, heated cylinders by natural convection as a function of rod diameter and

  • Molybdenum-99 production in the Oregon State TRIGA reactor : analysis of the reactor design using a new LEU target as fuel

    Creator:
    Hummel, Andrew J.
    Abstract:
    The most widely used and versatile medical radioisotope today is technetium-99m. Roughly 30 million people depend on this radioisotope for diagnostic procedures each year, and this demand is expected to grow. Although there are numerous ways of procuring this isotope, the most common and most practical, for reasons to be...
    Resource Type:
    Dissertation
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    : Molybdenum-99 Production in the Oregon State TRIGA Reactor: Analysis of the Reactor Design using a new LEU

  • 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
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    63 264 132 Rod pitch 1.62 1.25 n/a Assembly pitch 15.1 21.4 36.1 Pellet diameter (cm) 1.056

  • Reduced Order Modeling of Radiation Diffusion Kinetics via Proper Generalized Decomposition

    Creator:
    Alberti, Anthony L.
    Abstract:
    In this dissertation, we attempt to overcome the "curse of dimensionality" inherent to radiation diffusion kinetics problems by employing a novel reduced order modeling technique known as proper generalized decomposition (PGD). After verifying a proposed PGD algorithm and associated solvers through various tests, we explore its performance for computing reduced-order...
    Resource Type:
    Dissertation
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    ” inherent to radiation diffusion kinetics problems by employing a novel reduced order modeling technique

  • Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

    Creator:
    Misner, Alex C.
    Abstract:
    Antineutrino detectors could provide a valuable addition to current safeguards regimes. Antineutrinos are an attractive emission to monitor due to their low interaction cross-section that prevents them from being shielded and the dependence of their spectrum on the power level and isotopic content of a reactor core. While there are...
    Resource Type:
    Dissertation
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    . Palmer Antineutrino detectors could provide a valuable addition to current safeguards regimes

  • 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
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    power plant by an ejected control rod while at power. When the control rod is ejected in an LWR, a