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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 Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering

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  • Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

    Creator:
    Peguero, Lara M.
    Abstract:
    Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of Nuclear Physics in Uzbekistan. The WWR-SM is a high-power, pool-type research reactor currently utilizing IRT-4M fuel made by a single Russian supplier. A candidate for...
    Resource Type:
    Masters Thesis
    Full Text:
    . The other assembly contains a modified HANARO fuel rod with a reduced fuel meat radius; this smaller

  • A Computational Fluid Dynamic Study on Flow Induced Vibration in Helically Wire Wrapped Rods Under Axial Turbulent Flow

    Creator:
    Winkle, Tristan
    Abstract:
    Vibration of nuclear fuel rods is an area of significance for the long-term safe operation of any nuclear power plant. One mechanism of vibration, flow induced vibration (FIV), must be quantified when designing a new core, such as a sodium fast reactor which employs helically-wrapped wire spacers. Experimental work undertaken...
    Resource Type:
    Masters Thesis
    Full Text:
    test cases to validate Star CCM+ as a computational tool for fuel rod vibration simulations. Finally

  • Feasibility study on a soluble boron-free small modular reactor

    Creator:
    Mart, Justin R.
    Abstract:
    The elimination of soluble boron creates several advantages for Small Modular Reactor (SMR) operation. Most of these advantages are realized through significant core simplification (removal of pipes, pumping, and purification systems), the removal of the corrosive effects of soluble boron, and from improved safety effects. However, removing soluble boron creates...
    Resource Type:
    Masters Thesis
    Full Text:
    advanced control rod algorithm is thus recognized as a viable strategy for boron-free operation for SMRs

  • Development of a Fast Spectrum Test Loop at the Advanced Test Reactor

    Creator:
    Higgins, Anton
    Abstract:
    The United States currently has no infrastructure to provide a fast neutron flux for research purposes. With the increased interest in Sodium Fast Reactor (SFR) technology, this type of infrastructure is necessary for further development of key components such as Versatile Test Reactor. The purpose of this research is to...
    Resource Type:
    Masters Thesis
    Full Text:
    a lower rod thermal power than expected. A parametric study was also conducted to characterize

  • Binary stochastic media transport : a coupled mesh based method

    Creator:
    Barnett, Nathan A.
    Abstract:
    Transport in a binary stochastic media has been an area of interest for many applications over the past three decades. Many different methods have been attempted, most based on the Levermore-Pomraning coupled transport model. However, this method has never been able to correctly solve problems where a large amount of...
    Resource Type:
    Masters Thesis
    Full Text:
    Engineering Presented on July 25, 2008. Title: Binary Stochastic Media Transport: A Coupled Mesh Based

  • Predicting antineutrino source terms from a high temperature gas reactor

    Creator:
    Shaughnessy, Andra L.
    Abstract:
    Since the 1990s, researchers around the world have been creating antineutrino detectors for monitoring power reactors. These detectors have been deployed at light water reactors and are able to determine power levels and burn up throughout a fuel cycle. This technology could allow the IAEA to monitor LWRs remotely and...
    Resource Type:
    Masters Thesis
    Full Text:
    antineutrino energy spectrum emitted by a commercial pres- surized water reactor (PWR). The French are also

  • 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:
    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
    Full Text:
    : 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
    Full Text:
    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
    Full Text:
    The Development of a Mechanistic Critical Heat Flux