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Filtering by: Creator Carey, Andrew G. Remove constraint Creator: Carey, Andrew G. Advisor Klein, Andrew C. Remove constraint Advisor: Klein, Andrew C. License All rights reserved Remove constraint License: All rights reserved

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  • Fission Gas Bubble Behavior in Uranium Carbide

    Creator:
    Matthews, Christopher
    Abstract:
    The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution...
    Resource Type:
    Dissertation
    Full Text:
    : Fission Gas Bubble Behavior in Uranium Carbide Abstract approved: Andrew C. Klein The need for cheap

  • Classification Modeling of Nuclear Power Plant Outage Severities with Complement Naïve Bayes and Bidirectional Encoder Representations from Transformers

    Creator:
    Castillo, Michael A.
    Abstract:
    Low-level nuclear power plant outages in the United States can lead to unanticipated costs, potentially compromising the expected operation lifetime of the plant. Nuclear power plants are complex systems of interfacing components and highly regulated processes. This inherent complexity makes predicting outages from system dependencies very challenging. When outages do...
    Resource Type:
    Masters Thesis
    Full Text:
    : ______________________________________________________ Andrew C. Klein Low-level nuclear power plant outages in the United States can lead to

  • Proof of concept of the use of RAVEN and RELAP5-3D for risk informed safety margin characterization

    Creator:
    Riley, Thomas H.
    Abstract:
    This project was a proof of concept of the use of the RAVEN software, a tool developed for the Risk Informed Safety Margin Characterization (RISMC) approach, with RELAP5-3D. This novel approach combines older probabilistic and mechanistic approaches to look at how and why the complex systems of a nuclear power...
    Resource Type:
    Masters Thesis
    Full Text:
    : Andrew C. Klein This project was a proof of concept of the use of the RAVEN software, a tool

  • Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

    Creator:
    Thody, Austin
    Abstract:
    Nuclear Thermal Rocket (NTR) designs have received renewed interest due to their superior thermal efficiencies and a rehabilitated desire for space exploration. This has resulted in improved NTR fuel designs that have unique properties that require investigation and testing in order to be more safely designed and operated. Oak Ridge...
    Resource Type:
    Masters Thesis
    Full Text:
    approved: ______________________________________________________ Andrew C. Klein Nuclear

  • Top-down scaling analysis of the integral reactor vessel test facility

    Creator:
    Graves, Joshua D.
    Abstract:
    Oregon State University has conducted research in collaboration with TerraPower, LLC, to perform a top-down scaling analysis of an integrated test facility. The goal of this facility is to simulate transient and quasi-steady phenomena at a reduced scale, including steady-state operation, pump coastdown, natural circulation, reactor head heat transfer, and...
    Resource Type:
    Masters Thesis
    Full Text:
    Integral Reactor Vessel Test Facility Abstract approved: Andrew C. Klein Oregon State University has

  • Determination of a calculation bias in the MCNP model of the OSTR

    Creator:
    Kitto, Allyson K.
    Abstract:
    Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008, the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a Monte Carlo code that can be used for criticality calculations. Until now, a bias in the calculation...
    Resource Type:
    Masters Thesis
    Full Text:
    : Andrew C. Klein Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008

  • An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

    Creator:
    Onufer, Mark
    Abstract:
    The International Handbook of Evaluated Reactor Physics Benchmark Experiments contains detailed descriptions of many different reactor facilities. A large portion of these experiments have not been fully modeled due to the unavailability of computational power at the time of the experiment’s execution. With the advent of renewed interest in Sodium...
    Resource Type:
    Masters Thesis
    Full Text:
    :__________________________________________________ Andrew C. Klein The International Handbook of Evaluated Reactor Physics Benchmark

  • The Control and Safety Analysis of a Small Fission Surface Power Reactor

    Creator:
    Nelson, Noel B.
    Abstract:
    The NKUA1 is a Small Fission Surface Power (SFSP) space reactor intended for use in upcoming missions to Mars and the moon between the years 2020-2030. The concept of the reactor was created by Dr. Lee Mason and his research team in a joint effort between the Department of Energy...
    Resource Type:
    Honors College Thesis
    Full Text:
    : Andrew Klein The NKUA1 is a Small Fission Surface Power (SFSP) space reactor intended for use in

  • Preliminary framework for the run-ahead predictive simulation software (RAPSS)

    Creator:
    Makinson, Kevin A.
    Abstract:
    The Run-Ahead Predictive Simulation Software (RAPSS) is an architecture designed for faster-than-real-time decision support for operators of complex networks. To enable further development of the RAPSS methodology, the necessary proof of principle is illustrated in two applications: decision support for shift technical advisors in nuclear power plant control rooms (RAPSS-STA),...
    Resource Type:
    Dissertation
    Full Text:
    approved: ________________________________________________________________________ Andrew C. Klein

  • Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

    Creator:
    Deason, Wesley
    Abstract:
    Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant utilizing vented fuel has been characterized using analytical and computational methods. The goal was to increase current understanding of fission product transport in helium-cooled GFRs using vented fuel and to provide a toolset for determining issues which may arise...
    Resource Type:
    Masters Thesis
    Full Text:
    : _____________________________________________________________________ Andrew C. Klein Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant