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  • Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

    Creator:
    Riley, Thomas H.
    Abstract:
    The goal of this project was to pave the way for more data-driven decision making when considering safety within Nuclear Engineering by proving the concept of new and innovative accident scenario modeling techniques for the analysis of the economics of nuclear safety margins. To do this, a simple, if extremely...
    Resource Type:
    Dissertation
    Full Text:
    computational power and is very expensive, as the various paths to radionuclide release in an accident

  • 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:
    . Makinson for the degree of Doctor of Philosophy in Radiation Health Physics presented on April 19, 2013

  • 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:
    Characterization of Fission Product Transport in a Gen

  • 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:
    ............................................................................................ 6 2.1 Core Physics Prominent in Sodium Fast Reactors

  • 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:
    in the calculation will result in a roughly linear increase in computational time. However

  • 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:
    Science in Nuclear Engineering presented on December 7, 2012. Title: Top-Down Scaling Analysis of the

  • 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:
    performance in communications sytems (Bononi et al, 2009). Bononi et al lay out a methodology for the use

  • 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:
    study is organized in the following manner: 1) Overview of nuclear reactor physics and key

  • A CFD Analysis of a Single Channel in the Mars Hopper Engine

    Creator:
    Koll, Christopher J.
    Abstract:
    The Mars Hopper is an alternative extraterrestrial vehicle for the collection of samples from the Martian surface. This thesis studied the engine of the Mars Hopper to assess the validity of the current planned launch cycle according to current parameters. To do this, the engine was simplified to an average...
    Resource Type:
    Masters Thesis
    Full Text:
    any computational study the results are merely an educated guess of the physics in the system

  • 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:
    material. Benefiting from modern methods and enhanced computational power, the model created in 3DOT