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Filtering by: Creator Brevig, Rod E. Remove constraint Creator: Brevig, Rod E. Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian

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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 Korean-made High-flux Advanced Neutron Application Reactor (HANARO) fuel rod, which maintains the

  • 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:
    compares the amplitude and frequency of vibration between simulated and experimental wire-wrapped rod

  • 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:
    and end of cycle. Investigations of additional strategies involving an advanced control rod

  • 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

  • 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:
    outlet was reached. The fuel rod radial temperature profile was lower than was expected, likely due to

  • 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
    Full Text:
    ..................... 130 Figure 5.6 Custom heater rod cross-sectional diagram example ............................ 134

  • Modeling the Oregon State University TRIGA Reactor Using the Attila Three-Dimensional Deterministic Transport Code

    Creator:
    Keller, S. Todd
    Abstract:
    Attila is a state-of-the-art radiation transport based code that is efficient, accurate and straightforward to use. Geometric information is input to the code as CAD drawings. Material property information is input as a cross section library. The user has full control over standard transport options and output reports. In phase...
    Resource Type:
    Masters Thesis
    Full Text:
    ........................................................................ 117 E Full Core Depletion Calculation

  • 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:
    . . . . . . . . . . . . . . . . . . . . . . . . . 191 D Group Constant Generation with SCALE . . . . . . . . . . . . . . . . 194 E QD Boundary

  • 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
    Full Text:
    ..............................................................................67 4.1.3 Rod Worth

  • 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:
    Fuel Rod . . . . . . . . . . . . . . . . . . . . . . . . . 54 C Illustration of NEWT