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  • On the Flow-Induced Vibration of Solitary Wire-Wrapped Cylinders in Axial Flow

    Creator:
    Nixon, Chad A.
    Abstract:
    Vibration of nuclear power plant components can cause fretting wear and fatigue that can eventually lead to component failure. Flexible, high-aspect ratio components under flow, such as the wire-wrapped cylindrical fuel elements in a liquid metal-cooled fast reactor (LMFR) core, are particularly susceptible to vibration due to their low natural...
    Resource Type:
    Dissertation
    Full Text:
    be a member of his research group and to work on such an interesting and challenging project. His

  • Fuel Dispersal Under LOCA Conditions

    Creator:
    Latimer, Griffen D.
    Abstract:
    Most operating power reactors use oxide fuel in the form of uranium oxide (UO2) which is robust against high temperatures but suffers from poor mechanical performance at high levels of burnup. Currently, the maximum average burnup in light water reactors in the US is 62.5 GWd/t, which is partially imposed...
    Resource Type:
    Dissertation
    Full Text:
    : _____________________________________________________________ Wade R. Marcum Most operating power reactors use oxide fuel in the form of uranium oxide

  • Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D

    Creator:
    Marcum, Wade R.
    Abstract:
    Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both...
    Resource Type:
    Masters Thesis
    Full Text:
    Wade R. Marcum for the degree of Master of Science in Nuclear Engineering presented on January 23

  • Predicting mechanical instability of a cylindrical plate under axial flow conditions

    Creator:
    Marcum, Wade R.
    Abstract:
    Five U.S. high performance research reactors (HPRRs) are currently part of an international nonproliferation program with the objective of ultimately converting their highly enriched uranium (HEU) fuel to a new high density, low enriched uranium (LEU) fuel while still maintaining their reactor kinetic and thermal hydraulic performance. A uranium-molybdenum (U-Mo)...
    Resource Type:
    Dissertation
    Full Text:
    DISSERTATION OF Wade R. Marcum for the degree of Doctor of Philosophy in Nuclear Engineering presented on

  • Overstory Growth, Structural Development, and Regeneration Success Following Uneven-Aged Conversion Treatments in Douglas-fir Plantation of the Cascade Range in Oregon

    Creator:
    Marcum, Sean R.
    Abstract:
    Uneven-aged management has been suggested as a method for balancing biodiversity conservation and wood production goals from managed forests in a variety of regions. In coastal Douglas-fir (Pseudotsuga menziesii) forests of the Pacific Northwest, implementation of uneven-aged management is hindered by a lack of experience with uneven-aged silvicultural systems, including...
    Resource Type:
    Masters Thesis
    Full Text:
    AN ABSTRACT OF THE THESIS OF Sean R. Marcum for

  • Predicting critical flow velocity leading to laminate plate collapse—flat plates

    Creator:
    Jensen, P. and Marcum, W. R.
    Abstract:
    The Oregon State University (OSU), Hydro Mechanical Fuel test Facility (HMFTF) is designed to hydro-mechanically test prototypic plate type fuel. OSU’s fuel test program is a part of the Global Threat Reduction Initiative (GTRI), formerly known as the Reduced Enrichment for Research and Test Reactor program. One of the GTRI’s...
    Resource Type:
    Article
    Full Text:
    Plates Jensen, P., & Marcum, W. R. (2014). Predicting critical flow velocity leading to laminate plate

  • Quantification of Reactor Kinetics Parameters during Reactor Transients using Cherenkov Light and Auxiliary Application to Nuclear Safeguards

    Creator:
    Holschuh, Thomas V.
    Abstract:
    The International Atomic Energy Agency (IAEA) is the leading organization for monitoring nuclear facilities worldwide, and the Agency’s methods are constantly developing and improving in an effort to more effectively safeguard nuclear material. As such, the IAEA addresses near and long term risks in order to advance the capabilities of...
    Resource Type:
    Dissertation
    Full Text:
    advisor, Dr. Wade Marcum, who employed me in his research group since my third year of undergrad and

  • Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

    Creator:
    Jensen, Philip
    Abstract:
    The Oregon State University (OSU), Hydro Mechanical Fuel test Facility (HMFTF) is designed to hydro-mechanically test prototypical plate type fuel. OSU's fuel test program is a part of the Global Threat Reduction Initiative (GTRI), formerly known as the Reduced Enrichment for Research and Test Reactor program. One of the GTRI's...
    Resource Type:
    Masters Thesis
    Full Text:
    Abstract approved:____________________________________________________ Wade R. Marcum The Oregon State

  • 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:
    : _____________________________________________________________________ Wade R. Marcum The understanding of critical heat flux is crucial for the safety of nuclear

  • 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:
    approved: _____________________________________________________ Wade R. Marcum The United