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  • Development of a binary mixture gas composition instrument for use in a confined high temperature environment

    Creator:
    Cadell, Seth R.
    Abstract:
    With recent advancements in material science, industrial operations are being conducted at higher and higher temperatures. This is apparent in the nuclear industry where a division of the field is working to develop the High Temperature Gas Reactor and the Very High Temperature Gas Reactor concurrently. Both of these facilities...
    Resource Type:
    Dissertation
    Full Text:
    : _____________________________________________________________________ Brian G. Woods With recent advancements in material science, industrial operations are being

  • 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

  • Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor

    Creator:
    Gradecka, Malwina
    Abstract:
    Since High Temperature Gas-cooled Reactors are being considered as most promising design of upcoming IV Gen reactors, thus key research areas were identified to address safety aspects of this design. Number of simulations and experiments need to be conducted in this field. In this study thermal-hydraulics aspects of coolant flow...
    Resource Type:
    Dissertation
    Full Text:
    Gradecka for the degree of Doctor of Philosophy in Nuclear Engineering presented on June 17, 2015

  • Development of a Novel MEMS Thermal Sensor Array for Pebble Bed HTGRs

    Creator:
    Hertel, Matthew A.
    Abstract:
    A novel high temperature thermal instrument is proposed, which utilizes a dual-sensing platinum resistor encased in a mono-crystalline alpha-alumina (sapphire) substrate. The instrument is comprised of four platinum trace elements, oriented with 90° rotational symmetry atop a 1120 oriented crystal lattice substrate. All four of these sensors measure temperature directly...
    Resource Type:
    Dissertation
    Full Text:
    Head of the School of Nuclear Science and Engineering Dean of the Graduate School

  • An experimental study of laminarization induced by acceleration and curvature

    Creator:
    Jackson, R. Brian
    Abstract:
    The Generation IV Very High Temperature Reactor (VHTR) design is being actively studied in various countries for application due to its inherent passive safe design, higher thermal efficiencies, and proposed capability of providing high temperature process heat. The pebble bed core is one of two core designs used in gas...
    Resource Type:
    Dissertation
    Full Text:
    Engineering presented on June 15, 2012. Title: An Experimental Study of Laminarization Induced by

  • Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility

    Creator:
    Nelson, Benjamin L.
    Abstract:
    The Very High Temperature Reactor (VHTR) has two possible core configurations, a hexagonal prismatic and a pebble bed. It is essential that an experimental facility be built for the validation of computer codes for the safe operation of the VHTR. The scaling of the prismatic core configuration has been analyzed...
    Resource Type:
    Masters Thesis
    Full Text:
    ABSTRACT OF THESIS OF Benjamin L. Nelson for the degree of Master of Science in Nuclear Engineering

  • System model of a natural circulation integral test facility

    Creator:
    Galvin, Mark Robert, 1967-
    Abstract:
    The Department of Nuclear Engineering and Radiation Health Physics (NE/RHP) at Oregon State University (OSU) has been developing an innovative modular reactor plant concept since being initiated with a Department of Energy (DoE) grant in 1999. This concept, the Multi-Application Small Light Water Reactor (MASLWR), is an integral pressurized water...
    Resource Type:
    Dissertation
    Full Text:
    Nuclear Engineering presented on June 5, 2009. Title: System Model of a Natural Circulation Integral Test

  • 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:
    , representing Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

  • A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

    Creator:
    Jackson, R. Brian
    Abstract:
    Downward flow opposing mixed convection conditions have been studied using the FLUENT CFD code. This work was comprised of two primary objectives. The first was to study core channel flow reversal susceptibility in the Gas Reactor Test Section (GRTS) at low flow conditions. The second objective was the development of...
    Resource Type:
    Masters Thesis
    Full Text:
    Jackson for the degree of Master of Science in Nuclear Engineering presented on March 17, 2008

  • Design, fabrication, and characterization of the laser-imaged natural circulation (LINC) facility

    Creator:
    Goodrich, Sam S.
    Abstract:
    Currently there is a great amount of interest in the phenomena of natural circulation as a cooling mechanism for normal operation as well as emergency conditions in nuclear reactors and spent fuel pools. In order to better understand this phenomena for the specific geometry of vertical, heated rods in water,...
    Resource Type:
    Masters Thesis
    Full Text:
    degree of Master of Science in Nuclear Engineering presented on June 21, 2013. Title: Design