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  • The chemistry of acetohydroxamic acid related to nuclear fuel reprocessing

    Creator:
    Matteson, Brent Searle
    Abstract:
    Used Nuclear Fuel (UNF) contains transuranic (TRU) elements and numerous fission products as a result of the uranium fission process and neutron activation that occur in commercial light water power reactors. Recent environmental and nuclear proliferation concerns have spawned the development of advanced reprocessing techniques to close the nuclear fuel...
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    Dissertation
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    advanced reprocessing techniques to close the nuclear fuel cycle. By separating specific elemental groups

  • Investigation of mixed N,O-donor dipicolinamide derivative ligands for use in nuclear fuel separations

    Creator:
    Lapka, Joseph
    Abstract:
    In this work, three isomeric forms of N, N'-diethyl, N, N'-ditolyldipicolinamide (EtTDPA) were synthesized. The elements thorium through americium, which make up a significant portion of the actinides in used nuclear fuel (with the exception of curium), and two fission products, molybdenum and technetium, were tested for their ability to...
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    Dissertation
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    used fuel reprocessing. Degradation products were determined and the effect of their presence on

  • Aqueous complexation of citric acid and DTPA with selected trivalent and tetravalent f-elements

    Creator:
    Brown, M. Alex
    Abstract:
    Carboxylic acids have played an important role in the field of actinide (An) and lanthanide (Ln) separations and the reprocessing of irradiated nuclear fuel. Recent bench-scale experiments have demonstrated that 3-carboxy-3-hydroxypentanedioic acid (citric acid) is a promising aqueous complexant that can effectively aid in the separation of transition metals from...
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    Dissertation
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    reprocessing of irradiated nuclear fuel. Recent bench-scale experiments have demonstrated that 3-carboxy-3

  • Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

    Creator:
    Gullekson, Brian J.
    Abstract:
    Partitioning of trivalent actinides (in particular, americium and curium) from the fission produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste disposal. Several solvent extraction processes have been developed to address these chemically difficult separations. The historically employed TALSPEAK Process utilizes di-2-ethylhexyl...
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    Dissertation
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    produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste

  • Numerical solutions of the neutron transport equation

    Creator:
    Skeen, David Roy
    Abstract:
    Because of the high cost of fuel for nuclear reactors, fuel cycle costs must be predicted accurately. This leads to the high cost computer computations and a search for cheaper yet still accurate methods. For this paper we have chosen to study an alternate method for calculating thermal neutron cell...
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    Dissertation
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    studies are expensive. For an example, let us examine a fuel management program. A typical reactor fuel

  • A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

    Creator:
    Almarshad, Abdullah I. A.
    Abstract:
    A model has been developed to predict the long-term oxidation rate of Zircaloy-4 for ex-reactor (autoclave) and in-reactor (PWR) environments and operating conditions. A computer program has been written to solve the oxygen diffusion equation by employing a fully implicit finite difference method for a one dimensional cylindrical geometry. The...
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    Dissertation
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    oxide formed on the waterside surface of 132 reactor-irradiated rods with various fuel burnups. The

  • Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

    Creator:
    Al-Kheliewi, Abdullah S.
    Abstract:
    A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...
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    Dissertation
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    , where t is a reactor transient time in seconds, the fuel temperature does not exceed the melting

  • Design and analysis of a nuclear reactor core for innovative small light water reactors

    Creator:
    Soldatov, Alexey I.
    Abstract:
    In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...
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    Dissertation
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    fuel assembly design………………… 45 3.2.2. MASLWR reactor vessel geometry……………………………….. 45 3.5.2. CASMO-4

  • 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...
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    Dissertation
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    ) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an

  • 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...
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    : Analysis of the Reactor Design using a new LEU Target as Fuel by Andrew J. Hummel