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Filtering by: Subject Reactor fuel reprocessing Remove constraint Subject: Reactor fuel reprocessing Degree Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering License All rights reserved Remove constraint License: All rights reserved

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  • 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...
    Resource Type:
    Dissertation
    Full Text:
    produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste

  • SMR full-power scaling analysis and numerical simulation for nuclear hybrid energy system testing

    Creator:
    Hoover, Kyle J.
    Abstract:
    A scaling analysis of the Oregon State University (OSU) - Multi-Application Small Light Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model of the facility was improved. The purpose of this study is to support the research of hybrid energy systems, being led by Idaho National Laboratory...
    Resource Type:
    Masters Thesis
    Full Text:
    Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model of the facility was

  • Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases

    Creator:
    Gullekson, Brian J.
    Abstract:
    Spent nuclear fuel (SNF) resultant from the generation of nuclear power is a chemically and radiologically diverse system which is advantageous to chemically process prior to geologic disposal. Hydrometallurgy is the primary technology for chemical processing for light water reactor spent fuels, where spent fuel is dissolved in an acid...
    Resource Type:
    Masters Thesis
    Full Text:
    water reactor spent fuels, where spent fuel is dissolved in an acid for liquid based separations. The

  • 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:
    Using HANARO Fuel Rods in WWR-SM Reactor Abstract approved: Todd S. Palmer Interest in increased fuel

  • 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:
    , the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a

  • 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...
    Resource Type:
    Dissertation
    Full Text:
    fuel assembly design………………… 45 3.2.2. MASLWR reactor vessel geometry……………………………….. 45 3.5.2. CASMO-4

  • Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

    Creator:
    Alberti, Anthony L.
    Abstract:
    With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
    Resource Type:
    Masters Thesis
    Full Text:
    S. Palmer With the advent of next generation reactor systems and new fuel designs, the U.S. Depart

  • 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:
    ) 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...
    Resource Type:
    Dissertation
    Full Text:
    : Analysis of the Reactor Design using a new LEU Target as Fuel by Andrew J. Hummel

  • Comparison of HEU and LEU neutron spectra in irradiation facilities at the Oregon State TRIGA® reactor

    Creator:
    Schickler, Robert
    Abstract:
    In 2008, the Oregon State TRIGA® Reactor (OSTR) was converted from highly-enriched uranium (HEU) fuel lifetime improvement plan (FLIP) fuel to low-enriched uranium (LEU) fuel. This effort was driven and supported by the Department of Energy's (DoE's) Reduced Enrichment for Research and Test Reactors (RERTR) program. The basis behind the...
    Resource Type:
    Masters Thesis
    Full Text:
    Reactor-2 (PARR-2). Three types of LEU fuel (UO2 with zircaloy cladding, UO2 with aluminum cladding, and