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Filtering by: Subject Reactor fuel reprocessing Remove constraint Subject: Reactor fuel reprocessing Committee Member Reese, Steven Remove constraint Committee Member: Reese, Steven 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

  • 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