Global ETD Search

Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.

Results

Showing 1 to 5 of 5 for “"Uranium Carbide"”.

  1. Characterization of Uranium Carbide Microspheres In An Inert Zirconium Carbide Matrix For Gas Fast Reactors

    … of a dispersion/composite fuel involving Uranium Carbide (UC) and Zirconium Carbide (ZrC) have been characterized and studied. Uranium carbide (UC) microspheres produced in the USC-Nuclear Materials Laboratory were subjected to metallographic techniques, and then characterized by …

    south-carolina Repository record for Characterization of Uranium Carbide Microspheres In An Inert Zirconium Carbide Matrix For Gas Fast Reactors (opens in a new tab)

  2. Fluence-limited burnup as a function of fast reactor core parameters

    … fluence in the cladding, especially for reduced uranium enrichment cores using high-albedo MgO reflectors. The intent of this thesis was to determine the best design parameters - fuel type, fuel compound, fuel arrangement, and coolant - while observing these limitations. The ERANOS code was used …

    mit Repository record for Fluence-limited burnup as a function of fast reactor core parameters (opens in a new tab)

  3. Innovative design of uranium startup fast reactors

    … Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, deployment of fast reactors requires decoupling from reprocessing facilities. …

    mit Repository record for Innovative design of uranium startup fast reactors (opens in a new tab)

  4. Design Space Exploration for Salt Cooled Reactor Systems

    … FLiNaK and 3) NaF-ZrF4, and three fuel forms: 1) Uranium Dioxide (UO2), Uranium Carbide (UC), and Fully Ceramic Microencapsulated (FCM) fuel. A package of thermal-hydraulic operating domain search and design optimisation codes was created that can identify the optimum primary and secondary loop …

    cambridge Repository record for Design Space Exploration for Salt Cooled Reactor Systems (opens in a new tab)

  5. A strategy for transition from a uranium fueled, open cycle SFR to a transuranic fueled, closed cycle sodium cooled fast reactor

    … technology. A strategy centered around using uranium-fueled fast reactor cores in a once-through mode-a uranium startup fast reactor (USFR)-decouples fast reactor commercialization from fuel reprocessing and enables transition to a recycle mode once the technology becomes available and …

    mit Repository record for A strategy for transition from a uranium fueled, open cycle SFR to a transuranic fueled, closed cycle sodium cooled fast reactor (opens in a new tab)