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Showing 1 to 5 of 5 for “"metallic fuels"”.

  1. Modeling of Thermal Transport Properties in Metallic and Oxide Fuels

    … fast reactors that use U-Zr based metallic fuels. In this work, the thermal transport properties of both UO2 based oxide fuels and U-Zr based metallic fuels have been studied. At first, molecular dynamics (MD) simulations were conducted to study the effect of dispersed Xe fission …

    vt Repository record for Modeling of Thermal Transport Properties in Metallic and Oxide Fuels (opens in a new tab)

  2. Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel

    … reliable tool to simulate the behavior of metal fuels in fast reactors. The experimental database necessary to validate the codes is also very limited. The DOE-sponsored Advanced Fuels Campaign (AFC) has performed various experiments that are ready for analysis. Current metal fuel performance …

    unm Repository record for Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel (opens in a new tab)

  3. Modeling special nuclear material diversion from a pyroprocessing facility

    … separating both light water reactor (LWR) and metallic fuels, and inherent proliferation resistance. However, unlike aqueous reprocessing plants, industrial pyroprocessing plants do not yet exist. Similar to safety-by-design in next-generation reactors, reprocessing facilities could be designed …

    uiuc Repository record for Modeling special nuclear material diversion from a pyroprocessing facility (opens in a new tab)

  4. Development of Metallic Fuel Additives and Alloys for Sodium-cooled Fast Reactors

    … to develop effective additives for U-10Zr (wt.%) metallic fuel to mitigate the fuel-cladding chemical interactions (FCCIs) due to fission product lanthanides and to optimize the fuel phase mainly by lowering the gamma-onset temperature. The additives Sb, Mo, Nb, and Ti have been investigated. …

    vt Repository record for Development of Metallic Fuel Additives and Alloys for Sodium-cooled Fast Reactors (opens in a new tab)

  5. Molecular Dynamics Studies of Grain Boundary Mobilities in Metallic and Oxide Fuels

    … ongoing research examining uranium-based based metallic fuels, such as uranium-molybdenum (U-Mo) fuels with low uranium (U) enrichment for research reactors as part of a broader effort to combat nuclear proliferation, and uranium-zirconium-based fuels for Generation IV fast reactors. Each …

    vt Repository record for Molecular Dynamics Studies of Grain Boundary Mobilities in Metallic and Oxide Fuels (opens in a new tab)