- Home
- » Tags
- » Uranium carbide
Top View
- Carbide Fuel Development Final Report Period of May 15, 1959 To
- Modeling of the Thermal Behavior of Irradiated Sphere-Pac Mixed Carbide Fuel
- Tested and Analyzed Fuel Form Candidates for Nuclear Thermal Propulsion Applications
- "Diffusion Studies in Uranium Carbide Systems"
- (UB2) Via Carbo/Borothermic Reduction of UO2 Turner, Joel; Martini, Fabio; Buckley, James; Phillips, G; Middleburgh, Simon; Abram, Tim Journal of Nuclear Materials
- Advanced Ceramics for Use As Fuel Element Materials in Nuclear Thermal Propulsion Systems
- Oxidation of UC: an in Situ High Temperature Environmental Scanning Electron Microscopy Study Claudia Gasparrini, Renaud Podor, Denis Horlait, Michael J.D
- Accident-Tolerant Uranium Nitride
- Synthesis of Uranium Carbides Doped by Metal Oxide by Complex Sol-Gel Processes (CSGP)
- Oxidation of Zirconium and Uranium Carbides
- Spent Fuel Reprocessing Options
- Treatment and Recycling of Spent Nuclear Fuel
- Atomic Energy of Canada Limited URANIUM CARBIDE FUEL FOR
- Nuclear Thermal Propulsion Reactor Materials Douglas Burns and Stephen Johnson
- Synthesis and Characterization of Advanced Nuclear Fuels
- More Than 430 Nuclear Power Reactors Are Operating in the World
- Advanced Fuels Modeling: Evaluating the Steady- State Performance of Carbide Fuel in Helium- Cooled Reactors Using FRAPCON 3.4 Luke H
- High Temperature Gas Cooled Reactor Fuels and Materials
- Fuel Fabrication
- Fabrication and First Characterisations of Uranium Carbide Samples
- Review of the NIOSH Site Profile for the Santa Susana Field Laboratory