|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Atomistic Simulations of Silicon Carbide Layer in Tristructural Isotropic Fuel Particles
||Cong Dai, Michael Welland
|On-Site Speaker (Planned)
The use of Tristructural Isotropic (TRISO) fuels in advanced reactors greatly inhibits the release of fission gas from fuel as long as the SiC layer remains intact. SiC is a stable and effective coating layer in TRISO fuel particles. Failure mechanisms of the SiC coating layer include metallic fission product degradation, CO corrosion, pressure vessel failure, and oxidation. Experiments found CO corrosion along grain boundaries (GBs) in SiC layer of the TRISO fuel particle. Crystal orientations of adjacent grains and GB plane determine the type of GBs, and they may exhibit different resistance to CO corrosion. Stress-corrosion cracking would occur along low-resistance GBs in SiC layer, which may cause the release of radioactive fission products from the fuel kernel. This work simulate experimentally observed GBs in SiC. Various GB properties are calculated, which can be useful to determine which type of GBs has the highest resistance to CO corrosion.
||Computational Materials Science & Engineering, Nuclear Materials, Modeling and Simulation