About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
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Synergistic Irradiation, Corrosion, and Microstructural Evolution in Nuclear Materials
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Presentation Title |
Ion Irradiation Study of Polymer Derived SiFeOC-C-SiC Composite |
Author(s) |
Kathy Lu, Sanjay Kumar Singh |
On-Site Speaker (Planned) |
Kathy Lu |
Abstract Scope |
Silicon oxycarbides (SiOCs) are known for their resistance to crystallization, oxidation, and creep at high temperatures. There is great potential for the development of uniform C-SiOC coatings for TRISO fuels in advanced nuclear reactors. Use of iron precursor in SiOC not only helps the formation of nanodomains of β-SiC and FeSi but also enhances the mechanical integrity of the C-SiOC coatings. In this study, SiFeOC-C-SiC ceramics are prepared using a polymer derived method and irradiated using 400 keV Kr ions to 10 and 50 dpa at room temperature and 600°C. The effect of nanodomain interfaces (graphite, SiC, Fe and Fe3Si) in acting as a point defect sinks to mitigate the radiation tolerance and swelling are investigated. Oscillation of free volume or local bonding arrangement to recover itself by self-healing mechanism is elucidated. The effects of ion irradiation on the mechanical properties are studied using nano-indentation. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Composites, Characterization |