| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
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| Presentation Title |
Microstructural Characterization of the SiO2-SiC Interface of Oxidized TRISO Particles |
| Author(s) |
Katherine Montoya, Rachel Seibert, Tyler Gerczak, Elizabeth S. Sooby |
| On-Site Speaker (Planned) |
Elizabeth S. Sooby |
| Abstract Scope |
The SiC layer is the main structural component and barrier to fission product release in the TRISO particle configuration and damage to this layer can compromise the integrity of the fuel form. During an accident scenario, oxidants can be introduced to the core and expose the fuel compacts to an oxidizing atmosphere. Investigation of the stability of TRISO fuel under accident scenarios will aid in furthering the advancement of this fuel type. The compromised compact could allow for the oxidants to be introduced to the TRISO particles, specifically the SiC layer. Presented is a mapping of microstructures associated with the oxidized SiC layer from various thermochemical conditions. Characterization techniques will be used to investigate the microstructure, crystallinity, and composition of the SiO2-SiC interface. Comparisons are planned between the interface structure of irradiated and unirradiated particles. This insight is expected to provide context on the influence of irradiation on oxidation response. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Composites |