| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Advanced Characterization and Modeling of Nuclear Fuels: Microstructure, Thermo-physical Properties
|
| Presentation Title |
Advanced Characterization of Oxidation Behavior of TRISO Fuel SiC Coating |
| Author(s) |
Haiming Wen, Adam Bratten, Visharad Jalan |
| On-Site Speaker (Planned) |
Haiming Wen |
| Abstract Scope |
While high-temperature gas reactors use helium as a coolant, in some accident scenarios significant amounts of air or water vapor can be introduced into the coolant and reactor core. It is important to understand the oxidation and degradation processes of TRISO particles (especially the SiC coating layer) under these conditions. In this study, surrogate TRISO particles were subjected to oxidation in oxygen or water vapor containing environments, using thermogravimetric analysis – differential scanning calorimetry, custom-built tube furnace setup, or in-situ transmission electron microscope. Kinetic parameters of oxidation were measured through the oxidation studies at different temperatures with different partial pressures of oxidants. The microstructures of the SiC coating and the oxide layer after oxidation were carefully characterized via different techniques including scanning electron microscopy, focused ion beam, transmission electron microscopy, and atom probe tomography. The oxidation mechanisms were ascertained in relation to the oxidation conditions and microstructures of the materials. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Ceramics |