| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Advanced Characterization and Modeling of Nuclear Fuels: Microstructure, Thermo-physical Properties
|
| Presentation Title |
Structural Analysis of the IPyC/SiC Interface of AGR-2 Irradiated and Safety Tested TRISO Fuel |
| Author(s) |
Rachel L. Seibert, Tyler J. Gerczak, Jesse Werden, Darren Skitt, John D. Hunn |
| On-Site Speaker (Planned) |
Rachel L. Seibert |
| Abstract Scope |
Tristructural-isotropic (TRISO) coated particle fuel from the second Advanced Gas Reactor Fuel Qualification and Development Program irradiation experiment (AGR-2) was studied using focused-ion beam/scanning electron microscopy serial sectioning to analyze the inner pyrocarbon (IPyC)/silicon carbide (SiC) interface. Shared areas, interfaces, and pore/fission product shapes, sizes, and locations were quantitatively analyzed through both automated and manual batch processing of image stacks collected on 12 µm x 12 µm x 12 µm regions of interest. This analysis focused on quantifying the nature of the IPyC/SiC interface to understand its role on structural changes and fission product interactions from the PyC and into the SiC layer under both irradiation and after upper margin safety testing (1800°C, 300 h). |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, |