| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications II
|
| Presentation Title |
Oxidation Response of Irradiated and Unirradiated TRISO Fuel |
| Author(s) |
Tyler J. Gerczak, Darren J Skitt, Rachel L Seibert, John D Hunn |
| On-Site Speaker (Planned) |
Tyler J. Gerczak |
| Abstract Scope |
Potential high temperature gas-cooled reactor (HTGR) accident scenarios involve air ingress into the core subjecting the fuel to oxidizing conditions. Understanding the response of tristructural isotropic (TRISO) coated particle fuel under these accident conditions is necessary to develop predictive models. The Furnace for Irradiated TRISO testing (FITT) was implemented at Oak Ridge National Laboratory (ORNL) to conduct thermal exposures under controlled atmospheres of irradiated TRISO fuel from the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program. Unirradiated and irradiated TRISO particles from the AGR-2 and AGR-5/6/7 experiments have been simultaneously subjected to oxidizing conditions in FITT. The experimental conditions spanned 1200–1400ºC for 50–400 h at pO2 2–21%. Results indicate minor variation in oxidation kinetics between the unirradiated and irradiated TRISO particles although clear variations in oxide morphology are observed for exposures 50–100 h. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, |