| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Microstructure and Chemical States of Fission Products in Irradiated AGR-1 and AGR-2 TRISO Particle UCO Fuel Kernels |
| Author(s) |
Yong Yang, Isabella van Rooyen, Zhenyu Fu, Boopathy Kombaiah |
| On-Site Speaker (Planned) |
Yong Yang |
| Abstract Scope |
Over the past three years, extensive microstructural characterizations were conducted on irradiated AGR-1 and AGR-2 TIRSO fuel UCO kernels. It was found that the irradiated fuel kernel mainly consists of UO2 and UC, while the UO2 is the dominating fuel phase. UC phase contains a significant amount of fission products including Zr, Nb, Mo, Ru, Tc and Rh. The post irradiation safety testing significantly promotes the precipitations of U2Ru(Rh)C2 and UMo(Tc)C2 phases. Fission gas bubbles were only observed in UC or UMoC2 phases. Results from EDS analysis and APT study show that the lanthanides, e.g., Nd, are more likely to enrich within the UO2 phase. Comparison between the AGR-1 and AGR-2 fuel particle kernels shows the differences in irradiated microstructures and chemical states of fission products may result from a combination of irradiation temperature, fuel geometry, and chemical composition. However, irradiation temperature probably plays a more deterministic role. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |