About this Abstract |
| Meeting |
TMS Specialty Congress 2026
|
| Symposium
|
Energy Materials 2026
|
| Presentation Title |
Thermal Transport of Nuclear Fuels After Irradiation |
| Author(s) |
Zilong Hua, Amey Khanolkar, Shuxiang Zhou, Kaustubh Bawane, Marat Khafizov, David Hurley |
| On-Site Speaker (Planned) |
Zilong Hua |
| Abstract Scope |
The thermal conductivity of nuclear fuels is critical to reactor safety and efficiency. Irradiation-induced defects degrade the thermal conductivity over time, leading to local temperature increases and posing a potential risk of fuel melting. This presentation summarizes our recent investigations at Idaho National Laboratory into the thermal transport behavior of actinide oxides (ThO₂, UO₂, U-ThO₂) and metallic fuel candidates (UZr₂, UN) in both pristine and irradiated states. We examined possible mechanisms of the defect generation and evolution within these materials under extreme conditions and the corresponding thermal property reduction related to the carrier scatterings. This study provides essential insights for optimizing fuel performance codes and developing advanced fuels for future reactors. |
| Proceedings Inclusion? |
Undecided |