About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Metallic Fuels - Design, Fabrication, and Characterization
|
| Presentation Title |
Advances in the Understanding of Fuel-Cladding Chemical Interaction from FFTF MFF HT9 Clad U-Zr Metal Fuels |
| Author(s) |
Yachun Wang, Tzu-Yi Chang, Bao-Phong H. Nguyen, Alexander Swearingen, Tiankai Yao, Douglas L. Porter, Colby B. Jensen |
| On-Site Speaker (Planned) |
Yachun Wang |
| Abstract Scope |
The operating temperature limits of metal fuels are primarily determined by the microstructural stability of the cladding material. Recent comprehensive post-irradiation examination (PIE) activities have investigated microstructural changes and their impact on the mechanical properties of HT9 cladding. These changes include fuel-cladding chemical interaction (FCCI) induced by lanthanide diffusion, widening of the martensitic lath structure, subgrain growth, potential matrix carbon loss, and the precipitation and coarsening of secondary phases. Collectively, these factors constrain the operating temperatures of metal fuels. This presentation will highlight recent progress on FCCI observed in historic, prototypic full-length MFF fuel pins irradiated at the Fast Flux Test Facility (FFTF). The outcomes of these recent PIE activities contribute to establishing the qualification basis for U-10Zr/HT9 reference fuel, enhancing our understanding and predictive capabilities for future metal fuel developments in sodium fast reactor applications. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |