About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Metallic Fuels - Design, Fabrication, and Characterization
|
| Presentation Title |
Scaling Irradiation Behaviors: Examining Steady-State Swelling, Redistribution, and Fission Gas Release in Larger Diameter U-Zr Fuel Pins |
| Author(s) |
Allison R. Probert, Jason Schulthess, Colby Jensen, Assel Aitkaliyeva |
| On-Site Speaker (Planned) |
Allison R. Probert |
| Abstract Scope |
As priority candidate fuels for near-term sodium-cooled fast reactor (SFR) deployment, understanding the impact of U-Zr pin geometry on irradiation performance is crucial. This study investigates two U-Zr fuel pins with peak burnups of 7.3 and 7.4 at.% previously irradiated in EBR-II to generate performance data for larger diameter fuel pins. Axial elongation and outer cladding diametral strain were quantified using neutron radiography and element contact profilometry. One pin underwent destructive examination to determine fractional gas release via the fission gas assay, sample, and recharge (GASR) system and was sectioned for optical and scanning electron microscopy to analyze constituent redistribution and microstructural zoning. Results provide insights into geometry-dependent behaviors and discrepancies when compared to typical EBR-II diameter samples. These findings are valuable for guiding changes in fuel design and utilizing historical and accelerated performance data to SFR deployment. |
| Proceedings Inclusion? |
Planned: |