| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
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| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
Unraveling the Mechanisms of Oxide Texture Formation on Zirconium Alloys |
| Author(s) |
Junliang Liu, Houzhi Liu, Bhagwat Ghule, Hongliang Zhang, Gene Lucadamo, William Howland, Sergio Lozano-Perez, Chris Grovenor, Adrien Couet |
| On-Site Speaker (Planned) |
Junliang Liu |
| Abstract Scope |
Corrosion of zirconium alloys is limiting the lifespan of fuel cladding in light water reactors. The nanoscale oxide microstructure intricately influences the corrosion performance of these alloys. Generally, alloys with superior corrosion resistance exhibit an oxide layer with a stronger texture and a low density of oxide nano-pores However, the mechanisms by which oxide textures develop are still not well understood, limiting our ability to optimize the oxide texture to improve cladding’s corrosion resistance. Using nanoscale orientation analysis on oxides scaled on single-crystal pure zirconium, we observed multiple orientation relationships (ORs) between monoclinic-zirconia and α-Zr. Specific ORs will be selected during the metal-to-oxide transformation depending on the substrate orientations and lead to the formation of oxides with variations in texture strength. In this presentation, we will elucidate the mechanisms underlying the formation of oxide texture and the influence of substrate orientation on the development of oxide texture and corrosion rates. |
| Proceedings Inclusion? |
Planned: |