About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
|
| Presentation Title |
Understanding the Role of Hydrides in the Oxidation Behavior of Zircaloy-4 |
| Author(s) |
Josephine C. Hartmann, Chris McRobie, Emma Robertson, Caleb Schenck, Fu-Yun Tsai, Kayla Yano, Dallin Barton, Tamas Varga, Arun Devaraj, Ewa Ronnebro, David Senor, Bharat Gwalani, Elizabeth Jane Kautz |
| On-Site Speaker (Planned) |
Josephine C. Hartmann |
| Abstract Scope |
Hydrides are known to influence oxidation behavior in zirconium alloys, impacting their performance as nuclear fuel cladding. This study investigates the role of hydrides in Zircaloy-4 by comparing an as-received sample with one charged with deuterium. Both were oxidized at 500 °C in flowing oxygen during in situ XRD to monitor structural evolution. Post-exposure characterization using SEM, TEM, and APT revealed differences in oxide morphology, microstructure, and elemental redistribution. The deuterated sample showed enhanced oxide growth and isolated regions of advanced oxidation not present in the uncharged alloy, indicating that hydrides promote faster oxygen ingress and modify diffusion pathways. The role of Sn in oxidation kinetics and redistribution is also discussed. This comparative approach provides mechanistic insight into how hydrides accelerate oxidation in Zircaloy-4, with implications for cladding degradation in reactor environments. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Environmental Effects |