About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
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| Presentation Title |
Replicating In-Service Hydriding of Zirconium Alloy Fuel Claddings Utilizing a Combined Experimental-Computational Approach |
| Author(s) |
Rishi Pillai, Tracie Lowe, Yi Feng Su, Mackenzie Ridley |
| On-Site Speaker (Planned) |
Rishi Pillai |
| Abstract Scope |
Hydrogen embrittlement in light water reactor fuel cladding is a known issue. Laboratory preparation and characterization of microstructurally relevant hydrogen charged fuel cladding continues to be a challenge. The primary research goal of this study is to investigate the effects of hydrogen on zirconium alloy fuel cladding, specifically focusing on a unique hydriding process under controlled laboratory conditions that aims to replicate the hydride rim microstructure typically observed in high burnup fuel cladding in service. Microstructural examination, coupled with thermodynamic and kinetic modelling approaches, was used to predict hydrogen uptake and hydride precipitation in fuel cladding segments. This comprehensive approach will provide valuable insights into the hydriding behavior of zirconium alloys, thereby enhancing the reliability and safety of nuclear fuel cladding materials. |
| Proceedings Inclusion? |
Planned: |