About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
In-Situ Loading and Corrosion of Cr Coated ZIRLO with Scratch Defects |
| Author(s) |
Zhenyu Fei, Peng Wang, Connor Shamberger, Gary Was, Stephen Raiman |
| On-Site Speaker (Planned) |
Zhenyu Fei |
| Abstract Scope |
Accident-tolerant fuel claddings, particularly Cr-coated ZIRLO, offer enhancements to both the safety and economic performance of light water reactors. Since cladding defects remain a key driver of fuel failure, understanding the influence of coating imperfections on corrosion resistance and mechanical integrity is critical. In this study, controlled half-coating and cross-scratch defects were introduced into coated samples to investigate their impact under simulated LWR conditions. Mechanical loading was applied in situ using a custom-designed ring-pull apparatus on tubular cladding specimens, enabling precise evaluation of defect behavior under operationally relevant stresses. Hydrothermal corrosion performance was assessed concurrently with mechanical testing to capture synergistic effects. Stress-strain responses were derived from displacement measurements, while transmission electron microscopy was employed to examine the coating-substrate interface and damage propagation pathways. This presentation will share insights into the coupled mechanical-corrosion behavior of ATF claddings with realistic defect morphologies, offering implications for both fuel design and qualification strategies. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Surface Modification and Coatings |