| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
In-Situ Loading and Corrosion of Coated Zircaloy 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 (ATF) claddings, specifically Cr-coated Zircaloy, have potential to improve light water reactor (LWR) safety and economy. Because cladding defects are a prime cause of fuel failure, it is important to investigate how cladding with coating defects impacts corrosion and mechanical performance. For this work, scratch defects were introduced into cladding samples, which were then subjected to stress in simulated LWR environments. To evaluate the survivability of the coating and assess the impact of coating defects on hydrothermal corrosion. In-situ loading was applied on tubular samples using a ring-pull apparatus. To examine the mechanical effects on the coating and sample substrate, varying levels of coating defects were introduced at high-stress locations. Stress-strain curves were obtained using displacement data, and the coating-substrate interface was characterized with transmission electron microscopy. This talk will present new data investigating the mechanical, corrosion, and combined mechanical-corrosion performance of ATF cladding with representative defects. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, |