NSUF 24-5134: Nanostructural Analysis of Cold-Sprayed Cr-Coated Zircaloy-4 Under Proton Irradiation and Corrosion
The cold-sprayed Cr coating on Zircaloy-4 is a promising, cost-effective method for creating high-quality, corrosion-resistant cladding for accident-tolerant fuel (ATF) applications. However, interdiffusion between the Cr coating and Zr substrate poses significant challenges, including reduced coating longevity, formation of Kirkendall cavities, and increased brittle thermo-shock behavior. To address these issues, this study investigates the effects of proton irradiated and autoclave exposure on a cold-sprayed Cr-coated Zircaloy-4 using atom probe tomography (APT).
The Cr-coated Zircaloy-4 samples were subjected to proton irradiation up to 5 dpa at 350°C to promote interdiffusion, followed by a 90-day corrosion study in simulated PWR water chemistry at 320°C. The study will compare four sample conditions: non-irradiated (NI), proton-irradiated (350C-5dpa), non-irradiated and corroded (NI-90), and proton-irradiated and corroded (350C-5dpa-90). APT will be employed to analyze the surface oxide, oxide/coating interface, bulk coating, and coating/substrate interface before and after irradiation and corrosion.
The objectives include understanding the microstructural evolution of the Cr coating and its interface under irradiation, identifying the impact of irradiation on interfacial chemistry, and evaluating the influence of these changes on corrosion behavior. By elucidating the precipitates and segregation behavior at the nanoscale, this study aims to provide detailed insights into the Cr-Zr interdiffusion and its effects on the mechanical integrity and performance of the coated cladding.
The findings will guide the selection of appropriate diffusion barrier materials and optimize coating designs to enhance the safety and reliability of nuclear fuel cladding. This research will significantly contribute to the development of advanced ATF claddings, improving their performance under both normal and accident conditions in nuclear reactors.
Додаткова інформація
| Поле | Значення |
|---|---|
| Awarded Institution | University of Michigan-Ann Arbor |
| Embargo End Date | 2026-06-23 |
| Facility Tech Lead | Kevin Field, Mukesh Bachhav |
| NSUF Call | FY 2024 RTE 3rd Call |
| PI | Peng Wang |
| PI Email | [email protected] |
| PI Phone Number | 734 763 3116 |
| PIE Facilities | Microscopy and Characterization Suite |
| Prep Facilities | Michigan Ion Beam Laboratory |
| Project Member | Dr. Peng Wang, Research Scientist - University of Michigan (https://orcid.org/0000-0001-5071-7382) |
| Project Member | Dr. Mukesh Bachhav, Staff Scientist - Idaho National Laboratory (https://orcid.org/0000-0001-8104-6032) |
| Project Type | RTE |