About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Advances in Materials Deposition by Cold Spray and Related Technologies III
|
| Presentation Title |
Development of Cold Spray Coatings for Enhanced Performance Fuel Cladding in Light Water Reactors |
| Author(s) |
Kumar Sridharan, Evan Willing, Tyler Dabney, Nicholas Pocquette, Benjamin Maier, Jorie Walters, Katerina Frederick, Michal Zylka, Laney Zuelsdorff, Carson Lukas, Kasturi Sasidhar, Hwasung Yeom |
| On-Site Speaker (Planned) |
Kumar Sridharan |
| Abstract Scope |
Zirconium-alloy fuel claddings (tubes that contain the uranium dioxide fuel pellets) have been used successfully in light water reactors (LWRs) for several decades. However, in the event of loss of coolant accident (LOCA), Zr-alloys can potentially oxidize severely in reaction with steam leading to a loss of structural integrity and hydrogen generation. Various facets of the development of cold spray technology for the deposition of Cr coatings on zirconium-alloys to address this challenge will be discussed, including process optimization, HR-TEM and EBSD to understand coating structure and interfacial bonding, effects of irradiation on coating and coating-substrate interfacial micro/nanostructure, and micro-cantilever testing for coating and coating-substrate interfacial strength. The coatings provide excellent oxidation resistance in steam at temperatures exceeding 1000oC. The coatings can also provide for improved economics by opening opportunities for use of high burnup fuel. In-reactor performance of the cold spray coated claddings will also be briefly discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Process Technology |