| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Solid-state Processing and Manufacturing for Extreme Environment Applications: Integrating Insights and Innovations
|
| Presentation Title |
Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding |
| Author(s) |
Tyler Dabney, K. Sasidhar, Evan Willing, Ben Eftink, Nan Li, Ben Maier, Jorie Walters, Kumar Sridharan |
| On-Site Speaker (Planned) |
Tyler Dabney |
| Abstract Scope |
Cold spray coatings of chromium on zirconium-alloy cladding are being investigated with the goal of enhancing oxidation resistance during high temperature transients (>1000 °C) in pressurized water reactors. TEM examination revealed the Cr coatings exhibit a high dislocation density and dislocation substructure, which evolved into a fine grain structure during annealing. High energy ion irradiation induced compositional mixing at the coating-substrate interface and promoted bonding at interparticle boundaries. Micro-cantilever beams were fabricated from Cr coatings with different processing conditions (as-deposited, low/high temperature annealed, and ion irradiated) to simulate reactor environmental effects on the microstructure. TEM, EBSD, and stress/strain analysis of the in situ bending tests provide insights into the adhesion strength of the Cr-Zr interface. Full-length coated cladding assemblies tested in a commercial nuclear reactor for periods exceeding thirty-six months showed very good performance based on visual examination, microscopy for surface oxidation, and CRUD deposition characteristics. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Other |