| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
Microstructure, Mechanical Properties, and Performance of Cold Spray Cr Coatings on Zr-alloy Fuel Cladding |
| Author(s) |
Tyler Dabney, Hwasung Yeom, Benjamin Maier, Jorie Walters, K. Sasidhar, Ben Eftink, Nan Li, Kumar Sridharan |
| On-Site Speaker (Planned) |
Tyler Dabney |
| Abstract Scope |
Cold spray coating of Cr on Zr-alloy cladding is being investigated with the goal of enhancing accident tolerance in pressurized water reactors during high temperature transients. The coatings impart high oxidation resistance to the cladding at temperatures in excess of 1000 °C in ambient air and steam environments, while also providing good hydrothermal corrosion resistance in prototypical PWR water chemistry. TEM examination showed the as-deposited Cr coatings exhibit a high dislocation density and dislocation substructure, which evolves into a fine grain structure during annealing. The mechanical properties and adhesion strength of the coating in various microstructural conditions were evaluated using in situ micro-cantilever beam bending tests and associated load-displacement plots. Full-length coated cladding assemblies tested in a nuclear reactor for periods in excess of thirty-six months showed very good performance based on visual examination and microscopy for surface oxidation and CRUD deposition characteristics. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Other |