About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
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Presentation Title |
Impact of Thermal Treatment and Irradiation on Mechanical Behavior of Cold Spray Cr Coatings on Zr-alloy Cladding |
Author(s) |
Tyler Dabney, Hwasung Yeom, Nan Li, Ben Eftink, Kumar Sridharan |
On-Site Speaker (Planned) |
Tyler Dabney |
Abstract Scope |
Chromium-coated zirconium-alloy cladding is being considered for implementation in light water reactors for its superior oxidation resistance during high-temperature accident scenarios and improved corrosion kinetics during normal operating conditions. From reactor insertion through end-of-life, the coated cladding will undergo thermal- and irradiation-induced microstructural changes, and temperatures exceeding 1000 °C in the event of an off-normal condition. These environmental effects will cause changes to the mechanical behavior of the cladding due to stress relief, recrystallization and grain growth, irradiation-induced defect formation, or high-temperature diffusion leading to intermetallic compound formation at the interface. This study investigates the mechanical behavior of the coating and coating-substrate interface system after annealing at multiple temperatures as well as after ion irradiation, using a picoindenter housed in an SEM and the miniature cantilever techniques. This study is supported by post-test characterization of the deformed microstructure using SEM, TEM, and EBSD. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Mechanical Properties, Surface Modification and Coatings |