|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Development of PVD Cr Coatings for Hydrothermal Corrosion Resistance of SiC-SiCf Fuel Cladding in LWRs
||Kyle Quillin, Hwasung Yeom, Tyler Dabney, Evan Willing, Taeho Kim, Sergey Chemerisov, Christian Deck, Adrien Couet, Kumar Sridharan
|On-Site Speaker (Planned)
SiC-SiCf composite is being considered as a next-generation fuel cladding material for light water reactors (LWRs) based on its superior mechanical strength and oxidation resistance at high temperatures experienced during a potential loss-of-coolant accident (LOCA) compared to currently used Zr-alloys. However, SiC is prone to hydrothermal corrosion under normal LWR operating conditions. We are investigating the deposition of Cr coatings on SiC to address this concern. The coatings are being developed using a variety of state-of-the-art physical vapor deposition techniques. Through detailed microstructural analysis, we explain the effect of deposition parameters on coating microstructure and density. Nanoindentation and micropillar compression tests have been conducted to evaluate the mechanical properties of the coatings, and prototypical autoclave tests have been performed to understand their corrosion performance. The effects of water radiolysis on corrosion will also be discussed.
||Nuclear Materials, Surface Modification and Coatings,