| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-based Composites for Nuclear Fission Applications
|
| Presentation Title |
Microstructure, Mechanical Properties, and Residual Stresses of Cr-Coated SiC Fuel Cladding for Light Water Reactors |
| Author(s) |
Kyle Quillin, Hwasung Yeom, K.N. Sasidhar, Xiaofei Pu, David Frazer, Kumar Sridharan |
| On-Site Speaker (Planned) |
K.N. Sasidhar |
| Abstract Scope |
Chromium coatings produced with physical vapor deposition (PVD) processes have been investigated to mitigate the hydrothermal corrosion of SiC-SiCf fuel cladding. Nanoscale structural characterization of the coatings has been performed to assess the effects of deposition parameters on coating density and grain size. The mechanical properties and deformation behavior of the Cr coatings have been evaluated using nanoindentation testing followed by microscopy of the indentation features including pile-up and sub-surface deformation. In situ x-ray diffraction experiments in the temperature range of 300 °C to 1200 °C were performed to understand the evolution of residual stress within the coatings as well as chemical interactions between Cr and SiC. Thermal and microstructural contributions to residual stress evolution were identified. The coating microstructure, mechanical properties, and residual stress state have been correlated to evaluate the performance of PVD Cr coatings as protective surface layers for SiC fuel cladding. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Characterization |