| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
C-ring Compression of SiC-SiC Cladding at 1200°C with In-situ X-ray Computed Micro-tomography |
| Author(s) |
Dong (Lilly) Liu, Jon Ell, Guanjie Yuan, Peng Xu, Roger Lu, Edward J. Lahoda, Harold Barnard, Dula Parkinson, Robert Ritchie |
| On-Site Speaker (Planned) |
Dong (Lilly) Liu |
| Abstract Scope |
In this work, SiCf-SiC accident tolerant cladding materials were examined using a unique hot cell to perform C-ring compression tests coupled with real-time X-ray computed micro-tomography (XCT) to image cracks formation and propagation through the surface coating and composite substrate at ambient and 1200°C. Two types of cladding with different coating thicknesses were examined. Their mechanical behavior was found to be very different which indicated a need for optimizing the thickness of the surface coating and composite substrate for both strength and damage-tolerance. During the experiments, an XCT scan was collected at each loading step until final failure, with digital volume correlation methods utilized to identify 3D strain concentrations. Incipient cracks were segmented for both types of samples, with their 3D distribution and interactions with the composite substrate characterized. Differences in the maximum local failure strains and their distributions in the two types of samples will be discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Composites, Nuclear Materials |