| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-based Composites for Nuclear Fission Applications
|
| Presentation Title |
In Situ High-temperature 3D Imaging of the Damage Evolution in a SiC Nuclear Fuel Cladding Material |
| Author(s) |
Guanjie Yuan, J. Paul Forna Kreutzer, Peng Xu, Sean Gonderman, Christian Deck, Luke Olson, Edward Lahoda, Robert O. Ritchie, Dong (Lilly) Liu |
| On-Site Speaker (Planned) |
Dong (Lilly) Liu |
| Abstract Scope |
The deformation and fracture processes of SiC-based accident tolerant fuel cladding are studied using in situ X-ray micro-computed tomography (XCT) at RT and 1200°C under C-ring compression. Local mechanical properties and residual stresses were characterised using nanoindentation and Raman spectroscopy. The 3D strain distribution, crack formation and propagation processes including the toughening mechanisms (e.g., crack deflection, micro-cracking, crack bridging and bifurcation) are investigated in the coating and underlying composites at RT and 1200 °C. There is no particular sequence which toughening mechanism occurs first – this is very different from the conventional toughening theory in ceramic-matrix composites under uniaxial tension loading. Indeed, no evidence of fibre pull-out or fibre fracture was observed in this SiCf-SiCm nuclear cladding material in the current C-ring compression configuration. The correlation between local measurements and bulk mechanical behaviour will be discussed. |
| Proceedings Inclusion? |
Planned: |