About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
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Symposium
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Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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Presentation Title |
Multimodal Investigation of the Neutron Induced Defect of SiC/SiC Composites |
Author(s) |
David David Arregui-Mena, Takaaki Koyanagi, Weicheng Zhong, Yutai Katoh |
On-Site Speaker (Planned) |
David David Arregui-Mena |
Abstract Scope |
SiC/SiC composites are increasingly crucial for fuel cladding in Light Water Reactors (LWRs). Understanding the impact of thermal stresses, the harsh reactor environment, and neutron-induced dimensional changes on SiC/SiC composites is crucial for future deployment and development. This study focuses on characterizing end-plugs with various microstructural features before and after neutron irradiation. The multimodal research involved analyzing the tubes' hermeticity and using x-ray computed tomography scans to identify microstructural differences resulting from neutron irradiation. Additionally, digital volume correlation was used to assess the overall deformation caused by neutron-induced swelling, and the results were used for stress analysis. Various image-based model approaches were used to estimate the stress distribution across the tubes. Combining these test methods makes it possible to assess the damage that affects the hermetic properties and microstructure changes in neutron irradiated SiC/SiC composites. |
Proceedings Inclusion? |
Planned: |
Keywords |
Composites, Characterization, Nuclear Materials |