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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Ceramics and Ceramic-Based Composites for Nuclear Applications III
Presentation Title Measured Radiation-Induced Bowing of SiC/SiC Composite Components under Neutron Flux Gradients
Author(s) Christian M. Petrie, Peter Doyle, David Chandler, Nick G. Russell, Annabelle Le Coq, Josina W. Geringer, Christian P. Deck, Takaaki Koyanagi, Yutai Katoh
On-Site Speaker (Planned) Christian M. Petrie
Abstract Scope Despite the well-recognized benefits of SiC fiber-reinforced, SiC ceramic matrix composites (SiC/SiC) for light-water reactor (LWR) fuel cladding and other core internal components, there are still some degradation mechanisms that need to be understood before these materials can be fully qualified. One phenomenon for which no integral irradiation data currently exists is the extent to which SiC/SiC components would suffer from lateral bowing under the presence of fast neutron flux gradients, which could interfere with coolant channels and/or control rod/blade movements. This work presents the first reported measurements of radiation-induced bowing and local deformations of two SiC/SiC tube specimens and a miniature square channel box with varying neutron flux gradients. Results are compared with analytical equations and high-fidelity 3D neutron transport and finite element structural analysis calculations. The results are discussed in terms of the implications for LWR operations and plans for resolving the remaining data gaps.
Proceedings Inclusion? Planned:
Keywords Composites, Nuclear Materials, Environmental Effects

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Effective Thermal Conductivity Modeling of Synthetic TRISO Fuel Compacts
Effects of Compositional Complexity on the Ion Irradiation Response of Pyrochlore Oxides
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Fabrication of Engineered Oxide Fuels Mimicking High Burnup Fuels and their Fragmentation Mechanisms Under Simulated LOCA and RIA Thermal Transient
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Irradiation Experiment on the Performance of Carbon Composites at High Temperatures
Measured Radiation-Induced Bowing of SiC/SiC Composite Components under Neutron Flux Gradients
Mesoscale modeling of restructuring in high burnup UO2 fuel
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