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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Ceramics and Ceramic-Based Composites for Nuclear Applications III
Presentation Title Impacts of Fission Product Speciation on Mechanical Properties of Advanced Ceramic Nuclear Fuels and Their Surrogates
Author(s) Patrick Warren, Mira Khair, Kaustubh Bawane, Jana Howard, Elizabeth Sooby
On-Site Speaker (Planned) Patrick Warren
Abstract Scope The aim of this study is to evaluate the changes in the thermal/mechanical properties of advanced ceramic nuclear reactor fuels as a function of fission product content, migration, and speciation. Fission product accumulation, migration, and speciation profoundly impact the thermal/mechanical properties of uranium based nuclear fuel materials and ultimately reduce the fuel elements lifetime. Until now, the influence of fission product migration and speciation on the thermal/mechanical properties of advanced ceramic reactor fuels and their surrogates have not been thoroughly investigated. Here we have characterized the migration of fission products in advanced reactor fuels and their surrogates by TEM in situ heating of advanced fuel samples and advanced fuel surrogate samples infused with fission product dopants and the resulting mechanical properties through SEM in situ mechanical experiments.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Ceramics, Other

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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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High Temperature X-ray and Neutron Studies of Uranium Carbide Systems
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Impacts of Fission Product Speciation on Mechanical Properties of Advanced Ceramic Nuclear Fuels and Their Surrogates
Improved Radiation Shielding in SPS-Processed B4C Ceramics via High-Entropy Alloy Additions
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Ion Beam Irradiation and Analysis of Ultra-High Temperature Ceramics
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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
Mitigation of Room Temperature Oxidation of Uranium Mononitride Through the Use of Powder Injection Molding
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Multi-Phase Modeling of Defect Accumulation and Thermal Conductivity Degradation for Irradiated UO2 Fuel
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