About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-Based Composites for Nuclear Applications III
|
| Presentation Title |
Separate effect studies on fission gas release behavior of UO2 and Cr2O3-doped UO2 of various microstructures |
| Author(s) |
Tianyi Chen, Ian Ferguson, Kevin Yan, Dong Zhao, Jie Lian, Tanvir Sakib, Vishal Yadav, Michael Tonks, Tsvetoslav Pavlov, Pierre-Clément Simon, Peter Mouche |
| On-Site Speaker (Planned) |
Tianyi Chen |
| Abstract Scope |
Fission gas release (FGR) critically impacts the performance, lifespan, and accident tolerance of UO₂-based fuels. Predictive, mechanistic modeling of FGR is necessary for the design and qualification of advanced fuel forms; however, knowledge gaps remain, particularly regarding diffusion and burst-release mechanisms in the rim and central reconstructed regions of high-burnup fuels. This work uses surrogate UO₂ samples with carefully controlled microstructures—achieved through Spark Plasma Sintering (SPS)—to conduct separate-effect studies on the influence of grain size, porosity, and Cr₂O₃ doping on xenon diffusivity and microcracking behavior. Xenon is introduced via SPS or irradiation and retained within the samples, which are subsequently tested using a thermogravimetry–mass spectrometry (TG-MS) system to monitor weight loss and gas release under both steady-state and transient heating conditions. Experimental findings will support the validation of mechanistic models, advancing the understanding of fission gas behavior in nuclear fuels. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |