| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
Thermal Properties Degradation in Proton Irradiated Cr-Doped UO2 |
| Author(s) |
Adrien J. Terricabras, Rijul Chauhan, John Proctor, Oran Lori, Lin Shao, Sarah Finkeldei, Joshua White |
| On-Site Speaker (Planned) |
Adrien J. Terricabras |
| Abstract Scope |
Work has been done globally to improve the performance of light water reactors. Doped UO2 have been studied to enhance fuel properties, including fission gas retention. Despite considerable work being published of such systems, there is a lack of information in the literature regarding the degradation of doped UO2 thermal properties under irradiation. In this study, Cr-doped and undoped UO2 samples were fabricated using two different routes: powder processing and sol-gel. Samples were irradiated using a 2 MeV proton beam to locally heat the substrate, which was pre-annealed at temperatures up to 1000°C. The beam heat region was imaged by a high-speed IR camera to elucidate the change in thermal properties as a function of dose and capture the recovery/annealing of defects. In conjunction with finite element analysis, the thermal properties of the samples were extracted and compared to unirradiated measurements. Microscopy was conducted to evaluate defect structure evolution. |
| Proceedings Inclusion? |
Planned: |