About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Ceramics and Ceramic-based Composites for Nuclear Fission Applications
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Presentation Title |
Elucidating the Effect of Radiation-induced Defect Accumulation on Swelling in UN Using In-situ TEM Irradiation |
Author(s) |
Maria Kosmidou, Adrien J. E. Terricabras, Caitlin A. Kohnert, Joshua T. White, Erofili Kardoulaki |
On-Site Speaker (Planned) |
Maria Kosmidou |
Abstract Scope |
Uranium mononitride (UN) is under consideration as an advanced nuclear fuel alternative to UO2. During irradiation, the fuel swells due to the formation and growth of fission gas bubbles. A key limiting factor for its in-reactor application is runaway swelling; a phenomenon where at high temperatures (and burnups) changes to the mobility of defects combined with microstructural changes cause the swelling of the fuel to rapidly accelerate. It is thought that the accumulation of irradiation-induced defects and fission gas play a key role. Irradiations in test reactors are time intensive and costly due to handling hazardous irradiated nuclear material. In-situ TEM irradiations afford accelerated irradiation and damage evolution in nuclear materials to expedite and safely study irradiation damage in novel systems. In this work, we aim to in-situ study the nucleation and evolution of defects (e.g. dislocation loops, cavities) in UN by Kr ion irradiations at reactor relevant temperatures. |
Proceedings Inclusion? |
Planned: |