| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
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| Symposium
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Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
In-situ Thermal Conductivity of Uranium Nitride (UN) and SIMFUEL Composites Under Irradiation |
| Author(s) |
Elina Charatsidou, Maria Giamouridou, Robert Frost, Michael Short, Pär Olsson |
| On-Site Speaker (Planned) |
Elina Charatsidou |
| Abstract Scope |
Investigation of thermal properties of uranium nitride (UN) is essential in understanding its behavior and performance under irradiation. For thermal conductivity, limited data is available in the literature. This work provides an innovative approach of measuring in-situ thermal conductivity under irradiation. The effect of fission products on thermal properties of the UN fuel was studied after implantation with solid (Zr, Ba) and gaseous (Xe, Kr) elements. Mechanical and thermal properties of UN and SIMFUEL composites were investigated using room temperature nanoindentation and in-situ transient grating spectroscopy under elevated temperatures, respectively. Through detailed pre and post characterization, microstructural analysis and mechanical testing, this work contributes to a deeper understanding of the response of UN fuel to irradiation under various doses and burn-up, thus facilitating its future implementation in advanced nuclear systems. This research holds significant promise for accelerating advanced fuel qualification of UN fuel. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Characterization, Nuclear Materials |