| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Small Scale Mechanical Testing of Irradiated Cladding and Fuel for Nuclear Reactors |
| Author(s) |
David Frazer, Fabiola Cappia, Daniel Murray, Cameron Howard, Yachun Wang, Fei Teng, Jatuporn Burns |
| On-Site Speaker (Planned) |
David Frazer |
| Abstract Scope |
Evaluating the mechanical properties of nuclear fuels and cladding is important for multiple reasons. Firstly, it enables understanding the pellet-cladding mechanical interactions during operation. Secondly, a better understanding of the fuel’s properties would assist in evaluating fine fuel fragmentation for fuel burn up extensions. A main challenge with measuring these properties is the high levels of radioactivity of the samples, making them difficult to handle. Small-scale mechanical testing can be used to minimize the volume of material need to measure their mechanical properties allowing them to be performed cheaply and rapidly outside of hot cells. The small volume probed enables the ability to measure the heterogeneity in the microstructure of irradiated materials not captured with macro-scale techniques. In this work, a variety of small-scale mechanical testing techniques were applied on control and irradiated fuel and cladding to measure the mechanical properties such as Young’s modulusand hardness over temperature. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Nuclear Materials, |