About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
Presentation Title |
Small Scale Mechanical Testing of Nuclear Fuel and Cladding |
Author(s) |
David Frazer, Joshua White, Tarik Saleh, Fabiola Cappia, Fei Teng, Daniel Murray, Cameron Howard, Colin Judge |
On-Site Speaker (Planned) |
David Frazer |
Abstract Scope |
A thorough knowledge of the mechanical properties of fuel and cladding is important for understanding the pellet cladding mechanical interaction during operation of a nuclear reactor. A challenge with researching the mechanical properties of irradiated materials, particularly fuel, is that the high levels of radioactivity make testing the specimens difficult: usually requiring the use of time consuming and expensive hot-cells. Small scale mechanical testing (SSMT) enables probing the mechanical properties on highly irradiated materials using minute volumes of material which greatly reduces the radiation dose to workers and allowing testing without the use of hot-cells which reduces both expense and process time. Due to the small volume of the specimens required for testing SSMT also enables targeting specific microstructural features such as grain boundaries. Measurements of fresh fuel samples over temperature, the implementation of these techniques to irradiated fuels, and advanced cladding materials and concepts, will be addressed and evaluated. |
Proceedings Inclusion? |
Planned: |
Keywords |
Mechanical Properties, Nuclear Materials, |