| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
High Temperature Mechanical Testing of Uranium Fuel Pellets |
| Author(s) |
Tarik A. Saleh, James A Valdez, Michael A. Torrez, Scarlett Widgeon Paisner, Kathryn E. Metzger, Joshua T. White |
| On-Site Speaker (Planned) |
Tarik A. Saleh |
| Abstract Scope |
In order to understand high temperature mechanical and creep behavior of fuel pellets at realistic reactor temperatures, 5x5 mm and larger fuel pellets were fabricated in the Fuels Research Laboratory at Los Alamos National Laboratory and tested in compression at temperatures of 1500-2000 °C. Data from these experiments will inform mechanical behavior models to elucidate the thermal portion of the creep behavior of fuel pellets in reactors during operation. This talk will discuss processing and fabrication of high density UN fuel pellets, along with traditional UO2 pellets. Once pellets were made, they were tested in compression in a specially modified load frame and furnace in high purity environments at elevated temperatures. Discussion of testing techniques along with results from these compression tests on UN and UO2 pellets will be presented. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, |