| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
|
| Presentation Title |
Understanding Burnup Effects on UO2 Mechanical Behavior Using Surrogate Materials |
| Author(s) |
Tianyi Chen, Mack Cullison, Fabiola Cappia, David Frazer, Fei Teng, Jie Lian |
| On-Site Speaker (Planned) |
Tianyi Chen |
| Abstract Scope |
The mechanical integrity of nuclear fuel is crucial for safety and longevity. During burnup, fuel material degrades from thermal and displacement damage and fission product accumulation. Neutron-irradiated fuel studies are often restricted by high radioactivity, cost, and limited material access. Although these studies enhance our phenomenological understanding, they are not ideal for mechanistic insights due to complexity and lack of systematicity. Surrogate materials allow more experimental design freedom and separate-effect studies.
We studied surrogate UO2 materials, fabricated with advanced spark plasma sintering techniques for grain structure control, using ion irradiation, small-scale mechanical testing, and simultaneous thermal analysis techniques. The results elucidate mechanisms of high-burnup structure development and consequent fracture resistance degradation. The values and limitations of surrogate fuel experimental studies are discussed concerning mechanistic fuel-performance model development. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Nuclear Materials, Mechanical Properties |