| 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 |
Assessing Thermochemical Stability and Fission Product Mobility in Advanced Nuclear Fuels |
| Author(s) |
Elizabeth S. Sooby, Steven Cavazos, Mira Khair, Patrick Warren |
| On-Site Speaker (Planned) |
Elizabeth S. Sooby |
| Abstract Scope |
Many novel reactor designs include the use of unqualified, advanced nuclear fuels. In order to enhance economic viability of these designs, vendors propose either modified TRISO kernels or high uranium density fuel such as UN. In each of these cases, there are knowledge gaps which need to be bridged for qualification of these next generation fuel designs. In the case of UN, fission product behavior, thermochemical stability, and mobility in the fuel form are largely unknown. For modified TRISO fueled reactor designs, extending cycle lengths or operational windows beyond the AGR qualified fuel form necessitates an understanding of SiC corrosion by select fission products. Presented here will be microstructure and thermodynamic data to both motivate future phenomenological investigations as well as to enhance the current state of knowledge of fission product behavior in advanced reactor fuels. |
| Proceedings Inclusion? |
Planned: |