| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Advanced Characterization and Modeling of Nuclear Fuels: Microstructure, Thermo-physical Properties
|
| Presentation Title |
Modeling Irradiation-enhanced Diffusion in Advanced Ceramic Nuclear Fuels |
| Author(s) |
Michael W. Cooper, Christopher Matthews, Vancho Kocevski, Christopher Stanek, David Andersson |
| On-Site Speaker (Planned) |
Michael W. Cooper |
| Abstract Scope |
Nuclear fuel performance and the degradation of fuel properties are governed, in many respects, by the formation and diffusion of point defects and clusters in the lattice. For example, the diffusion of fission gas and vacancies through the lattice controls fission gas swelling and release, which are key performance metrics that also impact thermal transport. During reactor operation, the concentration and diffusion of defects can be enhanced through irradiation processes. In this work, we represent atomic scale calculations of the diffusion mechanisms of host and impurity (Xe) defects in ceramic nuclear fuels, such as doped UO2, UN, and UC. The atomic scale predictions of the stability and diffusivity of point defect and clusters in these systems have then been implemented in cluster dynamics simulations to predict irradiation-enhanced defect concentration and diffusivities. The importance of the in-reactor conditions and of including various defects will be discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Modeling and Simulation, Ceramics |