| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
Implications of Defect Induced Thermal Conductivity Degradation on Accelerated Irradiation of Nuclear Fuels |
| Author(s) |
Marat Khafizov, Joshua Ferrigno, Tsvetoslav Pavlov, Pierre-Clement A Simon, Anant Raj, Hany Abdel-Khalik |
| On-Site Speaker (Planned) |
Marat Khafizov |
| Abstract Scope |
Radial temperature gradients governed by thermal conductivity play an important role in fuel behavior in nuclear reactor environments. In oxide fuels, heat is conducted by lattice vibrations whose ability to transfer heat is significantly impacted by accumulation of irradiation induced defects and fission products. We estimate thermal conductivity degradation due to nonequilibrium defect populations as a function of fission rate to evaluate its impact on microstructure evolution in oxide fuels. Defect populations are predicted using a rate theory model parametrized by the results from high resolution microstructure experiments. Thermal conductivity is estimated using Boltzmann transport formalism. The resulting framework allows estimation of lattice defect population across the radial profile of nuclear fuel rods. Subsequently, we analyze the implications of these on fission gas release using models implemented in fuel performance codes to reveal an important interplay between these processes. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Modeling and Simulation, Characterization |