| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Atomistic and Mesoscale Modeling of Fission Gas and Fission Products Diffusivity in TRISO Fuel Kernels |
| Author(s) |
Xiang-Yang Liu, Christopher Matthews, Wen Jiang, Michael W. D. Cooper, Jason D. Hales, David A. Andersson |
| On-Site Speaker (Planned) |
Xiang-Yang Liu |
| Abstract Scope |
TRISO fuel particles are candidates for use in next generation reactors including gas reactors, fluoride salt- cooled high temperature reactors, and micro-reactors. A fundamental understanding of the fission gas and fission products diffusivity in the UCO fuel kernels in irradiation conditions is important for accurate fuel performance prediction of the TRISO fuels. Typically, UCO fuel kernels used in TRISO fuels are a mixture of uranium carbides and uranium dioxides. In this study, based on the atomistic modeling of the fuel kernel properties, cluster dynamics simulations have been carried out to predict the diffusivity of fission gas xenon and fission products such as Ag in UCO fuel kernels. And the application of the diffusivity model in fuel performance simulations is also demonstrated. Finally, the complexity in the modeling of TRISO fuel kernels is further discussed, including fuel chemistry, different forms of uranium carbides, and higher burn-up issues. |
| Proceedings Inclusion? |
Planned: |