About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Mechanistic Fuel Performance Simulation of UN TRISO Kernels |
| Author(s) |
Christopher Matthews, Michael Cooper, David Andersson |
| On-Site Speaker (Planned) |
Christopher Matthews |
| Abstract Scope |
Uranium mononitride has a number of beneficial performance characteristics that make it an attractive ceramic to replace uranium-oxy-carbide fuel kernels in TRISO particles. In particular, the high uranium density and superior thermal conductivity can help boost core lifetime and safety characteristics. By leveraging the experience from historical irradiations, and the strides made in mechanistic modeling of ceramic nuclear fuel in general, a new capability has been stood up in the BISON fuel performance modeling code to capture irradiation behavior of UN pellets. Through the utilization of mechanistic formulation of the models in BISON, we will show that these models can be extended to estimate the behavior of UN kernels as a replacement for UCO in TRISO fuel particles. Using this initial simulation, we will be able to provide estimates on performance of the TRISO particle as a whole, as well as outline gaps in understanding UN kernel behavior. |
| Proceedings Inclusion? |
Undecided |