| 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 |
Pipe Diffusion Along Edge Dislocation in UO2 and UN Nuclear Fuels |
| Author(s) |
Romain Perriot, Conor Galvin, Anton Schneider, Michael Cooper |
| On-Site Speaker (Planned) |
Romain Perriot |
| Abstract Scope |
Pipe diffusion, the enhanced transport of point defects along dislocations, plays an important role in materials phenomena such as creep diffusion, defect segregation, ageing or sintering. Such behavior can in turn drastically affect the performance of the material and must therefore be accounted for in order to produce reliable predictions at engineering scales.
In this work, we have characterized pipe diffusion in two important nuclear fuel materials, uranium dioxide UO2 and uranium nitride UN. State-of-the-art interatomic potentials were used in conjunction with nudged elastic band calculations and direct molecular dynamics simulations to demonstrate the enhanced transport of uranium interstitials and vacancies, as well as Xenon fission products, along three important edge dislocations, namely 1/2<110>{100}, 1/2<110>{110} and 1/2<110>{111}. The results will be used in higher length-scale models to improve the reliability of nuclear fuel performance codes. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Modeling and Simulation, Other |