| 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 |
Development of a Macroscopic Model of Irradiation-Enhanced Densification |
| Author(s) |
Brandon Battas, Michael Tonks |
| On-Site Speaker (Planned) |
Brandon Battas |
| Abstract Scope |
Porosity in nuclear fuels, particularly those processed from powders, plays a critical role in their performance within a reactor environment. Understanding the sintering behavior of these fuels under irradiation is essential, as it occurs alongside other significant microstructural evolutions in a reactor environment. In reactor conditions, irradiation significantly modifies defect concentrations and induces various microstructural changes, which in turn can accelerate the densification of sintered fuel pellets. This study employs mesoscale sintering modeling to analyze the effects of irradiation and microstructure-dependent defect concentrations in UO<sub>2</sub>, in order to develop a macroscopic model of irradiation-enhanced densification for application in the BISON fuel performance code. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Modeling and Simulation, Nuclear Materials, |