| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
|
| Presentation Title |
O-14: Calculation of Grain Boundary Diffusion Coefficients in Gamma U-Mo Using Atomistic Simulations |
| Author(s) |
ATM Jahid Hasan, Benjamin Beeler |
| On-Site Speaker (Planned) |
ATM Jahid Hasan |
| Abstract Scope |
The gamma U-10Mo alloy has been selected for the conversion of US High-Performance Research Reactor (HPRR) fuels from high-enriched uranium to low-enriched uranium. Although UMo alloys have high uranium density and good overall irradiation performance, the irradiation-induced swelling and creep remain important effects that influence the mechanical integrity of the fuel. Fuel performance models need fundamental properties, such as diffusion coefficients, as input to accurately describe the fuel evolution. In this study, we quantify the diffusivity along grain boundaries in UMo fuel. The grain boundary diffusivities of UMo alloys are obtained utilizing molecular dynamics simulations for a temperature range of 600-1200 K. We observe that U diffusivity in the grain boundary is significantly higher than Mo diffusivity, and the total diffusivity decreases with increasing Mo content. The information gathered in this work can inform creep and fission gas swelling models and help understand various phenomena related to UMo fuel performance. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Computational Materials Science & Engineering, Modeling and Simulation |