| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
Computational Studies of Radiation Induced Segregation in Metallic Alloys |
| Author(s) |
Yitao Wang, Jacob Jeffries, Marie Thomas, Daniele Offidani, Suveen Mathaudhu, Emmanuelle Marquis, Enrique Martinez, Fadi Abdeljawad |
| On-Site Speaker (Planned) |
Yitao Wang |
| Abstract Scope |
The evolution of radiation damage is a major technical issue for the durable and safe operation of materials in nuclear power plants. Under irradiation of metallic alloys, point defects drag alloying elements towards grain boundaries (GBs) due to flux coupling resulting in radiation-induced segregation (RIS). Recent studies revealed a strong interplay between RIS and various microstructural features. With the aid of a mesoscale phase field model, we explore RIS in a wide range of metallic alloys with the aim of quantifying the impact of grain size (i.e., GB density) on GB chemical profiles. Parametrized using atomistic and Monte Carlo simulations, the phase field model is used to explore the role of the initial point defect (i.e., vacancies and interstitials) concentrations arising from non-equilibrium materials processing in the evolution of RIS profiles. Finally, extensions of the model to multicomponent alloys are discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Entropy Alloys, Modeling and Simulation |