About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Local Ordering in Materials and Its Impacts on Mechanical Behaviors, Radiation Damage, and Corrosion
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Presentation Title |
Modeling Radiation-induced Segregation Near Nanosized Cavities in Fe-Cr Alloys |
Author(s) |
Xinyuan Xu, Xing Wang |
On-Site Speaker (Planned) |
Xinyuan Xu |
Abstract Scope |
Radiation-induced segregation (RIS) is a common non-equilibrium phenomenon that could significantly modify material properties. Despite of numerous works on RIS near grain boundaries in Fe-Cr alloys, only a few studies focused on RIS near nanosized cavities, including voids and bubbles, which are the primary reason for radiation-induced swelling. Here we applied a modified Perks model to calculate Cr segregation near nanosized cavities. The results showed that RIS reached the maximum at approximately 0.01 displacements per atom (dpa), regardless of the dose rate. This saturation dose was much smaller than that near grain boundaries (about 1 dpa). Furthermore, our analysis revealed that higher dose rates would lead to greater maximum magnitudes of Cr segregation. Additionally, the calculations predict a temperature crossover from Cr enrichment to depletion at about 640 °C. The segregated Cr layers around nano cavities may modify local defect mobility and contribute to the suppressed swelling in Fe-Cr alloys. |
Proceedings Inclusion? |
Planned: |
Keywords |
Modeling and Simulation, Nuclear Materials, Iron and Steel |