About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
|
| Presentation Title |
Self-ion irradiation induced defect evolution and micromechanical response of W |
| Author(s) |
Adil Wazeer, Yinghang Liu, Chang Xia, Ke Xu, Debargha Paul, Vaibhav Singh, Yongqiang Wang, Matthew Ryan Chancey, Tim Graening, Xiao-Ying Yu, Haiyan Wang, Xinghang Zhang |
| On-Site Speaker (Planned) |
Adil Wazeer |
| Abstract Scope |
Understanding radiation tolerance and high-temperature performance of tungsten (W) is critical for its deployment in nuclear fusion environments. In this study, pure W specimens were subjected to W ion irradiation at elevated temperature. High resolution TEM studies revealed distinct defect evolution with increasing dose, including the formation of voids and dislocation loops. To assess the impact of these defects on mechanical integrity, in-situ SEM micropillar compression tests were conducted on both unirradiated and irradiated pillars. The results demonstrate a complex interplay between irradiation dose and thermal activation. This work provides insights into the defect-mediated microstructural evolution and mechanical degradation mechanisms in irradiated W. The coupling of heavy ion irradiation with high-temperature micromechanical testing presents a comprehensive framework for evaluating structural performance under extreme reactor-relevant conditions, contributing to the design of resilient plasma-facing materials for future fusion energy systems. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, |