About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
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Materials Systems for the Future of Fusion Energy
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Presentation Title |
N-21: Dislocation Loop Formation in Self-ion Irradiated Ultra-high Purity Fe-Cr Alloys |
Author(s) |
Yao Li, Arunodaya Bhattacharya, Yajie Zhao, Ling Wang, Steven John Zinkle |
On-Site Speaker (Planned) |
Steven John Zinkle |
Abstract Scope |
Understanding the loop formation in Fe-Cr alloys as a function of irradiation temperature, Cr concentration, dose, and dose rate is an important aspect of radiation resistance. 8 MeV Fe ion irradiations were performed at 10-5 - 10-4 dpa/s, 350-450°C on ultra-high purity Fe and Fe-Cr alloys (3-18wt.%Cr) up to ~0.35 and 3.5 midrange dpa. Using TEM, we observed loop size reduction and density increase with increasing Cr, an increasing ½ <111> fraction with higher Cr concentration, and petal-shaped loops on {100} planes at 450°C. The fraction of ½ <111> loops reduced from ~20% to ~2% with increasing temperature. The <100> fraction decreased with increasing damage depth. 80% of the observed loops were ½ <111> in beyond-damage region in pure Fe at 350°C. Our observations contradict the glide and interaction models as the main mechanism for <100> loop production. Cr segregation onto dislocation loops was quantified for Cr < 10wt.%. |
Proceedings Inclusion? |
Planned: |