About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Accelerated Discovery and Qualification of Nuclear Materials for Energy Applications
|
Presentation Title |
Dislocation Loop Formation in Self-ion Irradiated Ultra-high Purity FeCr Alloys |
Author(s) |
Yao Li, Yajie Zhao, Arunodaya Bhattacharya, Jean Henry, Steven John Zinkle |
On-Site Speaker (Planned) |
Yao Li |
Abstract Scope |
The evolution of ½ <111> vs <100> loops in Fe-Cr alloys as a function of Cr concentration, dose, dose rate, and irradiation temperature is important for understanding the basis for radiation resistance. 8 MeV Fe ion irradiations (~0.35 and 3.5 dpa midrange doses) at dose rates of E-5 and E-4 dpa/s were performed on ultra-high purity Fe and Fe-Cr alloys (3-18 wt.%Cr) at 350-450°C. Using conventional diffraction contrast TEM imaging and detailed Burgers vector analysis, we observed loop size reduction as well as density increase with the addition of Cr, an increasing ½ <111> fraction with higher Cr concentration, the fraction of ½ <111> loops dropping from ~20% to ~2% with increasing temperature (in agreement with prior limited studies), nanoscale voids in Fe, and petal shaped loops at 450°C. Analytical scanning TEM (STEM)-high throughput energy dispersive X-ray spectroscopy (EDX) quantified Cr segregation onto dislocation loops for Cr<10 wt.%. |
Proceedings Inclusion? |
Planned: |
Keywords |
Characterization, Iron and Steel, Nuclear Materials |