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 |
Recent Progress in Understanding Fundamental Radiation Degradation Processes |
Author(s) |
Steven J. Zinkle, Yan-Ru Lin, Yajie Zhao, Samara Levine, Yao Li, Zehui Qi, Arunodaya Bhattacharya, Shradha Agarwal |
On-Site Speaker (Planned) |
Steven J. Zinkle |
Abstract Scope |
The intense neutron fluxes and He generation rates in the first wall and blanket regions of proposed DT fusion reactors generally accelerate the five key radiation damage degradation mechanisms in structural materials. TEM analysis of dual ion irradiated Fe-Cr and steel specimens irradiated at 0.1, 10 and 50 appm He/dpa and 400-550oC reveals a transition from monomodal to bimodal cavity size distributions with increasing He/dpa and peak swelling near fusion-relevant 10 appm He/dpa, along with a shift in peak cavity swelling to higher temperatures at higher He/dpa. A modified precipitate stability model has been developed to quantify the competing effects of ballistic dissolution and radiation enhanced precipitate regrowth in structural alloys. Improved insight on mechanisms for formation and conversion of 1/2<111> and <100> loops in Fe alloys are revealed by introducing novel nanostructured heterogeneous sink structures. The interrelationship between high temperature He embrittlement, stress, He/time and creep mechanisms are explored. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Phase Transformations, |