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 |
Neutron Radiation Enhanced Grain Growth in Tungsten and Tungsten Alloys under Mixed Spectrum Neutron Irradiation |
Author(s) |
Hanns Gietl, Takaaki Koyanagi, Xunxiang Hu, Yutai Katoh |
On-Site Speaker (Planned) |
Hanns Gietl |
Abstract Scope |
Tungsten (W) is the main plasma facing material under consideration for fusion devices. However, there are many open questions and challenges regarding the use of W. One major question is the response of W to neutron irradiation.
In this study, pure W and several W alloys were subjected to mixed spectrum neutron irradiation in HFIR at a best-estimate temperature of 850 ˚C and above. Microstructural analysis using SEM-EBSD found significant grain growth after irradiation at temperatures remarkably lower than reported recrystallization temperatures for unirradiated materials in a similar duration. Recrystallisation fraction was quantified by a combination of grain size, type of grain boundary and internal grain misorientation. Hardness measurements found softening consistent with grain growth in most materials. Recrystallisation kinetics under irradiation is described by calculation of a radiation enhanced self-diffusion. The research is sponsored by the U.S. Department of Energy, Office of Fusion Energy Sciences. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, High-Temperature Materials, |