About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials Systems for the Future of Fusion Energy
|
Presentation Title |
Neutron Irradiated Tungsten Defect, Surface Chemistry, and Microstructural Characterization |
Author(s) |
Chase N. Taylor, Masashi Shimada, Yasuhisa Oya |
On-Site Speaker (Planned) |
Chase N. Taylor |
Abstract Scope |
Fusion plasma facing components (PFCs) will be exposed to high fluxes of energetic neutrons, hydrogen isotopes, and helium. In addition, a variety of mixed materials end up on the surfaces of PFCs due to sputtering and redeposition from PFCs of other compositions. The end result will be the generation of new material surfaces with evolved properties with respect to the pristine surface. Tungsten surface and bulk properties significantly influence the behavior of tritium retention. These collective effects impact plasma-surface interactions, safety, and fuel cycle management.
Multiple fission campaigns irradiated tungsten samples under thermal and fast neutron fluxes. Samples then were characterized using XPS, PAS, and TEM in order to investigate the surface chemistry, defect structure, and microstructure, respectively. Deuterium irradiation and TDS were performed, which showed marked differences based on the sample surface condition. The present multi-technique analysis elucidates the complex interactions that occur in neutron irradiated tungsten PFCs. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, High-Temperature Materials |