About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components III
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Presentation Title |
O-8: Effects of Helium Implantation on Mechanical Properties Near the Tungsten-carbide Interfaces of Dispersion Strengthened Tungsten Alloy |
Author(s) |
Ashrakat Saefan, Xing Wang, Eric Lang, Jean Paul Allain |
On-Site Speaker (Planned) |
Ashrakat Saefan |
Abstract Scope |
Tungsten is a promising candidate for plasma-facing materials for fusion reactors but suffers from embrittlement due to irradiation and recrystallization. Adding second-phase dispersoids has been shown to improve the material thermomechanical properties. Here we used micromechanical testing to study the changes of mechanical properties of carbide dispersoid strengthened tungsten (DS-W) under helium (He) irradiation, which is a unique challenge for fusion materials. Micropillar compression found no failure at the carbide-tungsten interfaces regardless the 2 MeV He irradiation, indicating a tight bonding between dispersoids and matrix. Nano-indentation is applied to measure the local hardness near the interfaces. It is expected that the He irradiation would reduce the hardness at the interfaces, since the trapped He clusters and bubbles could either break the bonds at the interface or facilitate the dislocation nucleation. Microscopy analysis will be conducted to characterize the He distribution in DS-W to explain the observed changes in mechanical properties. |
Proceedings Inclusion? |
Planned: |
Keywords |
Mechanical Properties, Composites, Characterization |