Publication | Open Access
Self-passivating W-Cr-Y alloys: Characterization and testing
45
Citations
21
References
2017
Year
Materials EngineeringMaterials ScienceHigh Temperature MaterialsEngineeringSelf-passivating TungstenCorrosionSuperalloyMechanical EngineeringSelf-passivating W-cr-y AlloysAlloy DesignPure TungstenFusion MaterialsAlloy PhaseGrain SizeFusion Reactor MaterialMicrostructureStructural Materials
The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is advantageous concerning safety issues in comparison with pure tungsten. Bulk W-10Cr-0.5Y alloy manufactured by mechanical alloying followed by HIP resulted in a fully dense material with grain size around 100 nm and a dispersion of Y-rich oxide nanoparticles located at the grain boundaries. An improvement in flexural strength and fracture toughness was observed with respect to previous works. Oxidation tests under isothermal and accident-like conditions revealed a very promising oxidation behavior for the W-10Cr-0.5Y alloy. Thermo-shock tests at JUDITH-1 to simulate ELM-like loads resulted in a crack network at the surface with roughness values lower than those of a pure W reference material. An additional thermal treatment at 1550 °C improves slightly the oxidation and significantly thermo-shock resistance of the alloy.
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