Self-passivating W-Cr-Y alloys: Characterization and testing

Autor: E. Tejado, A. Calvo, Iñigo Iturriza, Freimut Koch, Jose Ygnacio Pastor, Carmen García-Rosales, Karsten Schlueter, N. Ordás, Gerald Pintsuk
Jazyk: angličtina
Rok vydání: 2017
Předmět:
Zdroj: Fusion engineering and design 124, 1118-1121 (2017). doi:10.1016/j.fusengdes.2017.03.001
Fusion Engineering and Design
Proceedings of 29th Symposium on Fusion Technology (SOFT 2016) | 29th Symposium on Fusion Technology (SOFT 2016) | 05/09/2016-09/09/2016 | Praga, República Checa
Archivo Digital UPM
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DOI: 10.1016/j.fusengdes.2017.03.001
Popis: 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 thermo-shock resistance of the alloy.
Databáze: OpenAIRE