%0 Journal Article
%A Calvo, Aida
%A García-Rosales, Carmen
%A Ordás, Nerea
%A Iturriza, Iñigo
%A Schlueter, Karsten
%A Koch, Freimut
%A Pintsuk, Gerald
%A Tejado, Elena
%A Pastor, José Ygnacio
%T Self-passivating W-Cr-Y alloys: Characterization and testing
%J Fusion engineering and design
%V 124
%@ 0920-3796
%C New York, NY [u.a.]
%I Elsevier
%M FZJ-2017-06242
%P 1118-1121
%D 2017
%X 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.
%F PUB:(DE-HGF)16
%9 Journal Article
%U <Go to ISI:>//WOS:000419411900232
%R 10.1016/j.fusengdes.2017.03.001
%U https://juser.fz-juelich.de/record/837273