TY  - JOUR
AU  - Calvo, Aida
AU  - García-Rosales, Carmen
AU  - Ordás, Nerea
AU  - Iturriza, Iñigo
AU  - Schlueter, Karsten
AU  - Koch, Freimut
AU  - Pintsuk, Gerald
AU  - Tejado, Elena
AU  - Pastor, José Ygnacio
TI  - Self-passivating W-Cr-Y alloys: Characterization and testing
JO  - Fusion engineering and design
VL  - 124
SN  - 0920-3796
CY  - New York, NY [u.a.]
PB  - Elsevier
M1  - FZJ-2017-06242
SP  - 1118-1121
PY  - 2017
AB  - 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.
LB  - PUB:(DE-HGF)16
UR  - <Go to ISI:>//WOS:000419411900232
DO  - DOI:10.1016/j.fusengdes.2017.03.001
UR  - https://juser.fz-juelich.de/record/837273
ER  -