W and W alloys are currently considered promising candidates for plasma facing components in future fusion reactors but most of the information on their mechanical properties at elevated temperature was obtained in the 1960s and 1970s. In this investigation, the strength and toughness of novel Y₂O₃-doped W-Ti alloys manufactured by powder metallurgy were measured from 25 ºC up to 1000 ºC in laboratory air and the corresponding deformation and failure micromechanisms were ascertained from analyses of the fracture surfaces. Although the materials were fairly brittle at ambient temperature, the strength and toughness increased with temperature and Ti content up to 600 ºC. Beyond this temperature, oxidation impaired the mechanical properties bu...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
W and W alloys are currently considered promising candidates for plasma facing components in future ...
W and W alloys are currently considered promising candidates for plasma facing components in future ...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
In this research the mechanical behaviour of pure tungsten (W) and its alloys (2 wt.% Ti–0.47 wt.% Y...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
W and W alloys containing 0.5 Wt% Y(2)O(3), x wt% Ti and (x wt% Ti + 0.5 Wt% Y₂O₃) have been prepare...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
W and W alloys are currently considered promising candidates for plasma facing components in future ...
W and W alloys are currently considered promising candidates for plasma facing components in future ...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
In this research the mechanical behaviour of pure tungsten (W) and its alloys (2 wt.% Ti–0.47 wt.% Y...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
W and W alloys containing 0.5 Wt% Y(2)O(3), x wt% Ti and (x wt% Ti + 0.5 Wt% Y₂O₃) have been prepare...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...
This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFR...