Proceedings of: 19th International Conference on Fusion Reactor Materials (ICFRM-19), 27 October-01 November 2019, La Jolla, California, U.S.AThe influence of 1 and 5 wt% of TiC nanoparticles on the oxidation behaviour of reinforced tungsten has been evaluated up to 700 °C in dry air. Isothermal thermogravimetric tests prove that the addition of 5 wt% of TiC particles is detrimental, increasing the mass gain of pure tungsten by a factor of ten. TiC particles act as stress concentrators, facilitating microcracking events within the scale and promoting decohesion between TiC-free boundaries and TiC-containing regions of the material. Compared to pure tungsten, lowering TiC addition to 1 wt% significantly improves the oxidation resistance at 7...
Self-passivating tungsten based alloys for the first wall armour of future fusion reactors are expec...
The plasma-facing materials in fusion reactors will face very extreme servicing condition such as hi...
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first w...
Proceedings of: 19th International Conference on Fusion Reactor Materials (ICFRM-19), 27 October-01 ...
The oxidation behaviour of W-2Ti (wt%) alloy has been evaluated in dry air at 600, 700 and 800 °C fo...
This study is for: The Fifteenth International Conference on Fusion Reactor Materials (ICFRM-15) wa...
The effect of vanadium additions on the oxidation behaviour of tungsten has been evaluated at 600 °C...
The oxidation behavior of International Thermonuclear Experimental Reactor (ITER)-reference tungsten...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
A detailed microstructural analysis is one key factor for establishing structure–property relationsh...
A cobalt-free tungsten carbide cermet (WC-FeNi) has been subjected to oxyacetylene flame tests to si...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
Tungsten is the material of choice for plasma-facing components in future plasma-burning fusion reac...
The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is ad...
AbstractSelf-passivating tungsten based alloys for the first wall armour of future fusion reactors a...
Self-passivating tungsten based alloys for the first wall armour of future fusion reactors are expec...
The plasma-facing materials in fusion reactors will face very extreme servicing condition such as hi...
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first w...
Proceedings of: 19th International Conference on Fusion Reactor Materials (ICFRM-19), 27 October-01 ...
The oxidation behaviour of W-2Ti (wt%) alloy has been evaluated in dry air at 600, 700 and 800 °C fo...
This study is for: The Fifteenth International Conference on Fusion Reactor Materials (ICFRM-15) wa...
The effect of vanadium additions on the oxidation behaviour of tungsten has been evaluated at 600 °C...
The oxidation behavior of International Thermonuclear Experimental Reactor (ITER)-reference tungsten...
This study is for: 14th International Conference on Fusion Reactor Materials (ICFRM-14), 6-11 septem...
A detailed microstructural analysis is one key factor for establishing structure–property relationsh...
A cobalt-free tungsten carbide cermet (WC-FeNi) has been subjected to oxyacetylene flame tests to si...
Proceedings of: The Thirteenth International Conference on Fusion Reactor, Nice (France), 10–14 Dece...
Tungsten is the material of choice for plasma-facing components in future plasma-burning fusion reac...
The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is ad...
AbstractSelf-passivating tungsten based alloys for the first wall armour of future fusion reactors a...
Self-passivating tungsten based alloys for the first wall armour of future fusion reactors are expec...
The plasma-facing materials in fusion reactors will face very extreme servicing condition such as hi...
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first w...