Tungsten (W) is a prime candidate as first wall armor material of future fusion power plants as W withstands extreme particle, heat, and radiation loads without forming long-lived radioactive waste. The release of radioactive material from the reactor to the environment should be suppressed in case of an accident such as a loss of coolant (LOCA) with simultaneous air ingress into the vacuum vessel. W oxidizes and sublimates in case of a LOCA. Therefore, oxidation resistant tungsten, chromium, yttrium (W–Cr–Y) alloys are developed to provide intrinsic safety in case of such an accident.In this paper, the optimization of the yttrium (Y) concentration is presented on bulk samples compacted by field assisted sintering technology (FAST). W with ...
Tungsten test is currently the baseline first-wall armor material for a future DEMOnstration power p...
The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is ad...
This study is for: The Fifteenth International Conference on Fusion Reactor Materials (ICFRM-15) wa...
Tungsten (W) currently is the main candidate as plasma-facing armour material for the first wall of ...
AbstractTungsten is a prime material candidate for the first wall of a future fusion reactor. In the...
Tungsten (W) is currently deemed the main candidate for the plasma-facing armor material of the firs...
Tungsten is a prime material candidate for the first wall of a future fusion reactor. In the case of...
Tungsten is currently deemed as a promising plasma-facing material (PFM) for the future power plant ...
AbstractSelf-passivating tungsten based alloys for the first wall armour of future fusion reactors a...
Tungsten (W) is deemed as the main candidate for the first wall armor material of future fusion powe...
Self-passivating tungsten based alloys for the first wall armour of future fusion reactors are expec...
Electricity from nuclear fusion is a promising approach. An accidental scenario of a fusion power pl...
The severe particle, radiation and neutron environment in a future fusion power plant requires the d...
Tungsten is considered the main candidate material for the first-wall in DEMO due to its high meltin...
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first w...
Tungsten test is currently the baseline first-wall armor material for a future DEMOnstration power p...
The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is ad...
This study is for: The Fifteenth International Conference on Fusion Reactor Materials (ICFRM-15) wa...
Tungsten (W) currently is the main candidate as plasma-facing armour material for the first wall of ...
AbstractTungsten is a prime material candidate for the first wall of a future fusion reactor. In the...
Tungsten (W) is currently deemed the main candidate for the plasma-facing armor material of the firs...
Tungsten is a prime material candidate for the first wall of a future fusion reactor. In the case of...
Tungsten is currently deemed as a promising plasma-facing material (PFM) for the future power plant ...
AbstractSelf-passivating tungsten based alloys for the first wall armour of future fusion reactors a...
Tungsten (W) is deemed as the main candidate for the first wall armor material of future fusion powe...
Self-passivating tungsten based alloys for the first wall armour of future fusion reactors are expec...
Electricity from nuclear fusion is a promising approach. An accidental scenario of a fusion power pl...
The severe particle, radiation and neutron environment in a future fusion power plant requires the d...
Tungsten is considered the main candidate material for the first-wall in DEMO due to its high meltin...
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first w...
Tungsten test is currently the baseline first-wall armor material for a future DEMOnstration power p...
The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is ad...
This study is for: The Fifteenth International Conference on Fusion Reactor Materials (ICFRM-15) wa...