First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma-wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation u...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
First wall components in controlled fusion devices undergo severe modification by various physical a...
The paper provides a concise overview of ion beam analysis methods and procedures in studies of mate...
Understanding of material migration and its impact on the formation of co-deposited mixed material l...
Plasma-wall interaction plays an essential role in the performance and safety of a fusion reactor. T...
Fuel inventory and generation of carbon and metal dust in a tokamak are perceived to be serious safe...
First wall materials in controlled fusion devices undergo serious modification by several physical a...
The dream of abundant clean energy has brought scientists and laypeople alike to ponder the possibil...
Wall components retrieved from the TEXTOR tokamak after tracer experiments with nitrogen-15 and moly...
Application of ion beam analysis techniques in the studies of material transport and fuel inventory ...
Controlled thermonuclear fusion may become an attractive future electrical power source. The most pr...
The International Tokamak Experimental Reactor (ITER), the first burning fusion plasma experiment ba...
Tracer techniques were used in the TEXTOR tokamak to determine high-Z metal migration and the deposi...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
First wall components in controlled fusion devices undergo severe modification by various physical a...
The paper provides a concise overview of ion beam analysis methods and procedures in studies of mate...
Understanding of material migration and its impact on the formation of co-deposited mixed material l...
Plasma-wall interaction plays an essential role in the performance and safety of a fusion reactor. T...
Fuel inventory and generation of carbon and metal dust in a tokamak are perceived to be serious safe...
First wall materials in controlled fusion devices undergo serious modification by several physical a...
The dream of abundant clean energy has brought scientists and laypeople alike to ponder the possibil...
Wall components retrieved from the TEXTOR tokamak after tracer experiments with nitrogen-15 and moly...
Application of ion beam analysis techniques in the studies of material transport and fuel inventory ...
Controlled thermonuclear fusion may become an attractive future electrical power source. The most pr...
The International Tokamak Experimental Reactor (ITER), the first burning fusion plasma experiment ba...
Tracer techniques were used in the TEXTOR tokamak to determine high-Z metal migration and the deposi...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...
The first wall and the divertor in present-day or next step thermonuclear fusion devices are exposed...