This research investigated whether unipolar arcing in the divertor of fusion reactors is a potential cause for enhanced wear of the divertor. It was found that 1 µm of nano-fuzz growth is sufficient to initiate arcing, mainly depending on the sheath potential drop and electron density. The average mass loss rate induced by the arc was determined from mass loss measurements and found to be consistent with the value estimated from the arc current. The average arc track erosion depth was estimated by using the measured mass loss and damaged surface area and was found to be one tenth of the fuzzy layer thickness. Due to melting of the fuzzy structures the actual depth is larger and some arc tracks occasionally appeared to even reach the bulk be...
Damage caused by plasma-surface interactions is of concern in fields involving the use of such plasm...
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions i...
The paper concerns experimental investigations of plasma facing components erosion under the plasma ...
Abstract This research investigated whether unipolar arcing in the divertor of fusion reactors is a ...
Materials exposed to plasma may undergo various forms of surface modifications. Among the important ...
International audiencePost-mortem analyses suggest that arcs in contact with metallic walls are the ...
The transition from carbon to high-Z divertor devices reduces the erosion of the plasma facing compo...
Studying the ageing of tungsten monoblocks, their erosion and their fuel inventory is the priority o...
Controlled thermonuclear fusion may become an attractive future electrical power source. The most pr...
ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exp...
The damage threshold and damage mechanisms of divertor armor materials, i.e. CFC and tungsten, were ...
AbstractAt the inner baffle of the AUG divertor massive polished inserts of tungsten and P92 steel w...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
Erosion of tungsten in the outer JET divertor was determined with a set of tungsten coated divertor ...
The interaction of tokamak plasma with several materials considered for the plasma facing components...
Damage caused by plasma-surface interactions is of concern in fields involving the use of such plasm...
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions i...
The paper concerns experimental investigations of plasma facing components erosion under the plasma ...
Abstract This research investigated whether unipolar arcing in the divertor of fusion reactors is a ...
Materials exposed to plasma may undergo various forms of surface modifications. Among the important ...
International audiencePost-mortem analyses suggest that arcs in contact with metallic walls are the ...
The transition from carbon to high-Z divertor devices reduces the erosion of the plasma facing compo...
Studying the ageing of tungsten monoblocks, their erosion and their fuel inventory is the priority o...
Controlled thermonuclear fusion may become an attractive future electrical power source. The most pr...
ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exp...
The damage threshold and damage mechanisms of divertor armor materials, i.e. CFC and tungsten, were ...
AbstractAt the inner baffle of the AUG divertor massive polished inserts of tungsten and P92 steel w...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
Erosion of tungsten in the outer JET divertor was determined with a set of tungsten coated divertor ...
The interaction of tokamak plasma with several materials considered for the plasma facing components...
Damage caused by plasma-surface interactions is of concern in fields involving the use of such plasm...
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions i...
The paper concerns experimental investigations of plasma facing components erosion under the plasma ...