Erosion characteristics of a tungsten plate heated up in TEXTOR by the plasma load have been investigated at temperatures extending to the melting point. No enhancement of atomic release exceeding physical sputtering and normal thermal sublimation for temperatures below 3700 K was observed. The liquid tungsten moved fast along the plate in the direction perpendicular to the magnetic field lines. The motion is caused by the Lorentz force due to the thermoelectron current emitted from the hot tungsten surface. The motion of liquid tungsten caused a material loss of 2.85 g during two discharges. The material redistribution due to the melt layer motion is compared with a MEMOS-1.5D simulation. (c) 2007 Elsevier B.V. All rights reserved
AbstractThe thickness of Tungsten monoblocks composing the future ITER divertor is supposed to be 8m...
Three different types of W limiters were exposed in the TEXTOR plasma and the response of the plasma...
Metallic materials such as tungsten and beryllium are candidates for the design of the plasma facing...
The paper provides an overview of processes and underlying physics governing tungsten melt erosion i...
The behaviour of tungsten (W) plasma-facing components (PFCs) has been investigated in the plasma ed...
Behaviour and characteristics of W plasma-facing components under impinging high heat fluxes are inv...
Tungsten samples were exposed to combined steady state and edge localised mode transient replication...
Tungsten samples were exposed to combined steady state and edge localised mode transient replication...
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions i...
To examine the performance of a castellated structure under plasma loading, a hemispherical solid tu...
The first MEMOS 3D simulations of liquid metal motion on an inclined bulk tungsten sample transientl...
In order to evaluate the applicability of toughened, fine-grained, recrystallized (TFGR)-W to tokama...
We investigated the erosion behaviour of tungsten under irradiation with a fusion reactor-relevant H...
In TEXTOR-93, experiments have been performed with the upper and lower poloidal limiter blocks made ...
In TEXTOR-94 experiments have been performed with the upper and lower poloidal limiter tiles made of...
AbstractThe thickness of Tungsten monoblocks composing the future ITER divertor is supposed to be 8m...
Three different types of W limiters were exposed in the TEXTOR plasma and the response of the plasma...
Metallic materials such as tungsten and beryllium are candidates for the design of the plasma facing...
The paper provides an overview of processes and underlying physics governing tungsten melt erosion i...
The behaviour of tungsten (W) plasma-facing components (PFCs) has been investigated in the plasma ed...
Behaviour and characteristics of W plasma-facing components under impinging high heat fluxes are inv...
Tungsten samples were exposed to combined steady state and edge localised mode transient replication...
Tungsten samples were exposed to combined steady state and edge localised mode transient replication...
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions i...
To examine the performance of a castellated structure under plasma loading, a hemispherical solid tu...
The first MEMOS 3D simulations of liquid metal motion on an inclined bulk tungsten sample transientl...
In order to evaluate the applicability of toughened, fine-grained, recrystallized (TFGR)-W to tokama...
We investigated the erosion behaviour of tungsten under irradiation with a fusion reactor-relevant H...
In TEXTOR-93, experiments have been performed with the upper and lower poloidal limiter blocks made ...
In TEXTOR-94 experiments have been performed with the upper and lower poloidal limiter tiles made of...
AbstractThe thickness of Tungsten monoblocks composing the future ITER divertor is supposed to be 8m...
Three different types of W limiters were exposed in the TEXTOR plasma and the response of the plasma...
Metallic materials such as tungsten and beryllium are candidates for the design of the plasma facing...