On the eve of component procurement, this paper discusses the present physics basis for
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …

Partial detachment is the desired regime for the baseline burning plasma scenario in ITER
and other next-step devices, as it allows for the dissipation of the majority of the energy …

Plasma probes are well established diagnostic tools. They are not complicated, relatively
easy to construct and to handle. The easiest and fastest accessible parameter is their …

A new system of probes was recently installed in the divertor of tokamak COMPASS in order
to investigate the ELM energy density with high spatial and temporal resolution. The new …

Abstract Analysis of heat fluxes in scrape-off layer (SOL) plasma is important for the
prediction of divertor tile heat loads in future reactor-sized tokamak machines. Typically, the …

Microsecond probe measurements of the electron temperature during the tokamak edge
localised mode (ELM) instability show that the peak values significantly exceed those …

Abstract The COMPASS-U tokamak (R= 0.894 m, a= 0.27 m, B t= 5 T, I p= 2 MA) is a new
medium-size device with fully metallic plasma facing components, currently under …

The COMPASS tokamak at IPP Prague is a small-size device with an ITER-relevant plasma
geometry and operating in both the Ohmic as well as neutral beam assisted H-modes since …

In fusion devices strong interest is deserved to the edge filament transport both related to
turbulent and ELMy structures, because they are believed to provide important interaction …

Three new in-vessel manipulators are designed and built for the new COMPASS Upgrade
tokamak with uniquely high vessel temperature (250–500 C) and heat flux density …