This paper summarizes the status of the COMPASS tokamak, its comprehensive diagnostic
equipment and plasma scenarios as a baseline for the future studies. The former COMPASS …

The COMPASS tokamak, a divertor device with clear H-mode and ITER-relevant geometry,
has been re-installed in IPP Prague after its transport from CCFE in UK. The first plasma was …

Abstract Wendelstein 7-X (W7-X) is a large optimized stellarator (B= 2.5 T, V= 30m 3) aiming
at demonstrating the reactor relevance of the optimized stellarators. In 2015 W7-X will begin …

Light reflections are one of the main and often underestimated issues of plasma emissivity
reconstruction in visible light spectral range. Metallic and other specular components of …

Abstract The COMPASS tokamak (R= 0.56 m, a= 0.2 m, BT= 1.3 T, I p~ 300 kA, pulse
duration 0.4 s) operates in ITER-like plasma shape in H-mode with Type-I ELMs. In 2019, we …

An efficient horizontal and vertical stabilization of the plasma column position are essential
for a reliable tokamak operation. Plasma position is generally determined by plasma current …

This paper presents an overview of the Control, Data Acquisition, and Communication
system (CODAC) at the COMPASS tokamak: the hardware set-up, software implementation …

The COMPASS tokamak has been recently equipped with two new fast (max. 800 kfps) color
cameras Photron FASTCAM Mini UX100 operating in the visible spectral range. A new data …

Semiconductor detector arrays are widely used in high-temperature plasma diagnostics.
They have a fast response, which allows observation of many processes and instabilities in …

The interaction of tokamak plasma with several materials considered for the plasma facing
components of future fusion devices was studied in a small-size COMPASS tokamak. These …