Reinstallation of the COMPASS-D tokamak in IPP ASCR

Abstract

The COMPASS-D tokamak, originally operated by UKAEA at Culham, UK, will be reinstalled at the Institute of Plasma Physics (IPP) AS CR. The COMPASS device was designed as a flexible tokamak in the 1980s mainly to explore the MHD physics. Its operation (with D-shaped vessel) began at the Culham Laboratory of the Association EURATOM/ UKAEA in 1992.The COMPASS-D tokamak will have the following unique features after putting in operation on IPP Prague. It will be the smallest tokamak with a clear H-mode and ITERrelevant geometry. ITER-relevant plasma conditions will be achieved by installation of two neutral beam injection systems (2 × 300 kW), enabling co-and counter-injections. Redeployment of the existing LH system (400 kW) is also envisaged. A comprehensive set of diagnostics focused mainly on the edge plasma will be installed.The scientific programme proposed for the COMPASS-D tokamak installed in IPP Prague will benefit from these unique features of COMPASS-D and consist of two main scientific projects, both highly relevant to ITER -Edge plasma physics (H-mode studies) and Wave-plasma interaction studies.The COMPASS-D tokamak will offer an important research potential as a small, flexible and low-cost facility with ITER-relevant geometry.

Deconvolution-based correction of alkali beam emission spectroscopy density profile measurements

“…Partially for this purpose, as well as to support the design and interpretation of BES measurements, the RENATE alkali BES simulation code has been developed. For the purpose of this study, alkali BES set-up and plasma parameters are chosen from the recently upgraded TEXTOR Li-BES diagnostic [13], and the alkali BES diagnostic planned for the newly restarted COMPASS [14]. We investigate the character and magnitude of the systematic error in density profile reconstruction, and conclude that it can be significant in certain, experimentally relevant cases, which we support with a general estimation of the maximal error in the calculated electron density.…”

Contribution to fusion research from IAEA coordinated research projects and joint experiments

“…Compass-D, Alcator C-Mod, T-10, Globus-M, START, RTP, TEXT, TJ-2, Uragan-2M, Uragan-3 and others have (or had) extended research programmes, wellequipped with sophisticated diagnostics and powerful heating systems. Figure 3 shows results from very advanced Thomson scattering diagnostics on COMPASS, IPP-AS Prague [30,31], and comparison of Thompson scattering (TS) measurements with very high core and edge resolution with reflectometry and Langmuir probes (LPs). Similar diagnostics on C-Mod, T-10 and Globus-M allows detailed investigation of the tokamak transport.…”

Finite Element Analysis of Glass Vacuum Windows of the “COMPASS” Tokamak in Prague

“…The "COMPASS" tokamak of IPP-CR in Prague is a medium size fusion device producing plasma with ITER-like shape [1]. Proper operation of such fusion devices need to fulfil some necessary prerequisites ( Fig.…”