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Overview of the COMPASS diagnostics

V. Weinzettl,R. Panek,M. Hron,J. Stockel,F. Zacek,J. Havlicek,P. Bilkova,D.I. Naydenkova,P. Hacek,J. Zajac,R. Dejarnac,J. Horacek,J. Adamek,J. Mlynar,F. Janky,M. Aftanas,P. Bohm,J. Brotankova,D. Sestak,I. Duran,R. Melich,D. Jares,J. Ghosh,G. Anda,G. Veres,A. Szappanos,S. Zoletnik,M. Berta,V.F. Shevchenko,R. Scannell,M. Walsh,H.W. Müller,V. Igochine,A. Silva,M. Manso,R. Gomes,Tsv. Popov,D. Sarychev,V.K. Kiselov,S. Nanobashvili

FUSION ENGINEERING AND DESIGN（2011）

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Abstract
The COMPASS tokamak, a divertor device with clear H-mode and ITER-relevant geometry, has been reinstalled in IPP Prague after its transport from CCFE in UK. The first plasma was achieved in December 2008. Many new diagnostic tools with both high temporal and spatial resolutions have been developed to address the scientific programme of COMPASS focused on H-mode physics and pedestal investigations. In the paper, an overview of existing and in near future planned diagnostics (magnetic, spectroscopy, microwave, probe and beam/particle) on COMPASS is given including their basic technical specifications and achievements. (C) 2011 EURATOM. Published by Elsevier B.V. All rights reserved.
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Key words
Plasma diagnostics,Tokamak,COMPASS
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