Title of article
Overview of the COMPASS diagnostics
Author/Authors
Weinzettl، نويسنده , , V. and Panek، نويسنده , , R. and Hron، نويسنده , , M. and Stockel، نويسنده , , J. and Zacek، نويسنده , , F. and Havlicek، نويسنده , , J. and Bilkova، نويسنده , , P. and Naydenkova، نويسنده , , D.I. and Hacek، نويسنده , , P. and Zajac، نويسنده , , J. and Dejarnac، نويسنده , , R. and Horacek، نويسنده , , J. and Adamek، نويسنده , , J. and Mlynar، نويسنده , , J. and Janky، نويسنده , , F. and Aftanas، نويسنده , , M. and Bohm، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2011
Pages
5
From page
1227
To page
1231
Abstract
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 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.
Keywords
Plasma Diagnostics , tokamak , COMPASS
Journal title
Fusion Engineering and Design
Serial Year
2011
Journal title
Fusion Engineering and Design
Record number
2358098
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