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Status of Magnetic Diagnostics on COMPASS
Havlíček, J. ; Kudláček, O. ; Janky, F. ; Horáček, Jan ; Beňo, R. ; Valcárcel, D.F. ; Fixa, J. ; Brotánková, Jana ; Zajac, Jaromír ; Hron, Martin ; Pánek, Radomír ; Cahyna, Pavel
The COMPASS tokamak is in a test operation after its reinstallation in Institute of Plasma Physics AS CR in Prague (IPP Prague) in the year 2008. This operation consists of commissioning of various diagnostics and tokamak auxiliary systems. This paper presents current status of magnetic diagnostics after its refurbishment, used method of the calibration and shows examples of magnetic diagnostics utilization for plasma position reconstruction as well as for vertical hydraulic preload interlock system.
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Navrh filtru pro detekci Thomsonovym rozptylem na tokamaku COMPASS
Aftanas, Milan ; Scannell, R. ; Bílková, Petra ; Böhm, Petr ; Weinzettl, Vladimír ; Walsh, M.
Reinstalled tokamak COMPASS, originally from Culham Science Centre, is now operating at the Institute of Plasma Physics, Prague and many new optical diagnostics are being developed [Sestak et al, 2009]. For measurement of electron temperature and density profiles, high resolution incoherent Thomson scattering spectroscopy based on Nd:YAG laser and avalanche photodiodes is under development now. The paper outlines part of the design of this diagnostic - proper choice of spectral filters. The design of filters is shown and its evaluation taking into account different angle of scattered light is introduced. Error bars of the electron temperature, density and pressure are determined with respect to assumed electron temperature and density profiles and to required high spatial resolution at the pedestal region.
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Komunikační protokol pro kontrolu polohy a tvaru plazmatu tokamaku COMPASS
Janky, F. ; Horáček, Jan ; Pereira, T.V.
The Compass tokamak, reinstalled at IPP Prague, will have a new digital plasma position and shape control system. Development of a communication protocol is necessary for the connection between the energetics devices built by CKD company and the operator - either human or computer together. The present work is focused on development of such communication protocol. Human operator can send a request for status of energetics, time synchronization, counting errors, etc. through communication protocol. Predefined currents for individual power supplies will be send through the communication protocol. In the future this system will be replaced by feedback control system integrated in CODAC (Control Data Acquisition and Communication system).
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Odhad zareni z plazmatu v systemu Thomsonova rozptylu projektovaneho pro tokamak COMPASS
Aftanas, Milan ; Böhm, Petr ; Weinzettl, Vladimír ; Stöckel, Jan
The COMPASS tokamak, originally from Culham laboratory, UKAEA, has been reinstalled at at Institute of Plasma Physics, Prague. Many innovations will be done and new diagnostics have to be constructed. Electron temperature Te and density ne as as key parameters of fusion plasma will be measured directly by the newly designed high spatial resolution incoherent Thomson scattering (TS) system. Several construction options of TS are considered. In this paper these options are discussed from a point of view of data analysis and estimation of background radiation.
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Charakterizace magnetických polí v tokamaku COMPASS
Havlíček, Josef ; Hronová-Bilyková, Olena
The principle of tokamak is based on the interaction of magnetic fields with the tokamak plasma. The magnetic fields generated by poloidal field coils of the COMPASS tokamak were examined. The stray magnetic field in the vicinity of the tokamak was computed. It was found out that the magnitude of this field is acceptable for operation of the Neutral Beam Injection ion source. The graphs describing magnetic field in the vacuum vessel originating from different poloidal field coils circuits are presented.
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Aplikace magneticke diagnostiku pro tokamak COMPASS
Naydenkova, Diana ; Hronová-Bilyková, Olena ; Stöckel, Jan
The paper outlines the main parameters and characteristics of typical plasma shapes. The reasons, basic physical principles and mechanisms for controlling of a plasma position in vertical and horizontal directions by means of magnetic sensors in the COMPASS tokamak are described below. All main parameters for the position control equate here. The sketchy description of diagnostic sensors and poloidal coils are used for control in COMPASS is done by the authors too. The progress report of current work is present as a summary.
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