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Design and implementation of the plasma control system for the COMPASS tokamak
Janky, Filip ; Horáček, Jan (advisor) ; Kudrna, Pavel (referee) ; Svoboda, Vojtěch (referee)
Design and implementation of the plasma control system Mgr. Filip Janky The COMPASS tokamak was recommissioned in 2007 and it needed new digital controllers for its experimental research. This thesis presents the design and imple- mentation of control of main plasma parameters such as plasma current, plasma position, plasma shape and electron density. Improved plasma current control with resetting set points suppresses overshooting and thus increases the length of the flat top phase. A method for estimating the plasma position, gain tuning for the controller and decreasing latencies and delays to obtain robust position control are presented. Lower delays improve plasma stability and decrease the frequency of disruptions. The plasma shape controller is a feedforward controller with a method to suppress oscillations which are coming from mutual inductance between power supplies controlling plasma horizontal position, plasma shape and plasma current, which all use the same coil. Averaged electron density is corrected in real-time according to the interferometer line of sight and a non-linearity of measurement. Controllers and their improvements described here, played a major role in achiev- ing H-mode scenario and fulfilling the experimental program. Keywords: tokamak, plasma current control, plasma position...
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Preliminary Measurements of Neutrons From The D-D Reaction in The Compass Tokamak
Dankowski, J. ; Janky, Filip ; Kurowski, A. ; Stöckel, Jan ; Twarog, D.
Recent results of measured fast neutrons created in the D-D reaction on the COMPASS tokamak during ohmic discharges are presented in this paper. Two different type detectors were used during experiment. He-3 detectors and bubble detectors as a support. The measurements are an introduction for neutron diagnostic on tokamak COMPASS and monitoring neutrons during discharges with Neutral Beam Injection (NBI). The He-3 counters and bubble detectors were located in two positions near tokamak vacuum chamber at a distance less than 40 cm to the centre of plasma. The neutrons flux was observed in ohmic discharges. However, analysis of our results does not indicate any clear source of neutrons production during ohmic discharges.
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Design and implementation of the plasma control system for the COMPASS tokamak
Janky, Filip ; Horáček, Jan (advisor) ; Kudrna, Pavel (referee) ; Svoboda, Vojtěch (referee)
Design and implementation of the plasma control system Mgr. Filip Janky The COMPASS tokamak was recommissioned in 2007 and it needed new digital controllers for its experimental research. This thesis presents the design and imple- mentation of control of main plasma parameters such as plasma current, plasma position, plasma shape and electron density. Improved plasma current control with resetting set points suppresses overshooting and thus increases the length of the flat top phase. A method for estimating the plasma position, gain tuning for the controller and decreasing latencies and delays to obtain robust position control are presented. Lower delays improve plasma stability and decrease the frequency of disruptions. The plasma shape controller is a feedforward controller with a method to suppress oscillations which are coming from mutual inductance between power supplies controlling plasma horizontal position, plasma shape and plasma current, which all use the same coil. Averaged electron density is corrected in real-time according to the interferometer line of sight and a non-linearity of measurement. Controllers and their improvements described here, played a major role in achiev- ing H-mode scenario and fulfilling the experimental program. Keywords: tokamak, plasma current control, plasma position...
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Measurements of Ion Temperature in the Edge Plasma of the COMPASS Tokamak
Naydenkova, Diana ; Janky, Filip ; Weinzettl, Vladimír ; Stöckel, Jan ; Šesták, David ; Odstrčil, T. ; Ghosh, J. ; Gomes, R. ; Pereira, T.
The two-grating spectrometer, which has been developed for the ISTTOK tokamak, allows an estimation of the temporal evolution of both ion temperature and poloidal velocity of the edge plasma by analysis of Doppler-shifted and broadened CIII spectral lines at ~465nm. At the current phase of the COMPASS tokamak operation, the first measurements of ion temperature using the optical system based on the spectrometer were performed and first results are presented.
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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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Kontrola vakua a plynového systému pro tokamak COMPASS
Janky, F. ; Pereira, T.V. ; Santos, B.A. ; Hron, Martin
This paper is aimed at creating a vacuum and a gas handling subsystem. The new vacuum and the gas handling subsystem was developed at IPP/Prague after the COMPASS tokamak reinstallation. It was necessary to build a system which can operate 24/7 and be fully autonomous. A firmware programmed in the C programming language controls devices connected to the vacuum and the gas handling subsystem. The firmware is programmed at dsPICr Microchip r embedded at a board assembled at IST Lisbon. The vacuum and the gas handling are connected through fiber optics to a server computer and can be controlled remotely through a workstation situated at the control room
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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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