The COMPASS Tokamak Plasma Control Software Performance

IEEE Transactions on Nuclear Science(2011)

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摘要
The COMPASS tokamak has began operation at the IPP Prague in December 2008. A new control system has been built using an ATCA-based real-time system developed at IST Lisbon. The control software is implemented on top of the MARTe real-time framework attaining control cycles as short as 50 μs, with a jitter of less than 1 μs. The controlled parameters, important for the plasma performance, are the plasma current, position of the plasma current center, boundary shape and horizontal and vertical velocities. These are divided in two control cycles: slow at 500 μs and fast at 50 μs. The project has two phases. First, the software implements a digital controller, similar to the analog one used during the COMPASS-D operation in Culham. In the slow cycle, the plasma current and position are measured and controlled with PID and feedforward controllers, respectively, the shaping magnetic field is preprogrammed. The vertical instability and horizontal equilibrium are controlled with the faster 50-μs cycle PID controllers. The second phase will implement a plasma-shape reconstruction algorithm and controller, aiming at optimized plasma performance. The system was designed to be as modular as possible by breaking the functional requirements of the control system into several independent and specialized modules. This splitting enabled tuning the execution of each system part and to use the modules in a variety of applications with different time constraints. This paper presents the design and overall performance of the COMPASS control software.
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plasma magnetohydrodynamics,plasma instability,feedforward,tokamak devices,preprogrammed shaping magnetic field,plasma shape controller,plasma current center position,compass control software performance,horizontal equilibrium,atca based real time system,fusion reactor instrumentation,real-time software systems,plasma horizontal velocity,marte real time framework,plasma toroidal confinement,control engineering computing,plasma control software,compass tokamak,software performance evaluation,pid controller,data acquisition,electric current control,ipp prague,velocity control,atca,magnetic field,plasma shape reconstruction algorithm,plasma vertical velocity,vertical instability,digital controller,ist lisbon,control systems,real-time,plasma performance,position control,compass tokamak plasma control software performance,time 50 mus,horizontal plasma equilibrium,tokamak plasmas,vertical plasma instability,feedforward controller,three-term control,plasma boundary shape,digital control,time 500 mus,plasma transport processes,plasma boundary layers,control system,real time,real time systems,functional requirement,plasmas,compass,software performance
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