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Development of ITER-relevant plasma control solutions at DIII-D
Humphreys, D.A.,Ferron, J.R.,Bakhtiari, M.,Blair, J.A.,In, Y.,Jackson, G.L.,Jhang, H.,Johnson, R.D.,Kim, J.S.,LaHaye, R.J.,Leuer, J.A.,Penaflor, B.G.,Schuster, E.,Walker, M.L.,Wang, H.,Welander, A.S. International Atomic Energy Agency 2007 Nuclear fusion Vol.47 No.8
<P>The requirements of the DIII-D physics program have led to the development of many operational control results with direct relevance to ITER. These include new algorithms for robust and sustained stabilization of neoclassical tearing modes with electron cyclotron current drive, model-based controllers for stabilization of the resistive wall mode in the presence of ELMs, coupled linear–nonlinear algorithms to provide good dynamic axisymmetric control while avoiding coil current limits, and adaptation of the DIII-D plasma control system (PCS) to operate next-generation superconducting tokamaks. Development of integrated plasma control (IPC), a systematic approach to model-based design and controller verification, has enabled successful experimental application of high reliability control algorithms requiring a minimum of machine operations time for testing and tuning. The DIII-D PCS hardware and software and its versions adapted for other devices can be connected to IPC simulations to confirm control function prior to experimental use. This capability has been important in control system implementation for tokamaks under construction and is expected to be critical for ITER.</P>
Controls on KSTAR Superconducting Poloidal Field (PF) Magnets
Hahn, Sang-Hee,Kim, K.H.,Choi, J.H.,Ahn, H.S.,Lee, D.K.,Park, K.R.,Eidietis, N.W.,Leuer, J.A.,Walker, M.L.,Yang, H.L.,Kim, W.C.,Oh, Y.K. The Korean Society of Superconductivity and Cryoge 2008 한국초전도저온공학회논문지 Vol.10 No.4
As a part of the plasma control system (PCS) for the first plasma campaign of KSTAR, seven sets of fast feedback control loop for the superconducting poloidal field magnet power supply (PF MPS) have been implemented. A special real-time digital communication interface has been developed for the simultaneous exchanges of the current/voltage data from the 7 sets of 12-thyristor power supplies in a 200 microsecond control cycle. Preliminary power supply tests have been performed before actual cooldown of the device. A $29mH/50m{\Omega}$ solenoid dummy has been fabricated for a series of single power supply tests. Connectivity and response speed of the plasma control system have been verified. By changing hardware cabling, this load was also used to estimate mutual inductance coupling effects of two geometrically adjacent solenoid coils on each power supply. After the cooldown was complete, each pair of the up/down symmetric PF coils has been serially connected and tested as part of the device commissioning process. Bipolar operation and longer pulse attempts have been investigated. The responses of the coils and power supplies corresponding to the plasma magnetic controls in plasma discharges are also analyzed for the future upgrades.