West Magnetic Control

2019 IEEE 58TH CONFERENCE ON DECISION AND CONTROL (CDC)(2019)

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摘要
The WEST facility is an upgrade of the former Tore Supra tokamak. Two in-vessel coils have been added to elongate the plasma shape and achieve diverted magnetic configuration with one or two X-points. This modification has implied the design of a new plasma control system with a dedicated magnetic control to deal with the vertical instability of the elongated plasma. This paper reports the development of this controller. All the aspects of the design are addressed: modeling of the system with the free-boundary equilibrium code FEEQS, controller design based on robust synthesis, simulation and experimental results.
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关键词
free-boundary equilibrium code FEEQS,controller design,WEST magnetic control,WEST facility,Tore Supra tokamak,in-vessel coils,plasma shape,magnetic configuration,plasma control system,dedicated magnetic control,vertical instability
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