Article ID Journal Published Year Pages File Type
4921071 Fusion Engineering and Design 2017 6 Pages PDF
Abstract
KTX, which stands for “Keda Torus for Experiment”, is a reverse field pinch (RFP) device, with main parameters between RFX and MST. It is supported by China domestic ITER-related research project. The target of KTX is to do the research work of “self-organization”of magnetic confinement plasma. It will include the dynamo and single spiral phenomena. Its magnet system includes the Toroidal Field (TF) coils, Ohmic Heating (OH) coils and Equilibrium field (EF) coils. The toroidal field coils should produce the magnetic field of 0.7 T in center of plasma for the 1 MA operation mode, the current of each TF coil is designed as 210 kA. The power supplies and OH & PF coils are divided into three groups to reduce the voltages on each capacitor bank. Then flux swing is provided by the coils from OH 1 to OH 7, while the stray field in the plasma region is minimized by the coils from OH 8 to OH 13. The total ampere turns of OH coils is optimized as 11.6 MAT with 228 turns in total. The magnet system design is one of the major activities for KTX device design. The key engineering features and design including electromagnetic parameters and related R&D work are presented in this paper.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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