Development of plasma control system for divertor configuration on QUEST

M. Hasegawa, K. Nakamura, H. Zushi, K. Hanada, A. Fujisawa, K. Matsuoka, O. Mitarai, H. Idei, Y. Nagashima, K. Tokunaga, S. Kawasaki, H. Nakashima, A. Higashijima

研究成果: Contribution to journalArticle査読

4 被引用数 (Scopus)

抄録

A plasma control system to sustain divertor configurations is developed on QUEST (Q-shu university experiment with steady-state spherical tokamak). Magnetic fluxes are numerically integrated at 100 kHz using FPGA (Field-Programmable Gate Array) modules and transferred to a main calculation loop at 4 kHz. With these signals, plasma shapes are identified in real time at 2 kHz under the assumption that the plasma current can be represented as one filament current. This calculation is done in another calculation loop in parallel by taking advantage of a multi-core processor of the plasma control system. The inside and outside plasma edge positions are controlled to their target positions using PID (proportional-integral-derivative) control loops. Whereas the outside edge position can not be controlled by the outer PF coil current, the inside edge position can be controlled by the inner PF coil current.

本文言語英語
ページ(範囲)1074-1077
ページ数4
ジャーナルFusion Engineering and Design
88
6-8
DOI
出版ステータス出版済み - 2013

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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