Parametric studies about vertical position control of the INTOR elongated plasma.

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概要

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• Considering only the most dominant of many eddy current modes induced in a fusion reactor, the authors estimated the shell effect required for suppression of the axisymmetric vertical positional instability of an elongated plasma. Here more accurate analysis involving higher eddy current modes is used. Also using this analysis, dependence of the shell effect and the plasma control characteristics upon the reactor structure is investigated. The parameters under consideration are shell shapes, number of the shells around the torus, and thickness of the shell structures for the shell effect. The delay time on a vertical position detection for the plasma, and the dead time of a power supply for the control coils are chosen as parameters for the feedback control system of the plasma position, too. Moreover, field penetration on the vertical position control into the plasma center is studied in order to show the appropriateness for the results in this paper.

• 社団法人 プラズマ・核融合学会の論文

著者

• Nishio Satoshi

  Naka Fusion Research Establishment Japan Atomic Energy Research Institute

• Sugihara Masayoshi

  Naka Fusion Research Establishment Japan Atomic Energy Research Institute

• 上田 孝寿

  Mitsubishi Electric Corp.

• Fujisawa Noboru

  Naka Fusion Research Establishment, Japan Atomic Energy Research Institute

関連論文

• Magnetic Field Analysis during Breakdown Phase in the Low Loop Resitance Tokamak HT-2
• VDE Characteristics during Disruption Process and its Underlying Acceleration Mechanism in the ITER-EDA Tokamak
• Confinement of Alpha Particles in a Low-Aspect-Ratio Tokamak Reactor
• Formation of Cold and Dense Divertor Plasma during Phases of Non-Inductive Current Ramp-Up and Recharging in Tokamak Fusion Reactor : Nuclear Science, Plasmas and Electric Discharges
• Parametric studies about vertical position control of the INTOR elongated plasma.

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