Conceptual Design of DC Power Supplies for FFHR Superconducting Magnet

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概要

• 論文の詳細を見る

• The force-free helical reactor (FFHR) is a helical-type fusion reactor whose design is being studied at the National Institute for Fusion Science. The FFHR will use three sets of superconducting coils to confine the plasma. It is not a fusion plasma experimental device, and the magnetic field configuration will be optimized for burning plasma. This paper introduces a conceptual design for a dc power system to excite the superconducting coils of the FFHR. In this design, the poloidal coils are divided into a main part, which generates a magnetic field for steady-state burning, and a control part, which is used in the ignition process to control the magnetic axis. The feasibility of this configuration was studied using the Large Helical Device coil parameters, and the coil voltages required to sweep the magnetic axis were calculated. It was confirmed that the axis sweep could be performed without a high output voltage from the main power supply. Finally, the power supply ratings for the FFHR were estimated from the stored magnetic energy.

• 社団法人 プラズマ・核融合学会の論文

著者

• CHIKARAISHI Hirotaka

  National Institute for Fusion Science

関連論文

• Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
• 大型ヘリカル装置用超伝導マグネット運転の現状 : 2001年秋
• DC Power System for Superconducting Coils of Fusion Plasma Test Facility LHD
• Hysteresis Loss in Poloidal Coils of the Large Helical Device
• Conceptual Design of DC Power Supplies for FFHR Superconducting Magnet

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