FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Development and test of the poloidal field prototype coil POLO at the Forschungszentrum Karlsruhe

M. Darweschsad, G. Friesinger, R. Heller, M. Irmisch, F. Wüchner1997年Fusion Engineering and DesignIF 1.7出版社

AbstractA superconducting prototype (3 m Ø and nominal current 15 kA) of a poloidal field coil was developed, constructed and tested according to the typical specification of the Tokamak magnet system in collaboration with European industry. In order to withstand fast ramping (≈2 T s−1), plasma disruption (80 T s−1, 10 ms) and plasma control (≈ ±0.05 T, 10 Hz) in the superconducting state a low loss conductor and a well developed high voltage technique at 4 K were indispensable attributes of the design. The sc cable of the conductor consists of mixed matrix strands (NbTi in Cu/CuNi) cooled by a dual cooling system (two phase forced flow helium for heat removal at constant temperature, and stagnant helium for good transient stability). The sc cable is inclosed in a thick walled stainless steel jacket. All coil components are designed and constructed according to the rules of the high voltage technique. The coil was tested in the TOSKA facility at FZK-Karlsruhe. For generating the typical positive and negative magnetic field transients a special high power switching circuit of a discharge power up to 700 MW (30 kA, 23 kV) was constructed and used. The coil was investigated considering its superconducting, electromagnetic and mechanical properties. All results were conclusive in agreement with calculations and fulfil the specifications. A highlight is that for this conductor type the stability against transient field changes is only determined by the expected stability margin or the critical current boundary no other limitations of the ramp rate were observed.

日本語訳

超伝導プロトタイプ(公称電流15 kA、直径3 m)のポロイダル磁場コイルが、トカマク磁石システムの標準仕様に従って、欧州産業界との協力のもと開発、建設、試験された。超伝導状態での高速ランプ(≈2 T s⁻¹)、プラズマディスラプション(80 T s⁻¹、10 ms)、およびプラズマ制御(≈±0.05 T、10 Hz)に耐えるためには、低損失導体と、4 Kにおける高度に発達した高電圧技術が設計上不可欠であった。導体の超伝導ケーブルは、混合マトリックス素線(Cu/CuNi中のNbTi)で構成され、二重冷却システム(熱除去のための一定温度での二相強制流ヘリウム、および過渡安定性のための静止ヘリウム)によって冷却される。超伝導ケーブルは、厚肉ステンレス鋼ジャケット内に封入されている。すべてのコイル構成要素は、高電圧技術の規則に従って設計・建設された。コイルは、FZKカールスルーエのTOSKA施設で試験された。典型的な正および負の磁場過渡現象を生成するために、最大700 MW(30 kA、23 kV)の放電出力を有する特殊な大電力スイッチング回路が建設され、使用された。コイルは、超伝導特性、機械的特性、および電磁的特性に関して調査された。すべての結果は、計算と一致し、仕様を満たすものであった。特筆すべき点として、この導体では、過渡磁場変化に対する安定性は、予想される安定性マージンまたは臨界電流境界によってのみ決定され、ランプ速度に関する他の制限は観察されなかった。

この論文にはまだAI要約がありません。

関連論文

Protection measures for selected ITER magnet system off-normal conditions

1998Fusion Engineering and Design

Research and development of superconductors and superconducting coils for the Large Helical Device

1993Fusion Engineering and Design

Design of the poloidal field system and plasma equilibrium of HT-7U tokamak

2001Fusion Engineering and Design

Present status of superconducting magnets design for the Large Helical Device

1993Fusion Engineering and Design

Experimental results of the R&D forced-flow poloidal coil (TOKI-PF)

1993Fusion Engineering and Design

Development of a novel spiral antenna system for low loop voltage current start-up at the Steady State Superconducting Tokamak (SST-1)

2022Plasma Physics and Controlled Fusion

Recent results from R&D on superconductors at CRPP

2003Nuclear Fusion

Design of the toroidal field coil for A-SSTR2 using high Tc superconductor

2001Fusion Engineering and Design

Toroidal field coil design for the spherical tokamak power plant

2000Fusion Engineering and Design

Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor

2015Nuclear Fusion