Feeder components and instrumentation for the JT-60SA magnet system

JT-60SA超伝導マグネットのフィダー部品と計測

吉田 清; 木津 要; 村上 陽之; 神谷 宏治; 本田 敦; 大西 祥広; 古川 真人; 淺川 修二; 倉持 勝也; 栗原 研一

Yoshida, Kiyoshi; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Honda, Atsushi; Onishi, Yoshihiro; Furukawa, Masato; Asakawa, Shuji; Kuramochi, Masaya; Kurihara, Kenichi

JT-60SA装置はEUと日本の共同で、ITERのサテライト・トカマク(JT-60SA)を製作する計画である。JT-60SA用超伝導マグネットは、18個のトロイダル磁場コイルと4個の中心ソレノイド・モジュール、6個の平衡磁場コイルから構成される。超伝導コイルには、交流損失や核発熱で3.2kWの熱負荷が発生し、4.4Kの超伝導臨界ヘリウムで冷却する。そのために、冷凍機からの冷媒を、クライオスタットに取り付けたバルブボックスで分配する。また、コイル端子箱に取り付けた高温超伝導電流リードから、超伝導フィーダーを経由して各コイルに電流を供給する。クエンチ検出などの計測の設計を示す。JT-60SA用超伝導マグネット装置は、既存のJT-60U装置の改造するために、配置や空間的な制限が多く存在していた。それらの設計条件を満足する概念設計が完了したので報告する。

The modifying of the JT-60U magnet system to the superconducting coils (JT-60SA) is progressing as a satellite facility for ITER by both parties of Japanese government and European commission (EU) in the Broader Approach agreement. The magnet system for JT-60SA consists of 18 Toroidal Field (TF) coils, a Central Solenoid (CS) with 4 modules, and 6 Equilibrium Field (EF) coils. The manufacturing of the JT-60SA magnet system is in progress in EU and Japan. The JT-60SA superconducting magnet system generates an average heat load of 3.2 kW at 4 K to the cryoplant, from nuclear and thermal radiation, conduction and electromagnetic heating, and requires current supplies 20 kA for 4 CS modules and 6 EF coils, 25.7 kA to 18 TF coils. The helium flow to remove this heat, consisting of supercritical helium at pressures up to 0.5 MPa and temperature between 4.4-4.8 K, is distributed to the coils and structures through the valve box (VB) from the cryoline connecting to the auxiliary cold box located outside the torus hall. The feeders also contain the electrical supplies from the current lead transitions to room temperature to the coil. The feeder components consist of the in-cryostat feeders with flexible parts to allow coil operational displacements from the connection pipes out of the cryostat, including S-bend conductor to allow differential thermal contraction and the coil terminal boxes (CTBs) with HIS current leads. A measurement and control system is required to monitor and control these coils and feeders for safety and optimal operational availability. For each coil, both current and supercritical helium are supplied from external systems and are controlled from a central system as part of the regular operation with plasma pulses. Quench detection instruments for superconducting coils, feeders and HTS current leads are provided as a separate, stand alone system.