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Ferro, A.*; Gaio, E.*; Novello, L.*; 松川 誠; 島田 勝弘; 川俣 陽一; 武智 学
Fusion Engineering and Design, 98-99, p.1053 - 1057, 2015/10
被引用回数：3 パーセンタイル：25.85(Nuclear Science & Technology)JT-60SA is the satellite tokamak under construction in Naka, Japan, in the framework of the EU - JA "Broader Approach" Agreement. In JT-60SA, to attain steady-state high-beta plasmas, suppression of Resistive Wall Modes (RWM) is necessary. At this purpose, a passive stabilizing plate (SP) and an active control system based on 18 in-vessel sector coils (SC) are foreseen. This paper firstly reports the main requirements for the RWM control system. Then, the reference design of the RWM-PS is described. It includes an ac/dc conversion system, dc-link capacitor banks and a set of 18 fast inverters. The advantages of the proposed scheme are discussed and the main electrical parameters are shown in detail. The main requirements of the control section are given, with details on possible implementation and interfaces with JT-60SA central control.
Novello, L.*; Baulaigue, O.*; Coletti, A.*; Dumas, N.*; Ferro, A.*; Gaio, E.*; Lampasi, A.*; Maistrello, A.*; 松川 誠; 島田 勝弘; et al.
Fusion Engineering and Design, 98-99, p.1122 - 1126, 2015/10
被引用回数：16 パーセンタイル：79.46(Nuclear Science & Technology)JT-60SA, the superconducting tokamak under construction in Japan, will be equipped with a mix of new and reused Power Supplies (PS). Most of the new PS are procured by European Voluntary Contributors under the framework of Broader Approach agreement between F4E and JAEA. For the toroidal circuit, the 6 pulses ac/dc converter will be procured by CEA. It is rated 25.7 kA and 80 V dc, and will work in steady state condition. For the poloidal circuits the procurement of ten ac/dc converters, rated 
20 kA and about 1 kV is shared between CEA and ENEA. They are 24 pulses four quadrant converters, with back to back thyristor bridges. Plasma initiation requires a fast variation of current in the Central Solenoids, obtained with the insertion of a settable resistor in series to the coils. This is achieved with the operation of four Switching Network Units procured by ENEA, producing up to 5 kV at the nominal 20 kA. The protection of superconducting magnets, both toroidal and poloidal, is assured by 13 Quench Protection Circuits procured by Consorzio RFX, rated 20 kA and 3.8 kV for poloidal QPCs and 25.7 kA and 2.8 kV for toroidal ones. The present status of the aforementioned PS is described in the paper: their detailed design has been completed and some systems have been already manufactured and tested.
Maistrello, A.*; Gaio, E.*; Ferro, A.*; Perna, M.*; Panizza, C.*; Soso, F.*; Novello, L.*; 松川 誠; 山内 邦仁
IEEE Transactions on Applied Superconductivity, 24(3), p.3801505_1 - 3801505_5, 2014/06
被引用回数：14 パーセンタイル：58.6(Engineering, Electrical & Electronic)This paper deals with the qualification process of the full scale prototypes of the Hybrid mechanical-static dc Circuit Breaker (HCB) for the Quench Protection Circuits (QPC) of the Toroidal Field (TF) and Poloidal Field (PF) superconducting coils of the Satellite Tokamak JT-60SA. The HCB developed for JT-60SA QPC is the first dc circuit breaker based on hybrid mechanical-static design at this level of power (25.7 kA - 1.93 kV, 20 kA - 3.8 kV). Special type tests have been designed to verify the performance of the device up to the nominal ratings and beyond, thus proving the suitability of the technology, the design margins and the reliability; the results of the most significant tests are presented and discussed. The qualification program also includes the validation of the electrical models developed during the design phase, which are described in the paper too.
Toigo, V.*; Zanotto, L.*; Bigi, M.*; Decamps, H.*; Ferro, A.*; Gaio, E.*; Guti
rrez, D.*; 土田 一輝; 渡邊 和弘
Fusion Engineering and Design, 88(6-8), p.956 - 959, 2013/10
被引用回数：18 パーセンタイル：79.79(Nuclear Science & Technology)ITER NBIの加速電源の設計進捗を報告する。この電源は1MVで55MW、準定常の大パワー電源であり、挑戦的なシステムである。EU国内機関と日本国内機関とで分担して製作することから、特に共通のインターフェースとするために設計が複雑である。この二つのシステムの間での重要なインターフェースについての改訂について報告する。さらに、異なるパラメータの許容値を考慮した運転状態において要求を満足することを確認したことを報告する。
松川 誠; 島田 勝弘; 山内 邦仁; Gaio, E.*; Ferro, A.*; Novello, L.*
Plasma Science and Technology, 15(3), p.257 - 260, 2013/03
被引用回数：7 パーセンタイル：30.26(Physics, Fluids & Plasmas)トカマク装置において高性能プラズマを実現するためには、誤差磁場補正が重要な課題の一つである。実際、国際熱核融合実験炉ITERにおいては、誤差磁場補正用の超伝導コイルが計画されており、JT-60SA装置では常伝導コイルが使用される予定である。同様のコイルは、他の世界中の多くの装置で据え付けられており、また運転中でもある。JT-60SA装置の場合、誤差磁場補正コイルは12個(あるいは18個)のセクターコイルが真空容器内に設置される予定である。本論文は、このような誤差磁場補正コイル用電源の回路構成と制御方式にかかわる概念設計について述べるものである。結論としては、電流フィーダや半導体電力素子の数を最小化することのできる多相インバータが、コスト面のみならず、軸対称成分による誘導電圧を相殺できる点などから、最も有望であることを示す。
Coletti, A.*; Baulaigue, O.*; Cara, P.*; Coletti, R.*; Ferro, A.*; Gaio, E.*; 松川 誠; Novello, L.*; Santinelli, M.*; 島田 勝弘; et al.
Fusion Engineering and Design, 86(6-8), p.1373 - 1376, 2011/10
被引用回数：20 パーセンタイル：81.61(Nuclear Science & Technology)JT-60SA is a joint international research and development project involving Japan and Europe, in the frame of the "Broader Approach Agreement", for the construction and operation of a new tokamak intended to prepare and support ITER operation. JT-60SA is to be built in Naka, Japan, using existing infrastructures and subsystems of the former JT-60U experiment, as much as possible. SA, as "super advanced", refers to the use of Superconducting Coils Magnets (SCM) and to the study of advanced modes in plasma operation. The SCM system includes Toroidal and Poloidal Field Coils (TFC and PFC respectively). In addition the machine features a number of normal conducting coils: Fast Plasma Control Coils (FPCC), a Resistive Wall Mode Control Coils and the Error Field Correction Coils. The paper describes the main features of the JT-60SA SCM Power Supply System (SCMPS) with special regard to coil current regulation mode and SCM protection.
Ferro, A.*; Gaio, E.*; 武智 学; 松川 誠
Fusion Engineering and Design, 86(6-8), p.1527 - 1530, 2011/10
被引用回数：2 パーセンタイル：18.29(Nuclear Science & Technology)JT-60SAにおいて定常高ベータ運転を行うには抵抗性壁モード(RWM)の安定化が必須である。そのため、JT-60SAには真空容器内に安定化板とRWM制御コイルが設置される予定である。この論文ではこのRWM制御コイルの電磁気解析を行うことにより、コイルの生成する磁場の強さや分布を調べ、必要な電圧や電流値等の評価を行う。また、ディスラプションやVDE時の誘起電流を示す。これらの結果はRWM制御コイルとその電源の設計の進展の指針となる。
松川 誠; 寺門 恒久; 山内 邦仁; 島田 勝弘; Cara, P.*; Gaio, E.*; Novello, L.*; Ferro, A.*; Coletti, R.*; Santinelli, M.*; et al.
Journal of Plasma and Fusion Research SERIES, Vol.9, p.264 - 269, 2010/08
Reliable plasma initiation is very important in the nuclear fusion devices especially in superconducting tokamaks. Applicable breakdown electric field would be limited up to level of 0.5 V/m to suppress large AC losses in the superconducting magnet. Furthermore, induced current in the passive structure such as vacuum vessel and stabilizing plate would increased easily to the comparable level of plasma current with several hundred kA even in the case of ECH assist breakdown. Therefore, optimization of the applied voltage to the poloidal field coil is necessary for stable plasma initiation. In this paper, the rationalized plasma initiation scenario using cost effectively designed power supply system will be provided.
松永 剛; 武智 学; 櫻井 真治; 井手 俊介; 松川 誠; 大山 直幸; 相羽 信行; 栗田 源一; Ferro, A.*; Gaio, E.*; et al.
no journal, ,
JT-60SA is designed and under construction as fully superconducting tokamak under a combined project of the ITER satellite tokamak program of EU-JA (Broader Approach Activities) and the Japanese national program. One of the main purposes of JT-60SA is the steady-state high-beta operation above the ideal no-wall beta-limit with suppressing resistive wall modes (RWMs). In order to control the RWMs, the RWM control coils and error field correction coils (EFCCs) are to be installed. The current design of these coils composes of 18 sector coils (6 coils in toroidally and 3 coils in poloidally) so as to suppress n=1-3 RWMs and to compensate various error fields. The EFCCs can also be utilized to apply the resonant magnetic perturbation to ergodize the peripheral magnetic field structure to mitigate and avoid the large edge localized modes. The design and analysis of these in-vessel tools for high-beta plasmas on JT-60SA will be presented.
武智 学; 松永 剛; 栗田 源一; 櫻井 真治; 藤枝 浩文*; 井手 俊介; 相羽 信行; Bolzonella, T.*; Ferro, A.*; Novello, L.*; et al.
no journal, ,
JT-60SAの最も重要な目的の一つは、ITERからDEMOへの補完のために定常高ベータ運転の実証と開発を行うことである。高ベータプラズマにおいて問題となる抵抗性壁モードの安定化に用いる制御コイル及び電源の仕様をフィードバックシミュレーション及びFEM解析を用いて行った。プラズマ着火時,ロックトモード回避,抵抗性壁モード安定化に重要な誤差磁場の補正コイルの仕様をNBIの打消しコイルの磁場評価及びトロイダルコイルとポロイダルコイルの公差から決定した。また、高速位置制御コイルの仕様を位置制御のフィードバックシミュレーションから決定した。これらの制御システムを用いて
MAにおいて
の非誘導定常プラズマが可能となる。さらに、ディスラプションシミュレーションを機器の電磁力の評価のために行った。
山内 邦仁; Baulaigue, O.*; Coletti, A.*; Coletti, R.*; Ferro, A.*; Gaio, E.*; Lampasi, A.*; 松川 誠; Novello, L.*; 島田 勝弘; et al.
no journal, ,
The JT-60SA tokamak device consists of superconducting toroidal field (TF) and poloidal field (PF) coils, and some in-vessel coils. All of 18 TF coils are connected in series and powered by a low-voltage unidirectional DC power supply (PS), while three Quench Protection Circuits (QPCs) are inserted for every six TF coils. Meanwhile, each PF coil circuit is independent from the others, and a bidirectional DC current is driven for plasma current ramp-up and sustainment by series-connected Base PS, and Switching Network Unit or Booster PS. TF coils are energized by commercial electric power grid directly, but the rest of the coils are planned to be powered by the existing motor-generator of JT-60. This paper describes the key features and the expected performances of the main PS system for the superconducting magnets in JT-60SA.
