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報告書

JT-60SAクエンチ保護回路の欧州による現地据付・調整試験と作業安全管理

山内 邦仁; 岡野 潤; 島田 勝弘; 大森 栄和; 寺門 恒久; 松川 誠; 小出 芳彦; 小林 和容; 池田 佳隆; 福本 雅弘; et al.

JAEA-Technology 2015-053, 36 Pages, 2016/03

JAEA-Technology-2015-053.pdf:8.33MB

JT-60SA計画は、日本の実施機関である原子力機構と欧州の実施機関であるFusion for Energy(F4E)が物納貢献により共同で進める国際事業である。欧州側では超伝導トロイダル磁場コイルの他、磁場コイル用電源の主要機器や極低温システム等を分担するが、F4Eの総括のもとで各国の指定研究機関が欧州のメーカーと契約し、その欧州のメーカーが那珂研での現地据付・調整試験までを行う。このため、原子力機構にとっては直接の契約がないにも係らず、欧州の作業員に対する作業管理や安全管理を行わなければならないという非常に難しい課題があった。本報告は、JT-60SA計画において、欧州の作業員による最初の那珂研での現地作業であるクエンチ保護回路の据付・調整試験を遂行するにあたって、欧州側との事前の密な交渉の結果として合意し、構築・実施した作業管理や安全管理の取組み、およびそれらをもとに完遂した欧州作業についてまとめたものである。これらの取組みの結果、欧州作業員によるクエンチ保護回路の現地据付調整作業を無事故で完遂させることができ、日欧双方にとって非常に大きな成果となった。

論文

Reference design of the power supply system for the resistive-wall-mode control in JT-60SA

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:2 パーセンタイル:66.76(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.

論文

First switching network unit for the JT-60SA superconducting central solenoid

Lampasi, A.*; Zito, P.*; Coletti, A.*; Novello, L.*; 松川 誠; 島田 勝弘; Burini, F.*; Kuate-Fone, Y.*; Taddia, G.*; Tenconi, S.*

Fusion Engineering and Design, 98-99, p.1098 - 1102, 2015/10

 被引用回数:7 パーセンタイル:22.72(Nuclear Science & Technology)

In JT-60SA, the first SNU (prototype), consisting of six cubicles, was assembled in 2013. The factory tests on this system, including tests at full current and voltage, are being performed throughout 2014. The manufacturing of the remaining three SNUs will proceed after the success of such tests. The main characteristics of the developed SNU are; (1) Snchronized use of an electronic static circuit breaker (SCB) in parallel with an electromechanical bypass switch (BPS), (2) Nominal voltage of 5 kV, with a specific circuit to limit the transient voltage to 5.5 kV, (3) DC current interruption up to 20 kA, (4) Light BPS with opening and closing times shorter than 15 ms and 65 ms, respectively, (5) Breakdown resistance adaptable from 0.25 $$Omega$$ to 3.75 $$Omega$$ by four selectors, (7) Fully electronic making switch (MS) and (8) Breakdown resistors that could dissipate much more than 90 MJ.

論文

Design and realization of JT60-SA Fast Plasma Position Control Coils power supplies

Zito, P.*; Lampasi, A.*; Coletti, A.*; Novello, L.*; 松川 誠; 島田 勝弘; Cinarelli, D.*; Portesine, M.*; Dorronsoro, A.*; Vian, D.*

Fusion Engineering and Design, 98-99, p.1191 - 1196, 2015/10

 被引用回数:8 パーセンタイル:18.76(Nuclear Science & Technology)

In JT-60SA, Fast Plasma Position Control Coils Power Supplies (FPPCC PSs) control vertical position of the plasma during a plasma shot, against Vertical Displacements Event (VDE). For this task, the FPPCC PSs have to be as fast as possible and provide as much voltage as possible. Further, these will be open loop feed forward voltage controlled. The main characteristics are: 4-quadrant AC/DC converter 12-pulse with circulating current, DC load voltage $$pm$$ 1000 V and DC load current $$pm$$ 5 kA. The induced overvoltage in FPPC coil during a plasma disruption can reach 10 kV and it is bounded by a nonlinear resistor in parallel to the crowbar. All these technical characteristics have strongly influenced the design of the FPPC converter and of the FPPC transformers, that have been validated by simulation model of FPPCC PS. The outcomes of the simulation have allowed to finalize the performances and dynamic behavior of voltage response.

論文

Overview of the new magnet power supply systems of JT-60SA procured by EU

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:9 パーセンタイル:15.14(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 $$pm$$20 kA and about $$pm$$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 $$pm$$20 kA and $$pm$$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.

論文

Type tests of JT-60SA Fast Plasma Position Control Coil (FPPCC) power supplies

Zito, P.*; Lampasi, A.*; Novello, L.*; 松川 誠; 島田 勝弘; Portesine, M.*; Fasce, F.*; Cinarelli, D.*; Dorronsoro, A.*; Vian, D.*

Proceedings of IEEE 15th International Conference on Environment and Electrical Engineering (IEEE-EEEIC 2015), p.156 - 160, 2015/06

In JT-60SA, Fast Plasma Position Control Coils (FPPCC) PSs allow controlling the vertical position of the plasma during a plasma shot, against Vertical Displacements Event (VDE). An open loop feed forward voltage control is adopted in order to achieve a fast control of FPPCC PSs. The characteristics of the PS are: 4-quadrant AC/DC converter 12-pulse, DC load voltage $$pm$$1000 V and DC load current $$pm$$5 kA. The design of the FPPCC converters has been validated by a simulation model, finalizing the performances and dynamic behavior of voltage response. After the completion of the realization phase, the testing phase has been carried out in accordance to the IEC60146 Standards and this is the focus of the paper. The tests performed have pointed out a good dynamic behavior of the FPPCC converter in open loop feed forward voltage control, for a reference voltage step of 1kV, the rise time of output voltage is 2.88 ms, confirming outcomes achieved by simulations.

論文

Design and implementation of four 20 kA, 5 kV hybrid switching networks for plasma ignition in the international tokamak JT-60SA

Burini, F.*; Kuate-Fone, Y.*; Taddia, G.*; Tenconi, S.*; Lampasi, A.*; Zito, P.*; 松川 誠; 島田 勝弘; Coletti, A.*; Novello, L.*

Proceedings of 40th Annual Conference of the IEEE Industrial Electronics Society (IECON 2014), p.5035 - 5040, 2014/10

This paper describes the design and implementation of the Switching Network Unit (SNU) for the superconducting Central Solenoid coils of the international nuclear fusion experiment JT-60SA to be built in Naka, Japan. The SNU can interrupt a current up to 20 kA in less than 1 ms to create a voltage up to 5 kV. It is realized with a hybrid switch integrating an electro-mechanical device and a solid state Static Circuit Breaker, parallel connected. SNU resistance can be pre-arranged and dynamically reduced by a solid state making switch. Preliminary test results confirmed the current balance of the multiple parallel branches constituting the solid state switch and proper behavior of the devices, confirming simulations results. Further applications could be medium voltage DC networks (either naval or land based); higher DC voltages are practicable.

論文

A Conceptual design study for the error field correction coil power supply in JT-60SA

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:3 パーセンタイル:79.56(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。

論文

Minimization of reactive power fluctuation in JT-60SA magnet power supply

島田 勝弘; 寺門 恒久; 山内 邦仁; 松川 誠; Baulaigue, O.*; Coletti, R.*; Coletti, A.*; Novello, L.*

Plasma Science and Technology, 15(2), p.184 - 187, 2013/02

 パーセンタイル:100(Physics, Fluids & Plasmas)

In JT-60SA, the four thyristor converters in poloidal field coil (PFC) power supplies are used for plasma initiation. In this case, the large reactive power fluctuation induced by the "Booster PS" is the cause of large voltage fluctuation across the terminals of the motor-generator. To minimize the reactive power fluctuation during plasma initiation, an asymmetric control method and a sequential timing control to start/stop each "Booster PS" are foreseen. To evaluate the effectiveness of above control methods for the "Booster PS," the reactive power has been simulated by using "PSCAD/EMTDC" code. From the simulation it results that the reactive power induced by the four units of the "Booster PS" can be dramatically reduced. In addition, the voltage fluctuation of the motor-generator connected to the "Booster PS" is expected to be suppressed to less than 10%, which ensures the stable control of JT-60SA magnet power supplies.

論文

Detailed analysis of the transient voltage in a JT-60SA PF coil circuit

山内 邦仁; 島田 勝弘; 寺門 恒久; 松川 誠; Coletti, R.*; Lampasi, A.*; Gaio, E.*; Coletti, A.*; Novello, L.*

Plasma Science and Technology, 15(2), p.148 - 151, 2013/02

 被引用回数:5 パーセンタイル:66.51(Physics, Fluids & Plasmas)

One of the most essential issues for designing a power supply system of superconducting coil is to avoid any overvoltage. Here, the most concerned overvoltage can appear between turns due to the transiently concentrated voltage distribution inside the coil, which is mainly caused by parasitic capacitances and high dv/dt. For this reason, the coil power supply, especially fast high voltage generation circuit, should equip proper snubber(s) in order to suppress the dv/dt. However, it is too complicated to accurately evaluate the transient voltage in the coil because of the distributed parameters of the mutual inductance between turns and the capacitance between adjacent conductors. In this study, such a complicated system is modeled with reasonably detailed circuit network with lumped ones, and is integrated into the overall simulation model of JT-60SA PF coil circuit. Then a detailed circuit analysis is conducted in order to evaluate the possible voltage transient in the coil circuit. As a result, appropriate circuit parameters in the coil power supply including the snubbers are obtained.

論文

Resonance characteristics and maximum turn voltage of JT-60SA EF coil

村上 陽之; 木津 要; 土屋 勝彦; 吉田 清; 山内 邦仁; 島田 勝弘; 寺門 恒久; 松川 誠; 長谷川 満*; 湊 恒明*; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.9501405_1 - 9501405_5, 2012/06

 被引用回数:3 パーセンタイル:69.2(Engineering, Electrical & Electronic)

超伝導コイルの開発において、ターン間絶縁の耐電圧特性は重要な設計パラメータである。しかし実機コイルのターン間電圧は、電源の電圧変動やコイル内の共振現象により、理想的に電圧が分布した場合に比べ局所的にターン間電圧が高くなる危険性が指摘されている。そこで電源の電圧変動を評価するためJT-60SAと同等の大型電源であるJT-60Uの電源電圧測定を実施した。また、コイル内の共振現象を把握するため、EF4ダミーパンケーキを用いた共振特性試験及び数値解析によりEFコイルの共振特性を評価した。これらの結果、実際のターン間電圧は理想的な電圧分布から大きく外れないことが確認できた。

論文

Design study of an AC power supply system in JT-60SA

島田 勝弘; Baulaigue, O.*; Cara, P.*; Coletti, A.*; Coletti, R.*; 松川 誠; 寺門 恒久; 山内 邦仁

Fusion Engineering and Design, 86(6-8), p.1427 - 1431, 2011/10

 被引用回数:5 パーセンタイル:50.9(Nuclear Science & Technology)

In the initial research phase of JT-60SA, the plasma heating operation of 30MW-60s or 20MW-100s is planned for 5.5 MA single null divertor plasmas. To achieve this operation, AC power source of the medium voltage of 18 kV and $$sim$$7 GJ has to be provided in total to the poloidal field coil power supplies and additional heating devices such as Neutral Beam Injection (NBI) and Electron Cyclotron Radio Frequency (ECRF). In this paper, the proposed AC power supply system in JT-60SA was estimated from the view point of available power, and harmonic currents based on the standard plasma operation scenario during the initial research phase. This AC power supply system consists of the reused JT-60 power supply facilities including motor generators with flywheel, AC breakers, and harmonic filters, etc. to make it cost effective. In addition, the conceptual design of the upgraded AC power supply system for the ultimate heating power of 41MW-100s in the extended research phase is also described.

論文

JT-60SA power supply system

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:14 パーセンタイル:19.73(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.

論文

A Design study of stable coil current control method for back-to-back thyristor converter in JT-60SA

島田 勝弘; 寺門 恒久; 松川 誠; Cara, P.*; Baulaigue, O.*; Gaio, E.*; Coletti, R.*; Candela, G.*; Coletti, A.*

Journal of Plasma and Fusion Research SERIES, Vol.9, p.163 - 168, 2010/08

This paper describes the stable coil current control method of back-to-back thyristor converters as a design study. The back-to-back thyristor converter is applied to "Base PS" which is low-voltage power supply for PF coil in JT-60SA. This converter has six arms of anti-parallel connected thyristor devices to enable to operate with 4 quadrant operation. The dead beat control method is applied on the current feedback control algorithm. In addition, the non-interacting control method is adopted between coil current and circulating current among converters, which is necessary for smooth reversing of the coil current polarity. The rate limiter for control angles of thyristor converter is introduced to suppress the excessive current unbalance between converters. To estimate the proposed coil current control method, the real "Base PS" models are simulated by "PSCAD/EMTDC" code. From the simulation results, the stable control capability was obtained.

論文

Electric circuit analysis for plasma breakdown in JT-60SA

山内 邦仁; 島田 勝弘; 寺門 恒久; 松川 誠; Cara, P.*; Gaio, E.*; Santinelli, M.*; Coletti, R.*; Coletti, A.*

Journal of Plasma and Fusion Research SERIES, Vol.9, p.220 - 225, 2010/08

High current of about 500 kA will be induced in the passive structures such as vacuum vessel and stabilizing plate at plasma initiation in JT-60SA, because the total resistance of the passive structure is approximately 16 $$mu Omega$$ and the breakdown electric field of 0.5 V/m is expected for stable plasma initiation from the experiments of JT-60U. Therefore, a precise evaluation of the magnetic field performance using the accurate circuit analysis model has to be conducted to obtain stable plasma breakdown and for designing the detail of power supply system. In this paper, the preparation procedure of the analysis model will be presented. Then, some circuit analysis results of plasma breakdown will be given using ideal power supply and actual thyristor converter model for comparison. The delay effect of converter voltage control and the discrepancy of current control would be summarized as the first achievement. The voltage fluctuation of generator (H-MG, 400 MVA) at plasma initiation will be also described, because large reactive power fluctuation may cause large voltage fluctuation and sudden phase shift of the AC source voltage of thyristor converter.

論文

Optimization of plasma initiation scenarios in JT-60SA

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.

論文

Conceptual design of the quench protection circuits for the JT-60SA superconducting magnets

Gaio, E.*; Novello, L.*; Piovan, R.*; 島田 勝弘; 寺門 恒久; 栗原 研一; 松川 誠

Fusion Engineering and Design, 84(2-6), p.804 - 809, 2009/06

 被引用回数:13 パーセンタイル:26.02(Nuclear Science & Technology)

コイルクエンチ時に超電導コイルの蓄積エネルギーを高速に取り除かなければならないJT-60SAのクエンチ保護回路の概念設計について発表を行う。クエンチ保護回路の主要部は、高速にコイル消磁を行うためにコイル電流を抵抗に転流させる直流電流スイッチで構成される。本発表では、機械スイッチと半導体スイッチの一つであるIGCT(Integrated Gate Commutated Thyristor)の並列接続で構成されたハイブリッド型電流スイッチを提案し、検討した結果について述べる。また、クエンチ保護回路の主要部のほかに、電流スイッチで電流遮断失敗した場合のバックアップ回路として直列にパイロブレーカーを接続する。提案するハイブリッド型クエンチ保護回路は、半導体スイッチの特徴である高速遮断性能とメンテナンスフリーの利点と機械スイッチの特徴である低損失の利点の両方を併せ持つ回路構成となる。

論文

Status of JT-60SA tokamak under the EU-JA broader approach agreement

松川 誠; 菊池 満; 藤井 常幸; 藤田 隆明; 林 孝夫; 東島 智; 細金 延幸; 池田 佳隆; 井手 俊介; 石田 真一; et al.

Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12

 被引用回数:13 パーセンタイル:26.45(Nuclear Science & Technology)

JT-60SAは、日欧の幅広いアプローチの下で建設する完全超伝導トカマク装置で、ITERや原型炉への貢献を目指している。2007年の両極の国会批准後、実質的には既に建設段階に移行している。JT-60SAは、既存の建屋,電源,プラズマ加熱装置,計測装置などの、JT-60U設備の最大限の有効利用が前提であり、完全に新作する主たる機器は本体装置のみである。最大プラズマは電流5.5MAで、プラズマ主半径3.06m,アスペクト比2.65,非円形度1.76,三確度0.36である。最大プラズマ加熱入力41MW,プラズマ電流のフラットトップ時間は100秒間である。本論文では、トカマク装置本体だけでなく、プラズマ加熱装置や遠隔保守装置の設計などについても言及するとともに、EUとの技術的な議論を踏まえて行った超伝導導体に関する最近の設計変更案などを紹介し、装置の全体像を明らかにする。

報告書

JT-60SAにおける直流電源系の初期設計検討

島田 勝弘; 大森 栄和; 岡野 潤; 松川 達哉; 寺門 恒久; 栗原 研一

JAEA-Technology 2008-031, 38 Pages, 2008/03

JAEA-Technology-2008-031.pdf:10.84MB

臨界プラズマ試験装置JT-60の次期装置としてJT-60SA(Super Advanced)の設計検討が進められている。JT-60SAでは、トロイダル磁場コイル(TFコイル),ポロイダル磁場コイル(PFコイル)が超伝導化され、100s以上のフラットトップを持つ長時間プラズマ運転が可能となる。このようなプラズマ運転,コイルの超伝導化に対応するために新しい直流系電源システムの構築を行う必要がある。これらの超伝導コイルに直流電力を供給する電源は、既存のJT-60電源を有効に再利用した電源機器と新規製作による電源機器を組合せた構成とし、コストの低減を図った。また、超伝導コイルを用いるため、コイルクエンチ時にコイル蓄積エネルギーを急速に消費させるクエンチ保護回路を新規に導入した。本報告書では、JT-60SAの直流系電源(TFコイル電源,PFコイル電源)の回路構成やそれらの制御手法の検討結果及びPSCAD/EMTDCを用いた設計した電源システムでの初期電源制御シミュレーション結果について報告する。

報告書

JT-60SAにおける加熱装置のための交流電源系の設計検討

島田 勝弘; 寺門 恒久; 栗原 研一

JAEA-Technology 2008-022, 24 Pages, 2008/03

JAEA-Technology-2008-022.pdf:8.01MB

臨界プラズマ試験装置JT-60の次期装置としてJT-60SA(Super Advanced)の設計検討が進められている。JT-60SAでは、NBI装置,RF装置で構成される加熱装置の加熱時間が大幅に延伸される。既存の給電システムである電動発電機のエネルギーだけでは不足となるため、系統から直接受電する新しい給電システムを構築する必要がある。本報告書では、増力される加熱装置への給電を商用系統から直接行う新しい交流電源系の提案を示し、加熱装置で系統直接受電する場合に問題となる那珂核融合研究所の受電条件を満たすために、電源解析シミュレーションの一つである「PSCAD/EMTDC」を用いた高調波フィルタ及び力率改善コンデンサ等の無効電力補償装置の設計検討について報告する。

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