Design and analysis of Switching Network Units for the ITER coil power supply system

Roshal, A.; Avanesov, S.; Koktsinskaya, E.; Manzuk, M. V.; Milani, F.; Mustafa, Ghullam; Nesterenko, O. N.; Song, Inho; Филиппов, А. А.; Frolov, A.

doi:10.1016/j.fusengdes.2011.01.032

Cited by 21 publications

(7 citation statements)

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“…Each FDU is interleaved with a pair of TF coils to limit the coil terminal voltage to ground [49,50]. The temperature dependent resistors are used for the quench protection to reduce the maximum terminal voltage and the electromagnetic force in the vacuum vessel results from the induced eddy current during the fast discharge [23,[50][51][52][53][54]. The equivalent thermal discharge time constant of the CFETR TF coil is about 10.6 s. According to the classical adiabatic hot spot temperature criterion of 250 K, the maximum quench detection and action time of the CFETR TF coil is about 2.3 s.…”

Section: Quench Analysis Of the Cfetr Tf Coilsmentioning

confidence: 99%

Electromagnetic, mechanical and thermal performance analysis of the CFETR magnet system

et al. 2015

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The Chinese Fusion Engineering Test Reactor (CFETR) superconducting magnet system was designed by the National Integration Design Group for Magnetic Confinement Fusion Reactor. The CFETR magnet system consists mainly of a central solenoid (CS) coil with six modules, 16 toroidal field (TF) coils, 8 poloidal field (PF) coils, and a set of correction coils (CC). The electromagnetic stresses and stored magnetic energy are huge on the CFETR magnets since they experience both large current densities and high magnetic field. The electromagnetic, structural and thermal performance needs to be evaluated to ensure that the magnetic field, stress, and hot spot temperature of the magnet system are within the allowed criteria.The evaluation of the electromagnetic performance of the CFETR superconducting magnet system under normal operation and fault conditions was performed. The two-dimensional finite element method was adopted to analyse the stress/strain behaviour of the CFETR CS coils. In addition, the thermal-hydraulic behaviour on quench propagation performance of the CFETR CS and TF coils was analysed to evaluate the hot spot temperature of the cable and the helium pressure inside a jacket during a quench.

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Section: Quench Analysis Of the Cfetr Tf Coilsmentioning

confidence: 99%

Electromagnetic, mechanical and thermal performance analysis of the CFETR magnet system

et al. 2015

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“…Введение в контур электропитания обмотки КТМ дополнительного сопротивления достигается с использованием полупроводникового ключа-прерывателя на полный ток нагрузки 30 кА, отличающегося от известных ключей-прерывателей [10][11][12][13][14] схемотехническим решением, основанным на использовании однооперационных тиристоров SCR и силовых диодов без применения электромеханических байпасных схем. На рис.…”

Section: прерыватель постоянного тока 30 ка источника питания обмоткиunclassified

Electrotechnical Complex of Tokamak KTM Pulse Power Supply System

Zarva¹,

Deriglazov²,

Batyrbekov³

et al. 2018

PAST-TF

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Системы импульсного электропитания установок типа токамак относятся к основным технологическим системам и предназначаются для создания требуемых сценариев изменения токов в обмотках электромагнитной системы. От точности реализации данных сценариев напрямую зависят возможность получения плазменного пробоя и конечные параметры получаемой плазмы. Учитывая уникальность каждой из сооружаемых в мире установок, а также установленную мощность применяемого электротехнического оборудования при комплектации их источников питания, с уверенностью можно констатировать, что сооружение подобных энергетических комплексов и их систем управления, оптимизация их электротехнических параметров и дальнейшая безаварийная эксплуатация являются актуальными задачами на пути освоения технологий управляемого термоядерного синтеза. В данной работе описаны система импульсного электропитания казахстанского материаловедческого токамака КТМ, система цифрового управления её силовым преобразовательным оборудованием, электротехнические решения, принятые при разработке системы импульсного электропитания токамака КТМ, и результаты проведённых испытаний некоторого оборудования и комплектующих. Испытания показали достаточную эффективность принятых электротехнических решений и возможность их использования при реализации систем импульсного электропитания токамаков малой и средней мощности.Ключевые слова: токамак KTM, импульсное электропитание, полупроводниковые преобразователи, система управления и диагностики преобразовательного оборудования, сильноточные прерыватели постоянного тока, распределение токов по параллельно соединённым полупроводниковым приборам. ВВЕДЕНИЕТокамак КТМ, сооружаемый в г. Курчатове (Республика Казахстан) в настоящее время, -единственная в мире «мегаамперная» установка (ток плазмы I = 0,75 МА), предназначенная для испытания материалов и технологий в штатных и аварийных (режим срыва плазмы) условиях работы термоядерных

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“…The switch network unit (SNU) is connected in series with the SC. It is used to generate a high enough voltage required for breakdown and plasma initiation by inserting discharge resistors in series with the coil [3]. In CFETR, the SNU is rated for up to 80 kA/20 kV, and the voltage should be established within 12 ms.…”

Section: Introductionmentioning

confidence: 99%

“…1 The BPS usually is a mechanical switch, carries current in the steady state and transfers it to SSS. The SSS operates in the pulse mode and is capable of transferring the current to DR. To this end, the SSS can be composed of IGBT or integrated gate commutated thyristor (IGCT) or thyristor switch equipped with pre-charge oscillation zero point circuit, as reported in [3], [4], [7]. The DR is used to generate FIGURE 1.…”

Section: Introductionmentioning

confidence: 99%

“…In ITER, the SNU also adopts a hybrid switch scheme based on mechanical switch and thyristor. Unlike the scheme mentioned in JT-60SA, ITER SNU adopts an ingenious three-step commutation scheme to realize the quick transfer of current from mechanical switches to discharge resistors, with the high rated parameters (45 kA/10 kV) [3]. As for SNU of CFETR, its rated parameters are up to 80 kA/20 kV and the voltage must be established within 12 ms.…”

Section: Introductionmentioning

confidence: 99%

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Conceptual Design of Switch Network Unit for CFETR Coil Power Supply Systems

Qian

Song

et al. 2019

IEEE Access

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The China Fusion Engineering Test Reactor (CFETR) device is a milestone in the roadmap for the utilizing of fusion energy in China, whose final goal of plasma current is up to 10.02 MA. As the key system to generate a high enough voltage (20 kV) required for gas breakdown and plasma initiation, the Switch Network Unit (SNU) should have the ability to transfer 80 kA direct current by inserting resistor (0.25 ) to the superconducting coil circuit in 12 milliseconds. SNU topologies applied in other fusion devices are mostly based on the utilization of oscillation zero-point circuit, or combination of mechanical switch and semiconductor switch and so on, which bring stricter requirements for the components in the circuit and raise the cost due to the series and parallel connection of multiple devices if used in 80 kA/ 20 kV application. Based on the combination of solid-state switch (SSS) and auxiliary capacitor, this paper proposes a novel hybrid switch scheme. The SSS consists of insulated gate bipolar transistors (IGBT) group and thyristors group connected in series. The combination of added auxiliary capacitor and SSS can significantly reduce the number of series-connected IGBTs. This paper introduces the operation principle, design methods and simulation analysis of proposed scheme in detail. Coinciding with the analysis, the simulation results of SNU demonstrates the feasibility and reliability of the proposed scheme, which suggests its promising applications in fast switches with tens of kilovolts and hundreds of kilo-amperes.INDEX TERMS CFETR, switch network unit, hybrid switch, auxiliary capacitor.

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Design and analysis of Switching Network Units for the ITER coil power supply system

Cited by 21 publications

References 2 publications

Electromagnetic, mechanical and thermal performance analysis of the CFETR magnet system

Electromagnetic, mechanical and thermal performance analysis of the CFETR magnet system

Electrotechnical Complex of Tokamak KTM Pulse Power Supply System

Conceptual Design of Switch Network Unit for CFETR Coil Power Supply Systems

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