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Minimization of Reactive Power Fluctuation in JT-60SA Magnet Power Supply
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作者 K. SHIMADA T. TERAKADO +5 位作者 K. YAMAUCHI M. MATSUKAWA O. BAULAIGUE R. COLETTI A. COLETTI L. NOVELLO 《Plasma Science and Technology》 SCIE EI CAS CSCD 2013年第2期184-187,共4页
This paper describes an asymmetric control method for the firing angle and a start/stop timing shift control of four thyristor converters called "Booster PS" to minimize the reactive power fluctuation during plasma ... This paper describes an asymmetric control method for the firing angle and a start/stop timing shift control of four thyristor converters called "Booster PS" to minimize the reactive power fluctuation during plasma initiation in JT-60SA. From the simulation using the "PSCAD/EMTDC" code, it is found that these control methods can drastically reduce the reac- tive power induced by the four units of the "Booster PS". In addition, the voltage fluctuation of the motor-generator connected to the "Booster PS" is expected to be suppressed. This can also contribute to achieve stable control of the JT-60SA magnet power supplies. 展开更多
关键词 jt-60sa power supply poroidal field coil reactive power fluctuation asym-metric control PSCAD/EMTDC
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Present Status of JT-60SA Project and Development of Heating Systems for JT-60SA
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作者 Yoshitaka IKEDA JT-60SA Team 《Plasma Science and Technology》 SCIE EI CAS CSCD 2011年第3期367-375,共9页
Present status of the JT-60SA (JT-60 Super Advanced) project, implemented jointly by Europe and Japan since 2007, is described. The design of the main tokamak components was completed in late 2008, and all the scien... Present status of the JT-60SA (JT-60 Super Advanced) project, implemented jointly by Europe and Japan since 2007, is described. The design of the main tokamak components was completed in late 2008, and all the scientific missions are preserved to contribute to ITER and DEMO reactors. The construction of the JT-60SA has begun with procurement activities for the superconducting magnet systems, vacuum vessel, in-vessel components and other components under the relevant procurement arrangements between the implementing agencies of JAEA (Japan Atomic Energy Agency) in Japan and Fusion for Energy in Europe. Designs and developments of the auxiliary heating systems for JT-60SA have been progressing at JAEA so as to provide the total injection power of 41 MW for 100 s. 展开更多
关键词 jt-60sa ITER DEMO JAEA heating systems
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Detailed Analysis of the Transient Voltage in a JT-60SA PF Coil Circuit
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作者 K. YAMAUCHI K. SHIMADA +6 位作者 T. TERAKADO M. MATSUKAWA R. COLETTI A. LAMPASI E. GAIO A. COLETTI L. NOVELLO 《Plasma Science and Technology》 SCIE EI CAS CSCD 2013年第2期148-151,共4页
A superconducting coil system is actually complicated by the distributed parameters, e.g. the distributed mutual inductance among turns and the distributed capacitance between adjacent conductors. In this paper, such ... A superconducting coil system is actually complicated by the distributed parameters, e.g. the distributed mutual inductance among turns and the distributed capacitance between adjacent conductors. In this paper, such a complicated system was modeled with a reasonably simplified circuit network with lumped parameters. Then, a detailed circuit analysis was conducted to evaluate the possible voltage transient in the coil circuit. As a result, an appropriate (minimum) snubber capacitance for the Switching Network Unit, which is a fast high voltage generation circuit in JT-60SA, was obtained. 展开更多
关键词 jt-60sa power supply transient voltage snubber PSIM
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Design Study of Top Lid with Clamp Structure in JT-60SA Cryostat
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作者 Shigetoshi NAKAMURA Yusuke K. SHIBAMA +1 位作者 Kei MASAKI Akira SAKASAI 《Plasma Science and Technology》 SCIE EI CAS CSCD 2013年第2期188-191,共4页
JT-60SA is a fully superconducting coil tokamak upgraded from the JT-60U. This paper focused on the integrity of the top lid of cryostat in JT-60SA. The design requirement for the cryostat in normal operations is to a... JT-60SA is a fully superconducting coil tokamak upgraded from the JT-60U. This paper focused on the integrity of the top lid of cryostat in JT-60SA. The design requirement for the cryostat in normal operations is to achieve vacuum insulation of 10-1 Pa, and the top flange of the top lid is lightly welded onto its body flange. The weld is tensile-loaded by bending deformation of the top lid due to vacuum pressure of external 0.1 MPa. This weld integrity is evaluated with tensile-load reduction, which results in clamp reinforcement. The structural integrity of the top lid is validated. 展开更多
关键词 CLAMP vacuum insulation top lid CRYOSTAT jt-60sa
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A Conceptual Design Study for the Error Field Correction Coil Power Supply in JT-60SA
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作者 M.MATSUKAWA K.SHIMADA +3 位作者 K.YAMAUCHI E.GAIO A.FERRO L.NOVELLO 《Plasma Science and Technology》 SCIE EI CAS CSCD 2013年第3期257-260,共4页
This paper describes a conceptual design study for the circuit configuration of the Error Field Correction Coil (EFCC) power supply (PS) to maximize the expected performance with reasonable cost in JT-60SA. The EF... This paper describes a conceptual design study for the circuit configuration of the Error Field Correction Coil (EFCC) power supply (PS) to maximize the expected performance with reasonable cost in JT-60SA. The EFCC consists of eighteen sector coils installed inside the vacuum vessel, six in the toroidal direction and three in the poloidal direction, each one rated for 30 kA-turn. As a result, star point connection is proposed for each group of six EFCC coils installed cyclically in the toroidal direction for decoupling with poloidal field coils. In addition~ a six phase inverter which is capable of controlling each phase current was chosen as PS topology to ensure higher flexibility of operation with reasonable cost. 展开更多
关键词 jt-60sa error field correction coil power supply inverter MULTI-PHASE
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超导托卡马克工程研究概况 被引量:2
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作者 丁逸骁 朱银锋 《低温与超导》 CAS CSCD 北大核心 2011年第8期36-41,共6页
首先简述了超导托卡马克的关键组成,接着归纳了在建的国际热核实验堆-ITER、日本的JT-60SA,以及中国和韩国先后建成并成功进行放电实验的EAST和KSTAR的研究现状,最后指出了超导托卡马克的发展趋势。
关键词 核聚变 托克马克 ITER jt-60sa EAST KSTAR
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