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The Alignment and Assembly for EAST Tokamak Device 被引量:2

The Alignment and Assembly for EAST Tokamak Device
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摘要 EAST (HT-7U) is a large fusion experimental device. It is a full superconducting tokamak with 1 MA of plasma current, 1000 s of plasma duration, high elongation and triangularity. It mainly consists of superconducting magnets of poloidal and toroidal field (PF & TF), vacuum vessel (VV), thermal radiation shield (TRS) and cryostat vessel (CV). The significant difficulty for assembly of EAST is tight installation tolerances, which are in the order of several tenth of a millimeter. In particular, the alignment of plasma facing components to the magnetic axis of the device is less than ±0.5 mm. At present, a reasonable assembly process of EAST has been defined, and based on it, the alignment method for EAST, including the survey control network, the location of the main components in different directions, the magnetic axis determination and the accurate positioning of the plasma facing components inside of the vacuum vessel and so on, has been defined by using the sophisticated optical metrology system (SOMS). This paper describes the assembly procedure of EAST and the installation tolerances associated with the main components. Meanwhile, how to establish the assembly survey control network, magnetic axis determination methods, are introduced in detail. EAST (HT-7U) is a large fusion experimental device. It is a full superconducting tokamak with 1 MA of plasma current, 1000 s of plasma duration, high elongation and triangularity. It mainly consists of superconducting magnets of poloidal and toroidal field (PF & TF), vacuum vessel (VV), thermal radiation shield (TRS) and cryostat vessel (CV). The significant difficulty for assembly of EAST is tight installation tolerances, which are in the order of several tenth of a millimeter. In particular, the alignment of plasma facing components to the magnetic axis of the device is less than ±0.5 mm. At present, a reasonable assembly process of EAST has been defined, and based on it, the alignment method for EAST, including the survey control network, the location of the main components in different directions, the magnetic axis determination and the accurate positioning of the plasma facing components inside of the vacuum vessel and so on, has been defined by using the sophisticated optical metrology system (SOMS). This paper describes the assembly procedure of EAST and the installation tolerances associated with the main components. Meanwhile, how to establish the assembly survey control network, magnetic axis determination methods, are introduced in detail.
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2005年第5期3017-3020,共4页 等离子体科学和技术(英文版)
基金 The project supported by National Meg-science Engineering Project of the Chinese Government
关键词 ALIGNMENT ASSEMBLY EAST TOKAMAK alignment, assembly, EAST, tokamak
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参考文献4

  • 1Wu S T. Fusion Engineering and Design 2001, 58~59:833~837
  • 2Saxena Y C, SST-1 team. Nuclear Fusion, 2000, 40(6):1069
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  • 4Doshi Bharat, Thomas K J, Das Subrat, et al. Assembly Integration and Dimensional Control of the Steady State Tokamak SST-1. 22st Symposium on Fusion Technology, San Diego, USA, April, 2002

同被引文献11

  • 1刘常乐,武松涛,郁杰.基于模块化设计的ITER真空室中子屏蔽结构组件数字化[J].机械设计与制造,2008(2):49-51. 被引量:2
  • 2Yao D M,Song Y T,Wu S T,et al.HT-7U vacuum vessel,Fusion Engineering and Design[J].2003,69(1/4):355-359
  • 3Song Yuntao,Yao Damao,Wu Songtao,et al.Structure analysis and experiment research of the welded bellows for the ports of the HT-7U vacuum vessel,Fusion Engineering,2002.19th Symposium on,19th Symposium on Fusion Engineering(SOFE);Atlantic City,United States,ISBN 0-7803-7073-2:376-379
  • 4刘常乐.ITER真空室中子屏蔽的结构设计与分析研究[D].安徽:中国科学院等离子体物理研究所博士论文.2006.6:13-16.
  • 5Spears W. Design description document 1.5 Vacuum vessel[R]. ITER G 15 DDD 4 01-06-25 RO.1, 2001, 35.
  • 6ASME Boiler and Pressure Vessel Code, SectionIII, ARTICLE D1 NC_3000[S]. 2001.
  • 7Ioki K, Sannazzaro G. Vacuum vessel design criteria in ITER. Meeting on Codes and Standards[R]. ITER International Team, Garching, Germany: 17-18, 2004.
  • 8American Society of Mechanical Engineers, Boiler and Pressure Vessel Committee. ASME boiler and pressure vessel code section III, rules for construction of nuclear vessels[S]. New York: American Society of Mechanical Engineers, 1963.
  • 9陈晨,宋云涛,王传礼,王忠伟,陆坤.ITER线圈终端盒真空隔断的结构设计与分析[J].真空科学与技术学报,2010,30(5):557-560. 被引量:8
  • 10CAO Hongrui,LI Shiping,XU Xiufeng,TANG Shibiao,YANG Jinwei,YANG Qingwei,YIN Zejie.An automatic gain adjustment Campbell integrator for neutron flux detection in ITER[J].Nuclear Science and Techniques,2012,23(2):114-117. 被引量:2

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