Design,Analysis and R&D of the EAST In-Vessel Components |
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引用本文: | 姚达毛,鲍立曼,李建刚,宋云涛,陈文革,杜世俊,胡庆生,卫靖,谢韩,刘旭峰,曹磊,周自波,陈俊凌,毛心桥,王声铭,祝宁,翁佩德,万元熙.Design,Analysis and R&D of the EAST In-Vessel Components[J].等离子体科学和技术,2008(3):367-372. |
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作者姓名: | 姚达毛 鲍立曼 李建刚 宋云涛 陈文革 杜世俊 胡庆生 卫靖 谢韩 刘旭峰 曹磊 周自波 陈俊凌 毛心桥 王声铭 祝宁 翁佩德 万元熙 |
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基金项目: | supported partly by JSPS-CAS Core-University Program on Basic Research of Nuclear Fusion Reactor Engineering in 2007
Acknowledgements The authors wish to thank all the EAST team members for cooperation during the extensive work. |
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摘 要: | In-vessel components are important parts of the EAST superconducting tokamak. They include the plasma facing components, passive plates, cryo-pumps, in-vessel coils, etc. The structural design, analysis and related R&D have been completed. The divertor is designed in an up-down symmetric configuration to accommodate both double null and single null plasma operation. Passive plates are used for plasma movement control. In-vessel coils are used for the active control of plasma vertical movements. Each cryo-pump can provide an approximately 45 m^3/s pumping rate at a pressure of 10^-1 Pa for particle exhaust. Analysis shows that, when a plasma current of 1 MA disrupts in 3 ms, the EM loads caused by the eddy current and the halo current in a vertical displacement event (VDE) will not generate an unacceptable stress on the divertor structure. The bolted divertor thermal structure with an active cooling system can sustain a load of 2 MW/m^2 up to a 60 s operation if the plasma facing surface temperature is limited to 1500 ℃. Thermal testing and structural optimization testing were conducted to demonstrate the analysis results.
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关 键 词: | 托卡马克 等离子体 导管 分析方法 |
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