应用于等离子体破裂防护的双涡流驱动快速充气阀的研制
Novel Type of Fast Gas-Filling Valve for Disruption Mitigation in Experimental Advanced Superconducting Tokamak
查看参考文献13篇
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文摘
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为了满足在EAST装置上开展高压气体注入缓解等离子体破裂实验研究需求,在单涡流驱动快速充气阀成功研制的基础上又研制成功了双涡流驱动快速充气阀。该快速充气阀由双涡流线圈驱动,且增加了一套可调节阀芯预紧力的弹簧预紧背压系统,双线圈驱动结构的采用使得阀体的体积更加小巧,同时阀体的开启性能更加优越;弹簧背压预紧系统使用,使得充气阀的工作安全性大为提高。经过平台测定,该充气阀的开启响应时间不大于0.15 ms,而通过选择合适的工作参数可以使快阀的整个开启脉冲周期控制在2 ms以内;而通过调节工作参数(气压和电压),充气阀在2 ms内的充气总量可以很方便的在0?10~(23)粒子数之间调节。该阀的成功研制为EAST装置开展等离子体破裂缓解研究提供了更加有效的杂质气体注入工具,该阀将应用于2014年秋季的EAST物理实验研究。 |
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其他语种文摘
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A novel type of fast gas-filling valve has been successfully developed to meet the stringent requirements on disruption mitigation,a sub-project of Experimental Advanced Superconducting Tokamak(EAST).The original work includes the two parallel flat-coils to generate the double eddy-current and to significantly reduce the size of the valve ; and a set of compression springs for pre-tightening the valve' s core and for improving safety and sealing. The prototyped valve was evaluated and calibrated in the lab-built test-platform. The test results show that the newly-developed valve displayed excellent performance.To be specific,the valve can be opened for less than 0.15 ms, the opening cycle can be shortened to below 2 ms,and the number of injected particles can be easily controlled within 10~(23) range by optimizing the operation voltage and pressure. We suggest that the novel fast gas-filling valve may be of much technological interest for the future large-sized Tokamak, including but not limited to EAST and International Thermonuclear Experimental Reactor, when it comes to filling of impurities. |
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来源
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真空科学与技术学报
,2015,35(6):657-661 【扩展库】
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DOI
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10.13922/j.cnki.cjovst.2015.06.04
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关键词
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等离子体破裂缓解
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双涡流驱动
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快速充气阀
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预紧系统
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EAST
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地址
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中科院等离子体物理研究所, 合肥, 230031
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语种
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中文 |
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文献类型
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研究性论文 |
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ISSN
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1672-7126 |
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学科
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原子能技术 |
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基金
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国家自然科学基金资助项目
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文献收藏号
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CSCD:5451367
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参考文献 共
13
共1页
|
|
1.
朱士尧.
核聚变原理,1992:22
|
被引
4
次
|
|
|
|
|
2.
ITER Physics Expert Group. ITER Physics Basis.
Nuclear Fusion,1999,39(12):2137
|
被引
8
次
|
|
|
|
|
3.
Bakhtiari M. Fast Plasma Shutdown Scenarios in the JT-60U Tokamak Using Intense Mixed Gas Puffing.
Nuclear Fusion,2002,42(10):1197
|
被引
8
次
|
|
|
|
|
4.
Parks P B. Avalanche Runaway Growth Rate from a Momentum-Space Orbit Analysis.
Phys Plasmas,1999,6(6):2523
|
被引
5
次
|
|
|
|
|
5.
Granetz R. Gas Jetdisruption Mitigation Studies on Alcator C-Mod.
Nucl Fusion,2006(46):1001
|
被引
1
次
|
|
|
|
|
6.
Wan Yuanxi. Overview of Steady state Operation of HT-7 and Present Status of the HT-7U Project.
Nuclear Fusion,2000,40(6):1057
|
被引
60
次
|
|
|
|
|
7.
唐明. HT-7托卡马克中破裂等离子体放电对器壁放气的影响.
真空科学与技术学报,2011,31(1):32
|
被引
3
次
|
|
|
|
|
8.
Savtchkov A. Development of a Fast Valve for Mitigating Disruptions in Tokamaks.
Review of Scientic Instruments,2002,73(10):3490
|
被引
5
次
|
|
|
|
|
9.
Zhuang H D. Development of a Fast Valve for Disruption Mitigation and its Preliminary Application to EAST and HT-7.
Plasma Sci Technol,2013,15(8):745
|
被引
4
次
|
|
|
|
|
10.
胡建生. HT-7超导托卡马克装置真空系统参数的标定及分析.
真空科学与技术学报,2004,24(2):149
|
被引
5
次
|
|
|
|
|
11.
庄会东. 高压气体注入缓解等离子体破裂实验研究.
原子能科学技术,2013,47(9):1492
|
被引
1
次
|
|
|
|
|
12.
庄会东. 等离子体破裂防护快速充气阀性能研究.
真空科学与技术学报,2013,33(2):181
|
被引
2
次
|
|
|
|
|
13.
Zhang Y. Prediction of Disruptions on ASDEX Upgrade Using Discriminant Analysis.
Nuclear Fusion,2011,51(6):063039
|
被引
2
次
|
|
|
|
|
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