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First experimental results of intrinsic torque on EAST

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Plasma Science and Technology 2020年第6期22卷 91-95页

作者： Xunyu wanG Bo LYU Xingqiang LU Yingying LI W M SOLOMON Baolong HAO Jun CHEN Fudi wanG Jia FU Hongming ZHANG Jin YANG Bin BIN Liang HE Yichao LI shunkuan wan Xueyu GONG Baonian wan Minyou YE School of Nuclear Science and Technology University of South ChinaHengyang 421001People's Republic of China Institute of Plasma Physics Chinese Academy of SciencesHefei 230031People's Republic of China General Atomics San DiegoCA92186-5608United States of America Department of Engineering and Applied Physics University of Science and Technology of ChinaHefei 230026People's Republic of China

Direct measurements of the intrinsic torque profile in L-mode plasmas on the EAST tokamak have been performed using the balanced neutral beam ***-and counter-current neutral beams are modulated to balance the intrinsic and externally injected torques, which result in the rotation profile close to zero and *** experimental results show that the intrinsic torque derived from momentum balance equations is found to be in the co-current direction, peaked in the plasma edge and negligibly small in the core.

关键词： intrinsic torque balanced injection momentum transport

Space-resolved vacuum-ultraviolet spectroscopy for measuring impurity emission from divertor region of EAST tokamak

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Plasma Science and Technology 2022年第6期24卷 14-22页

作者： Liang HE Yongcai SHEN Hongming ZHANG Bo LYU Cheonho BAE Huajian JI Chaoyang LI Jia FU Xuewei DU Fudi wanG Qiuping wanG Xianghui YIN shunkuan wan Bin BIN Yichao LI Shuyu DAI Institute of Plasma Physics HFIPSChinese Academy of SciencesHefei 230031People's Republic of China University of Science and Technology of China Hefei 230026People's Republic of China School of Physics and Materials Engineering Hefei Normal UniversityHefei 230601People's Republic of China Institute of Energy Comprehensive National Science CenterHefei 230026People's Republic of China School of Electrical Engineering University of South of ChinaHengyang 420001People's Republic of China Anhui Spectreation Instrument Co.Ltd Hefei 230088People's Republic of China National Synchrotron Radiation Laboratory University of Science and Technology of ChinaHefei 230029People's Republic of China School of Physics Dalian University of TechnologyDalian 116024People's Republic of China

The measurement of impurity distribution in the divertor region of tokamaks is key to studying edge impurity ***,a space-resolved vacuum-ultraviolet(VUV)spectrometer is designed to measure impurity emission in the divertor region on *** good spectral resolution,an eagle-type VUV spectrometer with 1 m long focal length with spherical holograph grating is used in the *** light collection,a collimating mirror is installed between the EAST plasma and the VUV spectrometer to extend the observing range to cover the upper divertor *** types of detectors,i.e.a back-illuminated charge-coupled device detector and a photomultiplier-tube detector,are adopted for the spectral measurement and high-frequency intensity measurement for feedback control,*** angle between the entrance and exit optical axis is fixed at 15°.The detector can be moved along the exit axis to maintain a good focusing position when the wavelength is scanned by rotating the *** profile of impurity emissions is projected through the space-resolved slit,which is set *** spectrometer is equipped with two gratings with 2400 grooves/mm and2160 grooves/mm,*** overall aberration of the system is reduced by accurate detector *** a result,the total spectral broadening can be reduced to about 0.013 *** simulated performance of the system is found to satisfy the requirement of measurement of impurity emissions from the divertor area of the EAST tokamak.

关键词： impurity measurement vacuum-ultraviolet spectrometer EAST divertor

EAST辐射偏滤器运行模式下等离子体杂质浓度评估方法

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核技术 2022年第3期45卷 59-66页

作者：计华健张洪明杨秀达尹相辉李克栋何梁符佳王福地沈永才万顺宽吕波龚学余龚先祖臧庆王嵎民林新王守信南华大学电气工程学院衡阳421001 中国科学院合肥物质研究院等离子体物理研究所合肥230031 合肥师范学院物理与材料工程学院合肥230070 合肥综合性国家科学中心能源研究院合肥230031 中国科学技术大学研究生院科学岛分院合肥230031

通过在偏滤器区域充入适量氖气(Ne)或氩气(Ar),东方超环(Experimental Advanced Super-conducting Tokamak,EAST)托卡马克装置实现了辐射偏滤器运行模式。在辐射偏滤器运行模式下,靶板热负荷显著降低,有效缓解了高能粒子流对偏滤器靶板... 详细信息

通过在偏滤器区域充入适量氖气(Ne)或氩气(Ar),东方超环(Experimental Advanced Super-conducting Tokamak,EAST)托卡马克装置实现了辐射偏滤器运行模式。在辐射偏滤器运行模式下,靶板热负荷显著降低,有效缓解了高能粒子流对偏滤器靶板的损伤。但是在偏滤器区域充入过量杂质气体时,杂质粒子会沿着磁力线进入主等离子体,影响主等离子体的约束性能,甚至导致等离子体破裂。因此,有必要研究偏滤器区域等离子体杂质浓度的估算方法,分析充入杂质气体时该区域杂质的定量变化,以此来评估充入的杂质气体对芯部等离子体约束性能的影响。本文针对不同的杂质种类,建立了不同的杂质浓度估算方法。对于钨杂质,通过极紫外光谱(Extreme Ultraviolet Spectroscopy,EUV)诊断系统测量偏滤器区域钨杂质的辐射强度,再根据碰撞-辐射模型对该区域的钨杂质浓度进行了估算。对于Ne杂质,则通过等离子体有效电荷数(Z_(eff))的变化进行了Ne杂质浓度估算。基于估算结果,对辐射偏滤器条件下的芯部杂质行为进行了讨论。上述杂质浓度评估方法对开展辐射偏滤器条件下等离子体约束性能研究,优化辐射偏滤器运行参数有重要意义。

关键词：杂质浓度杂质输运脱靶运行极紫外光谱仪有效电荷数