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EAST4．6GHz／4MW低杂波电流驱动系统隔直器优化设计

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核电子学与探测技术 2009年第6期29卷 1405-1408页

作者：赵连敏贾华徐旵东刘甫坤单家方王茂刘亮王晓洁张长虹李军低杂波电流驱动小组中国科学院等离子体物理研究所安徽合肥230031

为了研究全超导托卡马克稳态高参数等离子体性能，2008年在EAST托卡马克装置上研制并成功建成了一套能最大传输2兆瓦，工作频率是2450MHz的低混杂波电流驱动系统，要实现低杂波长时间地维持等离子体电流，还需要对低杂波系统的输出功率... 详细信息

为了研究全超导托卡马克稳态高参数等离子体性能，2008年在EAST托卡马克装置上研制并成功建成了一套能最大传输2兆瓦，工作频率是2450MHz的低混杂波电流驱动系统，要实现低杂波长时间地维持等离子体电流，还需要对低杂波系统的输出功率大小及运行时间长度提出更高要求，拟研制一套波源输出功率4MW，中心频率4．6GHz，波谱范围为1.7〈N〈2．5，运行脉冲宽度0～1000秒低杂波电流驱动系统。在EAST4．6GHz／4MW低杂波电流驱动系统中，因为速调管放大器和低杂波天线有共同的接地点，速调管放大器电源为负高压，有接地点，低杂波天线有接地点，并且和EAST托卡马克相连，在系统中要求不能有两个接地点，所以要通过隔直器来隔断托卡马克和速调管之间的的直流通路。论文详细介绍了隔直器的原理和设计过程，在以4．6GHz为中心频率，150MHz的频带范围内，隔直器各个端口微波性能良好。

关键词：低杂波电流驱动系统EAST托卡马克扼流法兰径向传输线驻波

lhcd Properties with a New Lower Hybrid Wave Antenna on HT-7 Tokamak

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Plasma Science and Technology 2005年第5期7卷 3005-3008页

作者：韦维匡光力丁伯江沈慰慈 HT-7 team Institute of Plasma Physics Chinese Academy of Sciences

The structure and the characteristic power spectrum of a new lower hybrid wave antenna on the HT-7 tokamak are briefly described in this paper. The main experimental properties with the new antenna have been demonstrated by showing the dependence of current drive efficiency and particle confinement time on phase difference between adjacent waveguides of the antenna. A few preliminary analyses about the experimental results are also discussed in the paper.

关键词： ower hybrid current drive (lhcd) lower hybrid wave (LHW) antenna tokamak

Recent Experimental Progress in the HT-7 Tokamak

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Plasma Science and Technology 2003年第3期5卷 1765-1766页

作者：万宝年 HT-7 team Institute of Plasma Physics Chinese Academy of SciencesHefei 230031China

Recent experimental campaign in the HT-7 toka-mak was scheduled to be ran from November 2002 toMarch 31, 2003, during which various issues were in-vestigated on getting high electron temperature, longpulse discharges and high performance plasma underquasi-steady-state condition. New systems includ-ing lhcd launcher, cryogenic compressor, real-timepoloidal control, water-cooled toroidal belt limiter,ferretic liner and several diagnostics were installedand operated to satisfy long-pulse operation require-ments. The maximum total injected power was over1 MW and the longest discharge duration was nearto 64 s.

关键词： lhcd of by In Recent Experimental Progress in the HT-7 Tokamak in were been HT

Feedback Control System for Antenna Phase Difference in the lhcd Experiments

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Plasma Science and Technology 2005年第6期7卷 3107-3110页

作者：蒋敏匡光力单家芳林建安孔军 HT-7 team Institute of Plasma Physics Chinese Academy of SciencesHefei 230031 China Southern Yangtze University Wuxi 214122 China Institute of Plasma Physics Chinese Academy of SciencesHefei 230031 China Southern Yangtze University Wuxi 214122 China

It is well accepted that lower hybrid current drive （lhcd） is the most efficient method for non-inductive current drive in fusion devices and the effect of the current drive is dependent on not only microwave power but also its grill phase shift. This paper presents a new kind of feedback control system for antenna phase difference in lhcd experiments. In this highspeed control system, a lot of new technologies and methods are incorporated. The results of the experiments show a very good agreement with the system design.

关键词： lower hybrid current drive (lhcd) feedback control system antenna phase difference

High Bootstrap Current Fraction during the Synergy of lhcd and IBW on the HT-7 Tokamak

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Chinese Physics Letters 2005年第6期22卷 1468-1470页

作者：张先梅万宝年吴振伟 HT-7team DepartmentofPhysics EastChinaUniversityofScienceandTechnologyShanghai200237//InstituteofPlasmaPhysicsChineseacademyofSciencesPOBox1126Hefei230031 InstituteofPlasmaPhysics ChineseacademyofSciencesPOBox1126Hefei230031 不详

More than 70% of the total plasma current is sustained by the bootstrapcurrent and current drive during the synergy of lower hybrid current driving (lhcd) and ion Bersteinwave (IBW) heating on the HT-7 tokamak. The lower hybrid non-inductive current source is off-axisand well localized, and more than 35% bootstrap current plasma has been obtained. The IBW incontrolling electron pressure profile can be integrated into the lhcd target plasma. The largeststeep gradient of the electron pressure profile in the region rho similar to 0.5-0.7 mostly comesfrom the electron temperature profile, which may induce the large fraction bootstrap current. Thelarge off-axis bootstrap current can help to create negative magnetic shear, and the good plasmaconfinement is achieved.

关键词： STEADY-STATE OPERATION PERFORMANCE PLASMAS

Study of Divertor Heat Patterns Induced by lhcd L-Mode Plasmas Using an Infra-Red Camera System on EAST

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Plasma Science and Technology 2015年第10期17卷 831-836页

作者：张斌甘开福龚先祖张晓东王福敏仰振东陈美文王晓琼 EAST team Institute of Plasma Physics Chinese Academy of Sciences

Divertor heat patterns induced by Lower Hybrid Current Drive （lhcd） L-mode plasmas are investigated using an infra-red （IR） camera system on an Experimental Advanced Superconducting Tokamak （EAST）. A two-dimensional finite element analysis code DFlux is used to compute heat flux along the poloidal divertor target and corresponding quantities. Outside the Origin Strike Zone （OSZ）, a Second Peak Heat Flux （SPHF） zone, where the heat flux is even stronger than that at the OSZ, appears on the lower-outer （LO） divertor plates with lhcd and disappears immediately after switching off the lhcd. The main heat-flux shifts from the SPHF zone towards the OSZ when the divertor configuration converts from double null to lower single null, indicating that the growth of the SPHF zone is apparently affected by a plasma magnetic configuration. The heat patterns on the LO divertor plates are observed to be different from that on the lower-inner （LI） targets as the SPHF zone appears only on the LO divertor target. It is also found that the heat flux at the SPHF zone was obviously enhanced after the Supersonic Molecule Beam Injection （SMBI） pulse.

关键词： lhcd IR camera SPHF zone SMBI

Heat transport analysis of the improved confinement discharge with LHW in the HT-7 tokamak

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Heat transport analysis of the improved confinement discharg...

Toroidal rotation induced by 4.6 GHz lower hybrid current drive on EAST tokamak

第十四届全国等离子体科学技术会议暨第五届中国电推进技术学术研讨会

作者： the HT-7 team

In the HT-7 tokamak,heat transport analysis is carried out for the lower hybrid current drive (lhcd) *** and ions are coupled and good confinement can be obtained by properly optimizating lhcd and plasma *** the conditions that the plasma current is about 220kA,the lower hybrid wave(LHW) power is about 300 kW and the central line-averaged density is about 1.5×10 cm,lower hybrid wave power deposition is off-axis. Local transport analysis illustrated that both electron and ion thermal diffusivities are decreased during the LHW phase,and the electron internal transport barriers(eITBs) are formed while been accompanied by the ion internal transport barriers(iITBs) during LHW *** are heated by electron-ion collision in the region of the barriers although the ohmic power and the LHW power were absorbed by the *** electron temperature and ion temperature are increased during the LHW phase,and in the confinement region,the electron-to-ion temperature ratio,T/T varies from 2.0～2.5 during OH phase to 1.3～1.6 during LHW injected into the plasma,which shows that electron confinement is not degraded by the electron-ion collisions meanwhile ions are also *** energy confinement is increased from 13ms to 25ms due to the formation of electron and ion internal transport barries after the LHW is injected into the *** driven current and bootstrap current contribute to 60%of the total current.

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Chinese Physics B 2017年第11期26卷 350-354页

作者：尹相辉陈俊胡睿佶李颖颖王福地符佳丁伯江王茂刘甫坤臧庆石跃江吕波万宝年 EAST team Institute of Plasma Physics Chinese Academy of Sciences Hefei 230031 China School of Nuclear Science and Technology University of Science and Technology of China Hefei 230026 China Department of Nuclear Engineering Seoul National University Seoul 151-742 Korea

Using a tangentially viewing x-ray imaging crystal spectrometer, substantial co-current rotation driven by lower hybrid current drive（lhcd） at 4.6 GHz is observed on EAST tokamak. This study presents plasma rotation behaviors with 4.6 GHz lhcd injection. Typically, the 10-20 km/s co-current rotation change and the transport of rotation velocity from edge to core are observed. The relationship between plasma parameters and rotation is also investigated, indicating that rotation decreases with increasing internal inductance（li） and increases with increasing safety factor（q0）. Hysteresis between rotation and Te plasma stored energy is observed, suggesting different response times between the electron heating and rotation acceleration by lhcd. A comparison between the rotations driven by 4.6 G lhcd and 2.45 G lhcd on EAST is also presented, in which higher frequency lhcd could induce more rotation changes.

关键词： intrinsic rotation lower hybrid current drive(lhcd)

Recent HL-1M Experiment Progress

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中国核科技报告 1999年第S3期 11-16页

作者： WANG Enyao (HL-1M team)

In 1993 and 1994, HL-1 was modified to HL-1M by replacing the vacuum chamber. HL-1M is a circular cross-section Tokamak with R=1.02 m, α=0.26 m. The goal of the HL-1M programme is to conduct high power auxiliary heating (NBI power of～1 MW, ICRH power of～1 MW, ECRH power of 0.5 MW) and current drive (lhcd power of>1 MW) experiments in order to develop the physics and technology basis for the next Tokamak, HL-2A, which is a modifica

关键词： Plasma performance lhcd NBI