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Analysis of the Cooling Water Temperature Rise of Accelerating Electrodes in EAST Neutral Beam Injector Beam Extraction

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Chinese Physics Letters 2013年第3期30卷 44-46页

作者：许永建胡纯栋谢远来李军刘胜谢亚红于玲 nbi group Institute of Plasma Physics Chinese Academy of SciencesHefei 230031

Neutral beam injection is recognized as one of the most effective means of plasma *** preliminary data of beam power deposition in different electrodes during beam extraction are obtained on the EAST neutral beam injector test *** measurement of the cooling water temperature rise of accelerating electrodes is *** data given can guide the optimization of beam extraction parameters and decrease the damage to the accelerating electrodes following long pulse beam extraction.

关键词： injection damage neutral

Technical Design of Arc-Discharge and Deceleration Power Supply for MW Level nbi System on HL-2A Tokamak

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Plasma Science and Technology 2012年第10期14卷 936-940页

作者：陈文光饶军李波雷光玖曹建勇王明伟康自华冯鲲 HL-2A nbi group chool of Electrical Engineering University of South ChinaHengyang 421001China Southwestern Institute of Physics Chengdu 610041China

Neutral beam injection （nbi） is one of the most effective ways to heat and drive plasma in a tokamak. The mega watt level neutral beam injector on the HL-2A tokamak consists of four high-power ion sources. Each source is supplied by discharge, beam extraction and auxiliary power supplies. Some circuit topologies and control sequences designed for the system are presented in this paper. Some important technologies such as the notching circuit, insulated gate bipolar transistor （IGBT） series-connected switch, high-frequency switching power supply and control system based on a digital signal processor （DSP） have been used. The system can be effectively used for high current ion beam extraction, protection, ion optics and so on. The power system has been safely used in HL-2A high-parameter nbi experiments for three years. The power of nbi can be kept at higher than 0.75 MW for 1 second and the ion beam power extracted from the ion source is higher than 2 MW. The ion temperature of the plasma center is close to 2.0 keV. These results show that the design of this power system is reasonable and reliable, and it can fully meet the system requirements for nbi of the HL-2A tokamak.

关键词： HL-2A neutral beam injector neutral beam injection power supply controlsequence

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Effect of Ne Glow Discharge on Ion Density Control in LHD

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Plasma Science and Technology 2004年第5期6卷 2440-2444页

作者： S.Morita M.Goto S.Masuzak H.Suzuki K.Tanaka H.Nozato Y.Takeiri J.Miyazawa LHD experimental group National Institute for Fusion Science Toki 509-5292Gifu JapanNational Institute for Fusion Science Toki 509-5292Gifu JapanNational Institute for Fusion Science Toki 509-5292Gifu JapanCollege of EngineeringChubu UniversityKasugai 487-8501AichiJapanNational Institute for Fusion Science Toki 509-5292Gifu JapanScience and Technology Center for AtomsMolecules and Ions ControlsOsaka UniversitySuita 565-0871OsakaJapanNational Institute for Fusion Science Toki 509-5292Gifu JapanNational Institute for Fusion Science Toki 509-5292Gifu Japan

Neon glow discharge cleaning was firstly attempted in Large Helical Device(LHD) instead of He glow discharge to remove hydrogen neutrals and to control the ion density, n_*** Ne glow discharge continued for 8 hours overnight after a three-day experiment. At the secondnight H_α emission became weaker than the emission usually observed in the He glow discharge. Aclear reduction of the hydrogen influx was also observed in neutral beam injection (nbi) dischargeswith Ne puff, whereas the neon recycling was strongly enhanced with appearance of a flat densityprofile. As a result, the lowest density limit was further reduced down to 0.2 X 10^(13)cm^(-3). Theuse of Ar puff formed a peaked density profile with a high T_i of 7 keV.

关键词： hydrogen recycling Ne glow discharge ion density

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Excitation Experiments of Alfvén Eigenmodes by AC Current Flowing Along the Magnetic Field Line in CHS

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中国核科技报告 1999年第S4期 380-380页

作者： G.Matsunaga,M.Takechi,K.Toi,CHS group Department Energy Eng.Science Nagoya University 322-6 Oroshi-cho Toki-shi 509-5292 Department Energy Eng.Science Nagoya University 322-6 Oroshi-cho Toki-shi 509-5292 National Institute for Fusion Science National Institute for Fusion Science

Energetic particles such as alpha particles and fast ions could destabilize Alfv(?)n eigenmodes (AEs) in a fusion reactor. If these modes become unstable, the loss of particles is enhanced and consequently prevents ig... 详细信息

关键词： Excitation Experiments of Alfv n Eigenmodes by AC Current Flowing Along the Magnetic Field Line in CHS AC

HL-2A上nbi加热H模实验的集成模拟分析

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物理学报 2022年第7期71卷 241-249页

作者：罗一鸣王占辉陈佳乐吴雪科付彩龙何小雪刘亮杨曾辰李永高高金明杜华荣昆仑集成模拟设计组核工业西南物理研究院聚变科学技术所成都610041 中国科学院等离子体物理研究所合肥230031 西南交通大学物理科学与技术学院成都611756

托卡马克等离子体物理过程时空尺度跨度大,不同空间区域(如芯部、台基区、刮削层、靶板区)的主要物理过程不同,因此需要采用系统集成方法开展全域多时空尺度物理问题分析.为了更加深入地研究托卡马克等离子体放电实验的稳态运行及爬升... 详细信息

托卡马克等离子体物理过程时空尺度跨度大,不同空间区域(如芯部、台基区、刮削层、靶板区)的主要物理过程不同,因此需要采用系统集成方法开展全域多时空尺度物理问题分析.为了更加深入地研究托卡马克等离子体放电实验的稳态运行及爬升期间的输运与约束过程,通常采用多种物理程序开展集成模拟研究,对放电实验结果进行集成模拟对照,相互验证并进一步开展物理分析.本文基于OMFIT平台,结合HL-2A装置第37012炮高比压放电实验结果完成了集成模拟验证与分析,验证了程序的可靠性与适用性.在该流程中,通过选取适当的模型,对实验参数进行了校核与补充,经演化后模拟结果与实验结果比较吻合.在此基础上,本文进一步采用TGLF模型开展了芯部静电漂移波线性不稳定性分析,结果显示nbi离轴加热导致H模约束改善的原因是,该实验在nbi功率沉积位置的ETG不稳定性处于被抑制的状态,输运由ITG不稳定性占据主导,同时输运水平降低至新经典水平.

关键词：磁约束核聚变 HL-2A 高比压 H模

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