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1.
HL-2A中性束大功率离子源的研制   总被引:1,自引:0,他引:1  
2007年3月, 为HL-2A中性束注入器研制的大功率离子源在核工业西南物理研究院成功通过了测试. 该离子源为圆柱结构的桶式离子源型; 加速器采用三电极的加减速系统. 实验运行参数如下: 灯丝加热电流1100A, 电压12V, 弧放电电压120V, 弧放电电流1050A, 等离子体密度达2.5×1012/cm3, 离子流密度0.44A/cm2; 在距等离子体电极5mm的平面上, 等离子体的均匀性好于5%, 工作脉宽2s. 离子源物理设计、工程考虑、实验研究结果等将在本文介绍.  相似文献   

2.
在中性束离子源引出过程中,详细分析了引出束流的产生,这有利于得到更准确的引出功率和引出电极表面的热功率沉积情况。根据HL-2A装置中性束离子源引出电极的电连接方式和束流引出的物理过程,对离子源束流引出过程进行了分析,给出抑制极电流产生的主要来源。通过分析放电气压扫描实验中的结果发现:随着放电气压的增加,不同弧放电电流情况下抑制极电流均逐渐增加,且抑制极电流与引出电流的比值近似线性增加。针对引出离子束流经过引出电极的过程建立了物理模型。计算了抑制极电流与引出电流的比值与放电气压的依赖关系,计算结果与实验结果一致,验证了引出束流分析结果的合理性。  相似文献   

3.
为了给HL-2M装置建设一条5 MW中性束加热束线,开展了中性束加热用热阴极弧放电离子源放电室的研制。这条中性束束线包含4套80 kV/45 A/5 s离子源,放电室的设计指标为850 A/5 s。首先采用CST软件中的电磁工作室对特定几何结构的放电室会切磁场进行了模拟计算,得到了会切磁场分布,验证了会切磁场布局的合理性。针对放电室加工工艺和实验过程中局部拉弧等问题,对放电室结构进行了不断改进。放电室侧壁由40列会切磁体改为7圈环形磁体,阴极灯丝结构从灯丝板结构最终改为陶瓷可伐结构,并且在放电室和加速器之间增加了陶瓷屏蔽。在阴极板结构放电室和阴极陶瓷可伐结构放电室内都获得了正常的弧放电。最终定型的放电室采用周边7圈环形会切磁体和陶瓷可伐结构。在定型的放电室内达到了5 MW中性束束线离子源弧放电的指标。弧放电时间接近5 s,最大弧放电电流达到1000 A。  相似文献   

4.
介绍了HL-2A 装置中性束加热系统阴极灯丝电源的主电路拓扑结构、控制硬件及控制时序等。运用MATLAB 仿真软件对灯丝电源主回路进行了反馈控制仿真,发现电流在1000A 左右时,纹波约为1%,而电流降低至200A 时,纹波增大,约为3%。分别去掉低位控制柜内进线端的串联交流滤波电抗器L1 和并联LC 谐波滤波器进行仿真,结果显示输出电流纹波明显变大,说明L1LC 除了能够吸收谐波电流减少进入电网谐波的作用外,还能够对交流调压后的斩波波形进行一定的滤波作用,使得输出波形更加平滑。  相似文献   

5.
HL-2A装置NBI的设计参数为,注入气体为氢气、束能量60keY、束脉宽2s、两条束线切向注入、最终达到总的中性束注入功率4MW。目前,初步方案拟定为一条束线安装两个离子源,束线真空部分由一个主真空室和一个次真空室以及离子源真空室和漂移管道构成。  相似文献   

6.
针对HL-2A装置的中性束加速极电源系统的远程管理和监控,设计了以太网环境下的分布式控制系统。该系统核心部分是PC-104嵌入式工控机、数字接口卡、模拟接口卡以及控制软件。以中性束加速极电源系统为出发点,提出了控制系统的设计要求。从硬件设计和软件设计两方面,论述了分布式控制策略在中性束加速极电源系统中的具体实现。实验证明,该控制系统兼顾了远程管理和实时控制,实现了电源系统的稳定运行。  相似文献   

7.
为了在HL-2A上实现3MW的中性束注入,我院自主研制了直径为260ram,高度为240ram的大功率多磁极会切场离子源.目前,它的性能已达到并超过了最初设计指标,放电脉冲为ls时,最大离子流密度为0.44A/cm2;放电脉冲为3s时,等离子体离子流密度0.24A/cin2;等离子体非均匀性都在5%-7%范围之内.目?它是我国国内等离子体密度最高,放电功率最大的长脉冲桶式离子源.本文通过实验数据与理论相结合的方式对弧放电特性进行分析.  相似文献   

8.
A circular magnetic multi-pole line-cusp ion source with a nominal 45 keV 25 A hydrogen ion beam is developed for the neutraJ beam injector of the HL-2A tokomak. At present, this bucket ion source can produce a 40 keV 20 A hydrogen ion beam for less than lOOms on a test bed, and a 35 ke V 13A ion beam for 300ms on the injector of the HL-2A tokomak. The 1/e half-width of the ion beam power profile is about 6.0 ± 0.2 em at the positionof 3.26m downstream from ion source, and the corresponding divergence degree is nearly 1.1. The optimum perveance matched conditions were obtained experimentally, and were in good agreement with the values from experiential equation of Uhlemann et al. The maximum of optimum perveance reached 2.2 × 10^-6 A/V^1.5 for 38 keV beam energy. An ion beam with above 60% H^+ species fraction can be achieved, which was measured by Ha light Doppler shift spectroscopy. According to research results, a neutral beam with a total power of more than 0.6 MW was successfully injected into the plasma of the HL-2A Tokomak in 2008.  相似文献   

9.
For heating the tokamak plasma effectively, the ion source must be capable of producing ions with high proton ratio. The proton ratio, which is found to be more than 65.6% at the ion current of 19.6A with the extraction voltage of 39.6 k V, is measured with an image spectrograph by Doppler shift effect of Balmer-α-radiation spectrum emitted from fast hydrogen particles. The tendency of proton ratio with the ion density in experiment is almost the same as the mode devised by Zhang et al. Okumura et al. only gave the affection of the plasma volume and ion loss area on the proton ratio, but the relationship between the ion density in chamber and the proton ratio was not presented. We give the relationship.  相似文献   

10.
HL-2A tokamak, the first tokamak with divertor in China, has been constructed and put into operation in 2002. The main parameters are R=1.65 m, a=0.4 m, BT=2.8 T, Ip = 0. 48 MA. The divertor of HL-2A is unique, because it is characterized with a large closed divertor chamber. The device has double divertor chamber, but now it is operating with lower single null configuration to study the physics of divertor for the next step design of a divertor. Supersonic molecular beam injection (SMBI) system with LN2 cooling trap was first installed and demonstrated on the HL-2A tokamak in 2004. The first results of SMBI into HL-2A plasma are to demonstrate the function of the HL-2A divertor and to observe the cold pulse propagation during multi-pulse SMBI on HL-2A Tokamak.  相似文献   

11.
12.
Recent work on pulsed cryogenic ion sources at the Tokyo Institute of Technology are reviewed briefly. Surface flashover processes of low-temperature dielectric materials are investigated experimentally in connection with the cryogenic ion sources. Values of dc or pulse breakdown voltage are measured, and fast-frame photographs are taken to observe the luminous surfaces. Characteristics of magnetically insulated cryogenic diodes with externally applied radial fields are clarified as a function of the anode temperature. Hydrogen, nitrogen, or argon ion beam is extracted from each ice on the anode surface of the cryogenic diode.  相似文献   

13.
利用最新自行研制的电扫描发射度探测系统, 在ECR离子源上进行了一系列关于ECR离子源引出束流发射度的研究. 这套电扫描发射度探测系统安装在中国科学院近代物理研究所(兰州)的LECR3试验平台的束运线上. 试验中, 通过测量相关参数, 研究了磁场、微波、掺气效应及负偏压效应等对引出束流发射度的影响. 利用实验所得的结果与关于ECR等离子体和离子源束流发射度的半经验理论, 分析推导了离子源各可调参数与ECR等离子体的直接关系, 这为分析探索ECR离子源的工作机制提供了一定的参考依据.  相似文献   

14.
After more than ten years of practice, SMBI has been developed to become a useful fuelling method that is already considered to be an improvement over conventional gas puffing (GP). The HL-2A tokamak is the first tokamak with divertors in China. The main parameters of HL-2A are R = 1.65 m, α=0.4 m, BT=2.8 T and Ip=0.48 MA. The divertor of the machine now is operated with lower single null configuration. Large hydrogen cluster (〉100 atoms) can be produced at low temperature gas.  相似文献   

15.
At the moment,a 70MeV cyclotron is under construction by the IBA company.This cyclotron will be able to accelerate H~- beam from a multicusp source and with a beam intensity in the range of 10mA at the source extraction.A He~(1 2 ) beam is also required.This beam will be produced by a PANTECHNIK ECR ion source(SUPERNANOGAN)with an extracted current of 1 to 2mA.In this paper the studies and design of the two sources with a common axial injection in the cyclotron are described.  相似文献   

16.
The advantages of pellet injection as a competitive means of fuelling a tokamak are well known. They include: ( 1 ) deep deposition of fuel, ( 2 ) better fuelling efficiency, ( 3 ) purer plasma, and so on. Meanwhile, improving plasma performance by pellet injection has been proven in many tokamak experiments. The deposition of pellet particles following pellet injection causes a temporal change of the local plasma temperature and density gradients which affects the transport properties of the plasma, so pellet injection can be used as a method of studying the transport process as well.  相似文献   

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