Experimental results of a magnetic field modification to the radio frequency driver of a negative ion source

A magnetic field produced by a current flowing through the plasma grid(PG) is one of the solutions to reduce the collisional loss of negative ions in a negative ion source, which reduces the electron temperature in front of the PG. However, the magnetic field diffused into the driver has some influence on the plasma outflowing. In order to investigate the effect of changing this magnetic field on the outflowing of plasma from the driver, a circular ring(absorber) of high permeability iron has been introduced at the driver exit, which can reduce the magnetic field around it and improve plasma outflowing. With the application of the absorber, the electron density is increased by about 35%, and the extraction current measured from the extraction grid is increased from 1.02 A to 1.29 A. The results of the extraction experiment with cesium injection show that both the extraction grid(EG) current and H-current are increased when the absorber is introduced.

Characteristics of the pressure profile in the accelerator on the RF negative ion source at ASIPP

Neutral beam injection(NBI)systems based on negative hydrogen ion sources-rather than the positive ion sources that have typically been used to date-will be used in the future magnetically confined nuclear fusion experiments to heat the plasma.The collisions between the fast negative ions and neutral background gas result in a significant number of high-energy positive ions being produced in the acceleration area,and for the high-power long-pulse operation of NBI systems,this acceleration of positive ions back to the ion source creates heat load and material sputtering on the source backplate.This difficulty cannot be ignored,with the neutral gas density in the acceleration region having a significant impact on the flux density of the backstreaming positive ions.In the work reported here,the pressure gradient in the acceleration region was estimated using an ionization gauge and a straightforward 1D computation,and it was found that once gas traveled through the acceleration region,the pressure dropped by nearly one order of magnitude,with the largest pressure drop occurring at the plasma grid.The computation also revealed that the pressure drop in the grid gaps was substantially smaller than that in the grid apertures.

Development of data acquisition and over-current protection systems for a suppressor-grid current with a neutral-beam ion source

Neutral beam injection is one of the effective auxiliary heating methods in magnetic-confinementfusion experiments. In order to acquire the suppressor-grid current signal and avoid the grid being damaged by overheating, a data acquisition and over-current protection system based on the PXI（PCI e Xtensions for Instrumentation） platform has been developed. The system consists of a current sensor, data acquisition module and over-current protection module. In the data acquisition module,the acquired data of one shot will be transferred in isolation and saved in a data-storage server in a txt file. It can also be recalled using NBWave for future analysis. The over-current protection module contains two modes： remote and local. This gives it the function of setting a threshold voltage remotely and locally, and the forbidden time of over-current protection also can be set by a host PC in remote mode. Experimental results demonstrate that the data acquisition and overcurrent protection system has the advantages of setting forbidden time and isolation transmission.

Design of the Prototype Negative Ion Source for Neutral Beam Injector at ASIPP

In order to support the design, manufacture and commissioning of the negative- ion-based neutral beam injection （NBI） system for the Chinese Fusion Engineering Test Reactor （CFETR）, the Hefei utility negative ion test equipment with RF source （HUNTER） was proposed at ASIPP. A prototype negative ion source will be developed at first. The main bodies of plasma source and accelerator of the prototype negative ion source are similar to that of the ion source for EAST-NBI. But instead of the filament-arc driver, an RF driver is adopted for the prototype negative ion source to fulfill the requirement of long pulse operation. A cesium seeding system and a magnetic filter are added for enhancing the negative ion density near the plasma grid and minimizing co-extracted electrons. Besides, an ITER-like extraction system is applied inside the accelerator, where the negative ion beam is extracted and accelerated up to 50 kV.

Influence of magnetic filter field on the radio-frequency negative hydrogen ion source of neutral beam injector for China Fusion Engineering Test Reactor

In the design of negative hydrogen ion sources,a magnetic filter field of tens of Gauss at the expansion region is essential to reduce the electron temperature,which usually results in a magnetic field of around 10 Gauss in the driver region,destabilizing the discharge.The magnetic shield technique is proposed in this work to reduce the magnetic field in the driver region and improve the discharge characteristics.In this paper,a three-dimensional fluid model is developed within COMSOL to study the influence of the magnetic shield on the generation and transport of plasmas in the negative hydrogen ion source.It is found that when the magnetic shield material is applied at the interface of the expansion region and the driver region,the electron density can be effectively increased.For instance,the maximum of the electron density is 6.7×10^(17)m^(-3)in the case without the magnetic shield,and the value increases to 9.4×10^(17)m^(-3)when the magnetic shield is introduced.

Analysis of the characteristics of the plasma of an RF driven ion source for a neutral beam injector

A radio frequency(RF)driven ion source is a very important component of a neutral beam injector for large magnetic confinement fusion devices.In order to study the key technology and physics of an RF driven ion source for a neutral beam injector in China,an RF ion source test facility was developed at the Institute of Plasma Physics,Chinese Academy of Sciences.In this paper,a two-dimensional fluid model is used to simulate the fundamental physical characteristics of RF plasma discharge.Simulation results show the relationship of the characteristics of plasma(such as electron density and electron temperature)and RF power and gas pressure.In order to verify the effectiveness of the model,the characteristics of the plasma are investigated using a Langmuir probe.In this paper,experimental and simulation results are presented,and the possible reasons for the discrepancies between them are given.This paper can help us understand the characteristics of RF plasma discharge,and give a basis for further R&D for an RF ion source.

Estimation of Ion Beam Trajectories for a Slot Aperture Accelerator of Long-Pulse Ion Source in Neutral Beam Injector

A neutral beam injection (NBI) system has been developed and is being tested for an Experimental Advanced Superconducting Tokamak (EAST) device. The NBI system needs to be employed for an auxiliary heating and current drive of EAST plasmas. The first long pulse ion source (LPIS-1) has been installed in the neutral beam test bed (NBTB) system, and the performance is being tested in the NBTB. The LPIS-1 consists of a magnetic bucket plasma generator with multipole cusp-fields and a set of tetrode accelerators with slit-type apertures (a transparency of 60%). The ion beam trajectories of the accelerator column are estimated for the LPIS-1, including an original structure, with the change of slit aperture distance, plasma grid shape, grid gap distance, and voltage ratio between a plasma grid and a gradient grid using the IGUN code. This kind of calculation for the ion beam trajectory may be useful for the estimation of beam extraction characteristics and the direction of accelerator upgrade or modification, prior to the experiments of ion beam extraction.

Using Adaptive Discrete-Time Gas Supply Control for Long Pulse Arc Discharge of Ion Source on NBI

A control model of gas supply system is introduced for ion source and an adaptive discrete-time control algorithm to regulate the hydrogen injection. A real-time feedback control system （RFCS） is designed to control the gas supply for ion source based on the control model and the discrete-time control algorithm. The experimental results have proved that RFCS could regulate the gas supply smoothly, suppress the arc＇s abrupt over-current at the end of the ion source discharging, prolong the discharge pulse and stabilize the ion concentration. With RFCS, the ion source for neutral beam injection has reached its longest pulse with a length of 4.5 seconds in a stable status.

Preliminary results of optical emission spectroscopy by line ratio method in the RF negative ion source at ASIPP

Optical emission spectroscopy(OES)using the trace rare gases of Ar and Xe have been carried out in a radio frequency(RF)driven negative ion source at Institute of Plasma Physics,Chinese Academy of Science(ASIPP),in order to determine the electron temperature and density of the hydrogen plasma.The line-ratio methods based on population models are applied to describe the radiation process of the excited state particles and establish their relations with the plasma parameters.The spectral lines from the argon and xenon excited state atoms with the wavelength of 750.4 and 828.0 nm are used to calculate the electron temperature based on the corona model.The argon ions emission lines with the wavelength of 480 and 488 nm are selected to calculate the electron density based on the collisional radiative model.OES has given the preliminary results of the electron temperature and density by varying the discharge gas pressure and RF power.According to the experimental results,the typical plasma parameters isTe2≈2-4 eV and ne≈1 x 1017-8 x 1017 m^-3 in front of plasma grid.

强流RFQ注入系统研制

本文介绍研制的强流RFQ注入系统。系统包括强流离子源、聚焦透镜、束流切割器等,注入系统在RFQ入口处形成了束流能量75keV、流强42mA、α参数为1.79、β参数为0.0596 mm/mrad、束流脉冲频率1-100 Hz、束流占空比1%-100%、发射度小于95.2πmm mrad的质子束,可满足强流RFQ对束流注入品质的要求。

750keV,50mA H^-RFQ预注入器调整结果

文章介绍西德DESY研究所750keV负氢离子预注入器的调整结果。通过提高弧流,磁控管型H^-离子源可以引出18keV,60—80mA的H^-脉冲离子流。发现外部磁场可以在螺旋管内部感生一个方向大体相同的磁场。在低能输运段,离子束空间电荷中和所需的时间约100μs。在离子源引出束流约65mA时,经两对螺旋管聚焦和RFQ加速后可以获得能量为750±8.8keV,聚团半宽度约0.8ns,发射度约3mm·mrad,束流为52mA的脉冲H^-流;其中33mA以上的束流处于1mm·mrad以内。

Hefei utility negative ions test equipment with RF source:commissioning and first results

In order to study the key technology and physics of RF driven negative ion source for neutral beam injector in China, the Hefei utility negative ions test equipment with RF source was developed at Institute of Plasma Physics, Chinese Academy of Sciences（ASIPP）. Its negative ion source can be equipped with single or double RF drivers. There is a plasma expansion chamber with depth of 19 mm and an enhanced filter field. A three electrodes negative ion accelerator was employed to extract and accelerate the negative ions, which are plasma grid,extraction grid and ground grid. And there are several diagnostic tools for the plasma and beam parameters measurement. The characteristics of plasma generation, negative ion production and extraction were studied on the test equipment. The negative ion beam was extracted from the RF driven negative ion source for the first time. The detailed structure and main results are presented in this article.

Development of Powerful RF Plasma Sources for Present and Future NBI Systems

This paper deals with the topic of RF plasma sources and their application inhigh-power neutral beam heating systems for nuclear fusion devices. RF sources represent aninteresting alternative to the conventional arc discharge sources. Due to the absence of hotfilaments they exhibit an inherent simplicity both in mechanical and electrical aspects andconsequently offer advantages in terms of cost savings, gain in availability and reliability andreduced maintenance. This renders the RF plasma source attractive for any long pulse (> 10 sec) NBIsystem and in particular for the ITER NBI system. The latter, however, requires that the RF plasmasource is also capable of delivering negative rather than positive hydrogen ions. In the first partof the paper the types, characteristics and operation experience of RF plasma sources for positiveions in operation are described. The second part is devoted to the development for ITER NBI: thebasic requirements, physics and technology issues and the present status are discussed.

双驱动射频负氢离子源匹配网络设计与实验研究

随着磁约束聚变实验装置对中性束注入器的输出束流强度与脉冲时间的要求越来越高,开展高功率大面积射频离子源的研究迫在眉睫。为了实现大面积、高密度均匀等离子体放电,基于多驱动射频离子源的设计是当前的发展趋势,而阻抗匹配网络是射频功率源将最大功率输送至线圈并耦合至等离子体的关键,故对其结构设计和调谐特性的研究是不可或缺的。基于前期在单驱动射频离子源的研究基础上,结合双驱动射频离子源的放电需求,开展了双驱动阻抗匹配网络优化结构的设计与分析,通过实验中对匹配网络的调谐,成功实现了140 kW高功率和25 kW/1 000 s长脉冲的稳定运行。随后在等离子体稳定放电的基础上研究了两个驱动器之间的功率分配均匀性问题,实验结果表明了该匹配网络的优化设计合理可行,上下驱动器的射频功率分配基本均匀。

直接等离子体注入模式下激光离子源与RFQ匹配的模拟研究

基于直接等离子体注入(Direct Plasma Injection Scheme,DPIS)的方法,设计并建造了一台低能段离子加速装置;目前实验上利用该方法成功地加速了峰值流强为11.28 m A,能量为593 ke V/u的C6+脉冲束流。考虑到激光离子源产生的束流为脉冲束,且具有能散大,强度高等特点,给低能传输线(LEBT)的设计带来很大的困难,而DPIS方法则简单易行,可有效地提高注入效率;因此该装置将激光离子源与RFQ直接连接在一起,将离子源产生的等离子体直接注入到RFQ,并没有采用传统的LEBT。并采用IGUN程序对该注入方法进行了模拟,计算确定了离子源引出的强流脉冲束的参数以及注入效率,模拟的结果与实验的测量值一致。

大功率射频负离子源等离子体发光监测系统的研制

基于射频波驱动的负离子源已成为未来中性束注入系统的首选方案。为监测大功率射频负离子源的各个激励器的等离子体放电状态,设计并搭建了基于光电二极管的等离子体发光监测系统。等离子体发光强度与特定碰撞发生次数、碰撞粒子密度、碰撞粒子能量等密切相关。因此,等离子体发光强度能够定性反映出等离子体参数;基于合理的碰撞辐射模型,同时通过分析等离子体特征谱线强度,能够定量地得到等离子体参数。据此,该系统通过实时采集不同位置的等离子体发光强度信息,并以电压信号形式展现并保存下来,用于上位机实时监测和后数据处理。实验结果表明:本系统能够准确、在线地测量射频激励器内的等离子体的激发、维持和熄灭过程,且等离子体发光强度与射频爬坡放电功率具有较好的线性度,并测试了等离子体电流产生的过滤磁场对等离子体发光信号的影响。

Overview of Development Status for EAST-NBI System

The neutral beam injection （NBI） system was developed on the Experimental Ad- vanced Superconducting Tokamak （EAST） for plasma heating and current driving. This paper presents the brief history, design, development, and the main experimental results of the R＆D of neutral beam injector on the test bed and on EAST. In particular, it will describe： （1） how the two beamlines with a total beam power of 8 MW were developed; （2） the design of the EAST-NBI system including the high power ion source, main vacuum chamber, inner components, beam diag- nostic system and sub-system; （3） the experimental results of beamline-1 on the summer campaign of EAST in 2014 and, （4） the status of beamline-2 and the future plan of EAST-NBIs.

CRAFT负离子源中性束注入系统400 keV加速器束流光学特性分析

负离子源中性束注入(NNBI)系统是聚变堆主机关键系统综合研究设施(CRAFT)的组成部分,其目标是开展NNBI相关的科学与工程问题研究,为未来聚变堆NNBI系统的研制与运行积累经验。加速器的束流光学特性决定着最终形成束流的发散性,进而影响着束流在加速器和束线中的传输效率,这对NNBI系统的高功率、高能量、长脉冲运行至关重要。为此,采用IBSimu离子束流模拟程序对目前CRAFT NNBI的400 keV加速器电极系统的物理设计进行束流光学特性分析与评估。目前该套电极结构的设计与ITER负离子源类似,束发散的计算结果满足设计要求。在负离子束流密度较高时(100~300 A/m^(2)范围内),具有更小束发散角;引出距离(5~7 mm范围内)和加速距离(88~110 mm范围内)的适当增加,也呈现出束发散角下降趋势。

大面积射频离子源等离子体激励模拟研究

中性束注入(Neutral Beam Injection,NBI)加热是磁约束核聚变装置中最重要的辅助加热手段之一。大面积强流射频(Radio frequency)离子源是高功率NBI系统的核心部件。为了获得高密度、均匀的等离子体,在单激励器射频离子源研究的基础上对双激励器射频离子源的结构和等离子体激励特性进行了模拟,给出了射频离子源不同结构和参数对等离子体产生的影响,包括射频激励器间距、扩展室深度、射频功率以及放电气压等。研究结果可为大面积射频离子源的研制和多激励器射频负离子源的设计和优化提供支持。

大面积负离子束源磁过滤器的设计及实验研究

中性束注入是磁约束核聚变能研究中重要的辅助加热手段。大面积负离子源是中性束注入系统的核心部件。在负离子源工作过程中,负离子的电子结合能非常小(约0.75e V),极易被高能电子破坏。为此需要设计过滤磁场降低电子温度,减少负离子的损失,同时也可以减少伴随引出的电子。根据大面积负离子束源的机械结构,分别设计了永磁体产生过滤磁场和利用等离子体电极(PG)电流产生磁场两种磁过滤器结构;通过有限元算法对产生的过滤磁场进行模拟分析和优化,完成了大面积负离子束源过滤磁场的研制。在负离子束源测试平台开展实验测试,引出区电子温度从5eV降至1eV。这个结果初步验证了大面积负离子束源的过滤磁场的性能,为大面积负离子束源的研制提供了支持。