A model for electrical fast transient analyses of the ITER NBI power supplies and the MAMuG accelerator

The design of ITER Neutral Beam Injector (NBI) is based on a five-stage electrostatic accelerator, known as Multi-Aperture Multi-Grid (MAMuG) and characterised by an overall acceleration voltage of ?1 MV. The MAMuG accelerator requires a five-stage power supply system under strict load protection requirements, being subjected in operation to breakdowns. In this paper a circuit model of ITER Neutral Beam Injector power supplies and MAMuG accelerator is illustrated, for the simulation of fast transients related to accelerator breakdowns in particular. Consideration of the high voltage involved and of the complex inductive and capacitive couplings implied careful assessment of stray parameters by calculations with finite element techniques. The circuit model, developed to address a number of design issues requiring simulations at system level, is now ready for use—the optimisation of passive protections being the most significant application.     

CSRe分子离子研究装置低能传输线物理设计

本文完成了CSRe分子离子研究装置低能传输线的物理设计。采用Poisson/Superfish软件对150 kV倍压型高压加速器的电场分布进行了模拟,结果显示,加速器各区域空间电场强度均远低于击穿电场强度限值。利用Beampath程序对离子源引出的分子离子束在高压加速器中的传输进行了模拟,束流包络显示,加速区电场对分子离子束具有较强的聚焦作用,加速管出口束斑尺寸较小。采用Trace-3D程序设计了高分辨能力的磁分析系统和RFQ加速器的注入匹配段。通过Beampath程序的模拟,分析出了质量数为150的分子离子束,并由三单元四极透镜实现了分析束流与直线加速器RFQ的注入匹配。     

Gas flow and related beam losses in the ITER neutral beam injector

The gas flow in the ITER neutral beam injectors has been studied using a 3D Monte Carlo code to define a number of key parameters affecting the design and operation of the injector. This paper presents the results of calculations of the gas density in the two accelerator concepts presently considered as options for the ITER injectors, and the resultant stripping losses of the negative ions during their acceleration to 1 MeV. The sensitivity of the model to various parameters has been studied, including the gas temperature in the ion source and the subsequent accommodation by collisions with the accelerator structure, and the degree of dissociation of the D₂ or H₂ in the ion source, and subsequent recombination during collisions with the accelerator structure. Additionally the sensitivity of the losses to details of the beam source design and operating parameters are examined for both accelerator concepts.     

Vacuum Outgassing Behavior of Carbon Nanotube Cathode with High-Intensity Pulsed Electron Emission

Experimental investigations on the vacuum outgassing of a carbon nanotube(CNT)cathode with high-intensity pulsed electron emission on a 2 MeV linear induction accelerator injector are presented.Under the 1.60 MV diode voltage,the CNT cathode could provide 1.67 kA electron beam with the amount of outgassing of about 0.51 Pa-L.It is found that the amount of outgassing,which determines the cathode emission current,depends on the diode voltage and the vacuum.     

100 MeV强流质子回旋加速器超高真空系统研制

中国原子能科学研究院建成了一台强流质子回旋加速器,其引出能量为100 MeV,流强为200 μA。为减小粒子加速时束流损失的目的,其粒子加速腔内工作真空度要求为6.7×10^-6 Pa。由于是紧凑型加速器结构,该加速器能提供给真空系统利用的通路有限,为此主真空系统设计为内置式低温冷板结合商业低温泵的排气方案以增加系统整体的抽气能力。设计、加工完成的真空系统已成功应用于100 MeV强流质子回旋加速器上,为加速器的束流调试和正常供束提供了有利的保障。     

Design issues of the High Voltage platform and feedthrough for the ITER NBI Ion Source

In the ITER heating Neutral Beam Injector (NBI), a High Voltage air-insulated platform (named High Voltage Deck, HVD) will be installed to host the Ion Source and Extractor Power supply system and associated diagnostics referred to ?1 MV DC potential. All power and control cables are routed from the HVD via a feedthrough (HV bushing) to the gas insulated transmission line which feeds the Injector.The paper focuses on insulation and mechanical issues for both HVD and HV bushing which are very special components, far from the present industrial standards as far as voltage (?1 MV DC) and dimensions are concerned. For this purpose, a preliminary design of the HVD has been carried out as concerns the mechanical structure and external shield. Then, the structure has been verified with a seismic analysis applying the seismic load excitation specified for the ITER construction site (Cadarache) and carrying out verifications according to relevant international standards. As regards the HV bushing design, proposals for the complex inner conductor structure and for interfaces to the HVD and transmission line are outlined; alternative installation layouts (aside or underneath the HVD) are compared from both mechanical and electrical points of view.     

A new approach to passive protection against high energy and high current breakdowns in the ITER NBI accelerator

The energy stored in the 1 MV ITER Neutral Beam Injector power supply system will exceed by far the energy stored in the existing largest NB Injectors; as a consequence, the limitation of the grid breakdown effects–grids damage and Electro Magnetic Interference emission–are critical issues. In the present ITER NBI reference design the mitigation system is based on the concept of the concentrated core snubber which, due to the large amount of stored energy, is a huge component. Furthermore, in the NBI a relatively large part of HV capacitance to ground remains downstream the core snubber, so neither the arc peak current nor the high-frequency oscillations can be effectively limited. Moreover, the concentrated core snubber is ineffective in limiting the voltage reversal caused by internal insulation fault, increasing the risk of cascade failures in components like HV bushing and transmission line. The paper proposes an alternative approach to limit the grid breakdown effects, based on the concepts of Damper Resistor- substituting the direct connection to ground of the zero-potential accelerating grid – and of Distributed Core Snubber (DCS) – installed along the whole length of the transmission lines. The DCS concept has been subjected also to experimental validation by a small scale setup supported by electrical modelling.     

Conceptual design of a high-voltage compact bushing for application to future N-NBI systems of fusion reactors

The energy of future neutral beam injector (NBI) heating systems of fusion power plants ranges from 1 to 2 MeV. They are based on powerful (several tens of MW) hydrogen negative ion electrostatic accelerators where electrodes are polarized by DC high-voltage. The beam line under vacuum is supplied by HV power supplies via a transmission line pressured under SF₆ and a high voltage feedthrough called bushing. The paper presents results obtained over experimental campaigns dedicated to high voltage vacuum insulation for future NBI systems (ITER). It addresses the problematic of the electron field emission and the high voltage breakdown limit under vacuum between large electrode surfaces. The paper highlights the dependence of the electron emission (dark current) with the voltage and the background tank pressure: at low pressure (～1E?3 Pa in hydrogen), an important dark current of I ～ 100 mA has been measured at 500 kV, while at higher pressure (～0.3 Pa in helium), the dark current has been nearly suppressed (less than 3 mA of dark current at 970 kV). The paper shows that a field induced gas adsorption process could occur on the emitting surfaces (cathode), and this process tends to lower the electron field emission current by increasing the work function of the electrode surface. The Fowler–Nordheim law applied to the measured dark current indicates about 70% of work function increase at 0.3 Pa in helium. Finally, a new high-voltage bushing concept relevant to the future NBI systems is presented; it is based on these experimental findings in high voltage vacuum insulation; the main feature of the new bushing concept is to take benefit of the field induced adsorption effect, i.e., the suppression of the dark current with helium gas, in the inner part of the bushing where the electric field intensity is highest.     

4.5MV静电加速器离子聚束电路的设计

在加速器中产生脉冲中子源需要对离子源脉冲化。采用10MHz聚束和2.5MHz扫描频率，通过在交叉场分析器设置直流偏置电压和变频切割电压，改变离子束脉冲频率，使之从2.5MHz到39KHz可调。本文介绍了脉冲频率可调，幅度可调的脉冲化电路的改进设计及初步实验结果，并给出功放热设计参考。     

HVPTF—The high voltage laboratory for the ITER Neutral Beam test facility

In the MITICA research program for the construction of the ITER Neutral Beam Injector prototype, a Laboratory for the investigation on high voltage holding in vacuum has been set up. This Laboratory - HVPTF: High Voltage Padova Test Facility - is presently capable of experiments up to 300 kV dc, and planned for the upgrade to 800 kV. The specific mission for this ancillary lab is the support to the electrostatic design and construction of the MITICA accelerator and the development and testing of HV components to be installed inside the MITICA accelerator during its operation.The paper describes the structure of the lab, characterized by a high degree of automation and reports the results of the commissioning at 300 kV and the first results of voltage holding between test electrodes.     

GIC4117串列加速器外束PIXE/PIGE分析系统

本文介绍在北京师范大学GIC4117串列加速器上建立的外束PIXE/PIGE分析系统,和基于此系统的薄样品外束PIXE/PIGE定量分析方法。给出了2010年Teflon滤膜采集的361个气溶胶样品外束PIXE分析得到的各元素平均探测限和最低探测限,并同真空PIXE分析探测限进行了比较。利用标准样品给出了激发曲线不同坪区薄样品外束PIGE分析F和Na的探测限,通过测定¹⁹F(p, p′γ)¹⁹F激发的197 keV γ射线得到的F的探测限可达73.9 ng•cm^-2,Na的探测限可达198.9 ng•cm^-2。     

Preliminary design of the control and data acquisition systems for the Neutral Beam Test Facility

The Neutral Beam Test Facility, which will be built in Padova, Italy, is aimed at developing the ITER heating neutral beam injector (HNB) and at testing and optimizing its operation up to nominal performance before installation on ITER. It requires the development of two independent experiments referred to as SPIDER (source for production of ions of deuterium extracted from Rf plasma) and MITICA (megavolt ITer injector & concept advancement). SPIDER will explore the full-size negative ion source for ITER, whereas MITICA will explore the full-size ITER neutral beam injector. Both experiments will be designed for long-pulse operation, up to 3600 s, as ITER itself. MITICA includes three functional components: the heating neutral beam injector plant system (HNB), which is the device under test; the auxiliary plant system (AUX), which includes all equipment to operate the HNB in the test facility (e.g. the local electric grid to feed the HNB power supplies), and MITICA supervisory system that is an electronics/informatics infrastructure to operate the facility. The paper introduces the requirements for the control and data acquisition systems of the experiments and proposes a preliminary design for both systems. SPIDER, which is preparatory to MITICA and will be developed on a shorter time scale, has no constraints coming from ITER CODAC, whereas MITICA includes the ITER neutral beam injector and therefore must be fully compatible with ITER CODAC.     

高平均束流功率辐照加速器加速结构的研究

本文介绍了10 MeV/100 kW的高平均束流功率工业辐照加速器束流动力学模拟结果及其加速结构的优化设计结果。加速器采用驻波双周期轴耦合结构,1个加速腔和1个耦合腔构成1个加速单元,其工作频率为325 MHz,工作模式为π/2,加速腔和耦合腔之间通过耦合狭缝在轴向以磁耦合的方式耦合在一起。使用SUPERFISH优化加速腔的有效分路阻抗、Kilp系数等关键参数。束流动力学方面,使用PARMELA模拟论证在粒子源提供2.5 keV、500 mA的电子束后,通过6个加速腔可得到10 MeV/100 kW的平均束流功率。加速腔优化完成后使用CST对耦合腔进行了设计,此时由6个加速单元组成的加速结构有效分路阻抗为23.9 MΩ/m、无载品质因数为29 347,各加速腔与相邻的耦合腔耦合系数为4.7%,工作模式与其相邻模式的最小频率间隔为2 MHz,每个加速单元功耗为290 kW。     

同步加速器束流能量自动切换控制系统

带电粒子放射治疗中3D主动治疗方式需要不同的束流能量照射不同的病灶切面,这就需要同步加速器控制系统能实现多级束流能量的自动切换控制并提供接口对接治疗计划进行自动变能控制。本文开发了同步加速器束流能量切换控制系统,同步加速器的前端服务器中存储着执行1个同步加速器加速周期所需的全部控制数据集,其中控制数据通过索引标号对其进行区分,同步事例信息是同步加速器多级束流能量切换的触发信号。当前端控制器被同步时间系统的同步事例触发激活后,从DSP波形发生器的SDRAM空间中读出磁铁电源、高频等控制数据进行数据切换。同步事例信号包含同步触发信息、束流能量控制数据的索引信息和控制数据的更新操作信息。多级束流能量自动切换控制系统能实现255级束流能量间自动切换控制（碳束能量在50～500 MeV间切换,步长可控制在1.77 MeV）,完全能满足实际中碳束能量在50～500 MeV间以10 MeV为步长的自动切换控制。     

10C次级束的产生

在中国原子能科学研究院HI-13串列加速器次级束流线上通过¹H(¹⁰B，¹⁰C)n反应产生了能量为(55.9±0.9)MeV的¹⁰C放射性次级束。经过磁刚度和速度选择，准直后的¹⁰C束流纯度达到90%以上，强度约为6s^-1•pnA^-1。     

100 MeV强流质子回旋加速器剥离靶驱动控制系统研制

100 MeV强流质子回旋加速器(CYCIAE-100)加速负氢离子,引出系统为电荷交换方式的双向剥离引出系统,剥离靶是引出系统的核心装置。剥离靶系统四维联动定位精度要求高。为满足剥离靶驱动控制系统要求,采用了PLC控制驱动电路,读取位置反馈信号,对运动控制形成负反馈闭环的控制方法,实现了引出系统的各项运动控制要求并达到了设计指标。经调试,该加速器于2014年7月首次成功引出75~100 MeV质子束流,引出效率达99%以上。剥离靶驱动控制系统经加工调试,满足引出系统的各项技术要求,目前已投入运行2 a,可靠性得到了验证。     

13N次级束的产生

在北京串列加速器次级束流线上通过²H(¹²C,¹³N)n反应产生了可用于核天体物理研究的¹³N次级束。经磁刚度选择以及速度选择，准直后的次级束纯度达91%，能量为(70.2±0.7)MeV，强度约为10s^-1•pnA^－1，可用来进行逆几何转移反应的实验测量。     

The external beam microprobe facility in Florence: Set-up and performance

An external beam microprobe facility, based on a quadrupole doublet supplied by Oxford Microbeam Ltd, has been installed on a new beamline at the 3 MV single-ended Van de Graaff accelerator in Florence. The goal was to obtain a beam with a spot size on target of 10–20 μm and a current in the order of at least 1 nA, in order to allow PIXE, PIGE and RBS elemental analysis in air or in a helium atmosphere. The beam was extracted from the vacuum lines through a 0.1 μm thick Si₃N₄ window to minimise lateral straggling. The design goals have been successfully achieved; the measurements of the beam spot characteristics in vacuum as well as in air and in helium atmosphere, are here reported.     

高电荷态重离子束流产生技术的研究

为了提高北京HI-13串列加速器束流的硅中射程和LET值,本文开展了高电荷态束流引出技术及pA级弱束流诊断技术研究。采用电刚度和磁刚度模拟技术,配合pA级弱束流束斑观测和束流强度监测技术,获得能量360 MeV、峰总比80%的¹⁹⁷Au离子束流,其在Si中的表面LET为86.1 MeV•cm²•mg^-1、射程为30.1 μm,满足单粒子效应（SEE）实验的要求,拓展了北京HI-13串列加速器上单粒子效应实验所用离子的能量和LET值范围。     

Operation of the ITER Electrostatic Residual Ion Dump with a Perturbed Field

ITER will use a novel electrostatic method to remove the unwanted residual charged component from the neutral beam injectors in place of the usual magnet separation system. This technique has not been tested experimentally and is subject to the additional complication of plasma formation perturbing the electric field. Previous calculations have shown that whilst this is not significant for the 1 MeV heating beam systems, the lower energy diagnostic beam system will be susceptible. An analytical model of the electrostatic dump has been developed that includes the perturbation of the vacuum electrostatic field by both plasma and the separating positive and negatively charged residual beams. An approximate solution of Poisson’s equation is formulated that allows analysis of the space charge field when plasma density is insufficient to ensure zero electric field at the anode. The resulting modified electric field is then incorporated into a particle trajectory code to determine the deposition of the residual ions on the ERID panels. It is shown that the effect of plasma formation is to introduce an asymmetry into the deflecting field and the effect of the separating charges is to weaken the deflection of the residual beams. As a consequence the reference design for the ITER diagnostic beam will not collect all of the residual ions and it is recommended that the deflection voltage be increased by at least 50%.