EAST-ICRH系统高功率同轴隔直器的研制

EAST超导托卡马克是我国开展受控核聚变研究的新一代实验装置,离子回旋波加热(ICRH)是在该装置中加热等离子体的重要手段之一。离子回旋加热系统中的发射机和天线两者各有一个地电平,两个地电平会存在严重的相互干扰。高功率同轴隔直器的作用是用来隔断两者之间的直流通路,从而把两端的地电平分开,保证发射机和天线系统的正常运行。论文介绍了隔直器的原理、工程结构和设计指标,分析了S参数、端口驻波比的计算和仿真,最后给出了实际的隔直器参数曲线。     

EAST-ICRH发射机宽频阻抗匹配网络的研究及实现

EAST(Experimental Advanced Superconducting Tokamak)是我国开展受控核聚变研究的新一代实验装置,离子回旋波加热(ICRH)是在该装置中加热等离子体的重要手段之一。论文介绍了离子回旋发射机中阻抗匹配网络的原理及实现方法,并采用LabVIEW软件和PLC相结合的方式开发了一套阻抗匹配网络调节系统。     

AST-ICRH天线相位的控制研究

EAST超导托卡马克是我国开展受控核聚变研究的新一代实验装置,离子回旋波加热(ICRH)是在该装置中加热等离子体的重要手段之一.要高效地实现波加热就要很好地控制相位,设计了一套相位控制系统,可以有效地调节加热系统天线的相位关系,从而很好地实现波加热.     

EAST-ICRH天线相位的控制研究

EAST超导托卡马克是我国开展受控核聚变研究的新一代实验装置,离子回旋波加热(ICRH)是在该装置中加热等离子体的重要手段之一。要高效地实现波加热就要很好地控制相位,设计了一套相位控制系统,可以有效地调节加热系统天线的相位关系,从而很好地实现波加热。     

EAST离子回旋波加热快速阻抗匹配系统的研究

离子回旋波加热是EAST装置最重要的辅助加热方法,在实验中获得了明显的加热效果。射频功率源与天线负载之间阻抗匹配才能保证最大的加热功率输出。在射频加热实验中,等离子体参数的改变将会引起天线负载阻抗的快速变化,为应对这一情况研制出了快速阻抗匹配系统。本文采用解析法和计算机仿真相结合的分析方式,研制了该阻抗匹配系统的铁氧体匹配支节,并对其性能进行了测试。测试结果表明,快速阻抗匹配系统的时间响应速度明显优于传统匹配方式的,可作为实时匹配的候选者。     

射频损耗下EAST四电流带ICRF天线电流带热-结构分析

为实现EAST装置等离子体高参数、稳态运行目标,需要高功率外部辅助加热,离子回旋共振(ICRF)加热是主要的辅助加热手段之一。由于ICRF天线运行频率高,因此ICRF天线的射频损耗较大,在天线表面的热负载较大。本文对EAST ICRF天线进行电磁分析的基础上得到天线的射频损耗分布。根据天线的射频损耗分布完成冷却流道设计,并通过对天线的热结构分析推算电流带的使用寿命,同时验证冷却流道结构设计的可行性与可靠性。     

EAST中性束注入器研制进展

EAST(Experimental Advanced Superconducting Tokamak)作为世界上第一个全超导非圆截面托克马克,其目标是研究1 000 s的长脉冲稳态运行的前沿性物理问题,要达成这一目标,必须有高功率电流驱动和辅助加热系统以实现EAST装置的高参数稳态运行。中性束注入(Neutral Beam Injection,NBI)加热是等离子体辅助加热和维持最有效的手段之一,为此一套注入功率4–8 MW、脉冲宽度10–100 s的中性束注入系统于2010年开工建设,并于2014年实现了对等离子体的加热和驱动。本文主要展示了EAST中性束注入器的最新进展,从长脉冲束引出和高功率束引出两个方面介绍了EAST中性束注入器综合测试台的最新实验结果,结果表明在束功率和脉冲宽度方面已经达到或超过设计指标。     

EAST-ICRF传输线驻波电压测量系统设计

为准确测量EAST离子回旋波加热(ICRF)系统中的驻波电压,设计了一款传输线驻波电压测量系统。该系统利用传输线上的电压探针阵列,经检波器、光电隔离器和采集卡接入PC机的数据处理模块,并用LabVIEW数据采集处理软件将采集到的信号进行拟合。测量结果能够清楚地得到各电压探针的电压值,拟合结果具有明显的驻波特性,同时还可以将探针信号作为发射机的保护信号,用于保护发射机安全稳定运行。     

EAST离子回旋加热系统高功率射频放大器阳极电源的研制

离子回旋共振加热是EAST超导托卡马克核聚变实验中重要的辅助加热手段。高性能的高功率射频放大器阳极电源对整个加热系统的稳定运行起重要作用。本工作设计了基于脉冲阶梯调制（PSM）技术的阳极电源及其控制保护系统，通过采集电源的实验数据对电源的设计进行了验证。实验结果证明，本阳极电源的设计和参数选择均是合理正确的，电源的开通和关断以及控制保护的数据指标完全达到设计要求。     

基于FPGA的EAST-ICRH天线相位测量研究

离子回旋波加热(ICRH)是EAST超导托卡马克核聚变实验装置加热等离子体的重要手段之一,而离子回旋加热天线电流带之间的相位关系影响到天线的加热效果。论文提出了一种基于FPGA的ICRH天线相位测量方案,采用双AD8302模块以及新的算法解决了相位测量的二值性和非线性误差问题,测量精度高。同时利用FPGA可编程的特点,使得系统的设计变得简洁灵活,便于后期功能的扩展。     

Current Status of ICRF Heating Experiments on EAST

Radio frequency (RF) heating in the ion cyclotron range of frequencies (ICRF) is one of the primary auxiliary heating methods for EAST. The ICRF system provides 6 MW power in primary phase and will be capable of 10 MW later. Three 1.5 MW ICRF systems in a frequency range of 25 to 70 MHz have already been in operation. The ICRF heating launchers are designed to have two current straps with each driven by a RF power source of 1.5 MW. In this paper a brief introduction of the ICRF heating system capability in EAST and the preliminary results in EAST are presented.     

EAST ion cyclotron resonance heating system for long pulse operation

Radio frequency (RF) power in the ion cyclotron range of frequencies (ICRF) is one of the primary auxiliary heating techniques for Experimental Advanced Superconducting Tokamak (EAST). The ICRF system for EAST has been developed to support long-pulse high-β advanced tokamak fusion physics experiments. The ICRF system is capable of delivering 12 MW 1000-s RF power to the plasma through two antennas. The phasing between current straps of the antennas can be adjusted to optimize the RF power spectrum. The main technical features of the ICRF system are described. Each of the 8 ICRF transmitters has been successfully tested to 1.5 MW for a wide range of frequency (25–70 MHz) on a dummy load. Part of the ICRF system was in operation during the EAST 2012 spring experimental campaign and a maximum power of 800 kW (at 27 MHz) lasting for 30 s has been coupled for long pulse H mode operation.     

Optimization Study of ICRF Hydrogen Minority Heating in a Deuterium Plasma of EAST

The full wave TORIC code and the Kinetic Fokker-Planck SSFPQL code are combined to perform self-consistent simulations of the ICRF heating in the EAST 2D magnetic configuration.The combined package is applied to the ICRF hydrogen minority heating in a deuterium plasma with the hydrogen concentration up to 10%.The fast wave propagation and absorption properties,power partitions among the plasma species and the RF driven energetic tails have been analyzed.Meanwhile,in order to optimize the ICRF heating,changing the resonance locations has also been considered in EAST plasmas.     

Experimental study of a single tube high RF power amplifier for ICRF heating system

A concept of a single tube high RF power amplifier was developed for ion cyclotron range of frequency (ICRF) plasma heating system. In the concept, a tetrode was used with a grounded cathode and input power to drive a control grid of the tetrode was provided by a switching circuit. As the new amplifier arrangement can eliminate a low power (10 kW level) and an intermediate power (100 kW level) tetrode amplifiers, their high voltage DC (HVDC) power supplies, and control and monitor system for these amplifiers and HVDC power supplies in a conventional high RF power source of the ICRF heating system, this new high RF power source is more flexible on frequency change and more mechanically reliable than the conventional one. A test amplifier composed of the tetrode and a field effect transistor (FET) switching circuit was constructed. The FET switching circuit was so compact that it could be mounted close to the tetrode socket. The maximum output RF power of 8.5 kW was obtained with a plate efficiency of 82% at 70 MHz. The feasibility of the single tube high RF power amplifier was experimentally proved. The plate efficiency of 82% could not be explained by the standard class-C amplification but by high efficiency amplification under assumptions of a flat-topped plate current pattern and double resonance of an output cavity at the fundamental frequency and the third higher harmonic frequency.     

Results of ICRF Heating Experiments from the EAST 2010 Campaign

Radio frequency(RF) plasma heating in ion cyclotron range of frequencies(ICRF)was successfully performed on the Experimental Advanced Superconducting Tokamak(EAST).This is mainly because lithium wall conditioning was routinely used to reduce both impurity and hydrogen(H) recycling and to improve the ICRF power absorption.Mainly ICRF heating of the H minority regime at 27 MHz has been applied in deuterium plasmas.The ion cyclotron resonance heating(ICRH) is found to depend strongly on plasma preheating.The ICRH efficiency can be much improved in conjunction with the lower hybrid wave(LHW).Effective ion and electron heating was observed with the H minority heating mode.The increase of the stored energy reached30 kJ in L-mode plasma by using the ICRF power of 1.0 MW alone when the H cyclotron resonance layer was at plasma center.     

Achievement of 1.9 MW for 300 s during the commissioning of the KSTAR ICRF transmitter

KSTAR (Korea Superconducting Tokamak Advanced Research) is a national tokamak aiming at the high beta operation based on AT (Advanced Tokamak) scenarios in Korea and ICRF (Ion Cyclotron Ranges of Frequency) is one of the essential heating and current drive tools to achieve this goal. The ICRF heating and current drive scenario requires 4 units of 2 MW transmitters with a frequency range from 25 to 60 MHz. The first KSTAR transmitter is a modified FMIT (Fusion Material Irradiation Test) transmitter consisting of four amplifier stages. An amplitude-modulated 1 mW frequency source drives a 500 W solid state wideband amplifier, which in turn drives three tuned triode/tetrode amplifier stages. The tube employed in the final power amplifier is a 4CM2500KG tetrode fabricated by CPI (Communications & Power Industries). After the fabrication of the cavity and power supply was completed in 2004, several failures of the tube during a factory and a site acceptance test occurred before eventually achieving 1.9 MW for 300 s at 33 MHz in 2007. The electrical efficiency of the FPA (Final Power Amplifier) is about 70%. Although this is a very encouraging result for the development of an ICRF transmitter for ITER (International Thermonuclear Experimental Reactor), continued efforts for a reliable operation are required to achieve the final goals of the KSTAR and ITER ICRF system.     

Study on Cavity Modes for D(H) Ion Cycloton Range Frequency Heating Scenarios in EAST

For low single-pass absorption of ion cyclotron range frequency (ICRF) wave in the EAST plasma cavity modes are expected to be excited between the low field side (LFS) antenna and the hybrid cut-off layer. The toroidal spectrum for D(H) minority heating scenarios in EAST is modeled by using FELICE（Finite Elements Ion Cyclotron Emulator）, a full wave code based on plane-stratified geometry. The excitation of cavity modes is studied. The methods for suppressing cavity modes are also discussed, to increase the efficiency of minority ion heating.     

Observation of Central Toroidal Rotation Induced by ICRF on EAST

Core plasma rotation of both L-mode and H-mode discharges with ion cyclotron range of frequency(ICRF) minority heating(MH) scheme was measured with a tangential X-ray imaging crystal spectrometer on EAST(Experimental Advanced Superconducting Tokamak).Cocurrent central impurity toroidal rotation change was observed in ICRF-heated L-and H-mode plasmas.Rotation increment as high as 30 km/s was generated at ~1.7 MW ICRF power.Scaling results showed similar trend as the Rice scaling but with significant scattering,especially in L-mode plasmas.We varied the plasma current,toroidal field and magnetic configuration individually to study their effect on L-mode plasma rotation,while keeping the other major plasma parameters and heating unchanged during the scanning.It was found that larger plasma current could induce plasma rotation more efficiently.A scan of the toroidal magnetic field indicated that the largest rotation was obtained for on-axis ICRF heating.A comparison between lower-single-null(LSN)and double-null(DN) configurations showed that LSN discharges rendered a larger rotation change for the same power input and plasma parameters.     

Mechanical design of the second ICRF antenna for EAST

In order to satisfy the requirements of heating plasma on EAST project, 3 MW ion cyclotron range of frequency (ICRF) heating system will be available at the second stage. Based on this requirement, the second ICRF antenna, has been designed for EAST. The antenna which is planned to operate with a frequency ranging from 30 MHz to 110 MHz, comprises four poloidal current straps. The antenna has many cooling channels inside the current straps, faraday shield and baffle to remove the dissipated RF loss power and incoming plasma heat loads. The antenna is supported via a cantilever support box to the external support structure. Its assembly is plugged in the port and fixed on the support box. External slideway and bellows allow the antenna to be able to move in the radial direction. The key components of the second ICRF antenna has been designed together with structural and thermal analysis presented.     

Tunable biasing magnetic field design of ferrite tuner for ICRF heating system in EAST

Ion cyclotron range of frequency(ICRF) heating has been used in tokamaks as one of the most successful auxiliary heating tools and has been adopted in the EAST. However, the antenna load will fluctuate with the change of plasma parameters in the ICRF heating process. To ensure the steady operation of the ICRF heating system in the EAST, fast ferrite tuner(FFT) has been carried out to achieve real-time impedance matching. For the requirements of the FFT impedance matching system, the magnet system of the ferrite tuner(FT) was designed by numerical simulations and experimental analysis, where the biasing magnetic circuit and alternating magnetic circuit were the key researched parts of the ferrite magnet. The integral design goal of the FT magnetic circuit is that DC bias magnetic field is 2000 Gs and alternating magnetic field is±400 Gs. In the FTT, E-type magnetic circuit was adopted. Ferrite material is Nd Fe B with a thickness of 30 mm by setting the working point of Nd Fe B, and the ampere turn of excitation coil is 25 through the theoretical calculation and simulation analysis. The coil inductance to generate alternating magnetic field is about 7 m H. Eddy-current effect has been analyzed, while the magnetic field distribution has been measured by a Hall probe in the medium plane of the biasing magnet. Finally, the test results show the good performance of the biasing magnet satisfying the design and operating requirements of the FFT.