Feedback Control System for Antenna Phase Difference in the LHCD Experiments

It is well accepted that lower hybrid current drive （LHCD） is the most efficient method for non-inductive current drive in fusion devices and the effect of the current drive is dependent on not only microwave power but also its grill phase shift. This paper presents a new kind of feedback control system for antenna phase difference in LHCD experiments. In this highspeed control system, a lot of new technologies and methods are incorporated. The results of the experiments show a very good agreement with the system design.     

HT-7装置上充气对低杂波耦合影响的实验及分析

在低杂波（LHW）天线端口充D₂和CD₄,发现LHW的耦合效果能得到明显改善,充气后LHW的反射系数基本降为6%左右。不同窗口充气对波的耦合和等离子体密度的影响不同,其原因是改善耦合的关键是提高刮削层（SOL）内等离子体的密度。D₂与CH₄对LHW耦合影响的实验结果表明：D₂对LHW的耦合效果影响略好于CH₄,但D₂对等离子体密度的影响明显高于CH₄,原因是D₂对电子密度的贡献更大。     

Experiment and Operation of a LHCD—35kV／2.8MW／1000s High—Voltage Power Supply on HT—7 Tokamak

A-35kV/2.8MW/1000s high-voltage power supply(HVPS) for HT-7 superconducting tokamak has been built successfully.The HVPS is scheduled to run on a 2.45 GHz/1MW lower hybrid current drive(LHCD)^[1] system of HT-7 superoonducting tokamak before the set-up of HT-7 superconducting tokamak in 2003.The HVPS has a series of advantages such as good steady and dynamic response,logical computer program controlling the HVPS without and fault,operationa panel and experimental board for data acquisition.which both are grounded distinctively in a normative way to protec the main body of HVPS along with its attached equipments from dangers.Electric power cables and other control cables are disposed reasonably,to prevent singals from magnetic interference and ensure the precision of signal transfer.This paper involves the experiment and operation of a 35kV/2.8 MW/1000s HVPS^[2] for 2.45 GHz/1 MW LHCD system.The reliability and feasibility of the HVPS has been demonstrated in comparison with experimental results of original design and simulation data.     

Numerical Simulation of Modified Radial Electric Field by LHCD

Based on the electron‘s radial force equilibrium, the profiles of radial electric field in OH and LHCD phase are calculated by using a simulation code. The dependences of radial electron field on electron density and its profile and different current ratio, Irf/Ip, are given. The connections between the improvement of plasma confinement and the modified radial electric field by LHCD are discussed by comparing the calculated results with the experimental results.     

EAST4.6GHz/4MW低杂波电流驱动系统隔直器优化设计

为了研究全超导托卡马克稳态高参数等离子体性能,2008年在EAST托卡马克装置上研制并成功建成了一套能最大传输2兆瓦,工作频率是2450MHz的低混杂波电流驱动系统,要实现低杂波长时间地维持等离子体电流,还需要对低杂波系统的输出功率大小及运行时间长度提出更高要求,拟研制一套波源输出功率4 MW,中心频率4.6GHz,波谱范围为1.7< N_(//)< 2.5,运行脉冲宽度0～1000秒低杂波电流驱动系统.在EAST4.6GHz/4MW低杂波电流驱动系统中,因为速调管放大器和低杂波天线有共同的接地点,速调管放大器电源为负高压,有接地点,低杂波天线有接地点,并且和EAST托卡马克相连,在系统中要求不能有两个接地点,所以要通过隔直器来隔断托卡马克和速调管之间的的直流通路.论文详细介绍了隔直器的原理和设计过程,在以4.6GHz为中心频率,150MHz的频带范围内,隔直器各个端口微波性能良好.     

Commissioning of 3.7 GHz LHCD system on ADITYA tokamak and some initial results

To drive plasma current non-inductively, a lower hybrid current drive (LHCD) system has been designed, fabricated and successfully installed on ADITYA tokamak. The system is designed to launch 120 kW of RF power, at a frequency of 3.7 GHz. The system mainly consists of a high power CW klystron source, a long waveguide transmission line of about 100 m length, a UHV compatible modular waveguide line of about 2.65 m, and a conventional grill type antenna. Independent phase shifters, one each in the eight lines, are used to adjust the antenna phasing and also provides the flexibility to launch a composite spectrum. The antenna is designed to launch lower hybrid waves (LHW) with parallel refractive index (N_||), in the range, 1 < N_|| < 4.5, by appropriately phasing the antenna. Antenna is positioned in the shadow of the poloidal limiter and is provided with 100 mm radial movement to achieve optimum coupling conditions.The complete system development includes design, fabrication and testing of number of waveguide components, modular waveguide lines and their integration. Different cost effective fabrication techniques are adopted to achieve good RF performance. Special attention is paid on the flanged joint seals in the long transmission line to minimize the RF losses. The entire LHCD system is calibrated, especially, in terms of phase, insertion loss and return loss measurements.After the successful integration of the system on ADITYA tokamak, some initial experiments have been carried out to assess the system commissioning and its performance. The experiments were done with a plasma (hydrogen) density of 2-5 × 10¹² cm⁻³ at a toroidal magnetic field of 0.8 T with 10-25 kA of plasma current. Initial results indicate that, good coupling is achieved in the presence of proper edge density. Measurements obtained from second harmonic electron cyclotron emission (ECE) and hard X-ray diagnostics suggest generation of suprathermal electrons in the presence of LH pulse. Plasma current pulse elongation with LH power is observed but needs further investigation to derive conclusions.This paper presents the design, fabrication, testing and integration of the waveguide lines, waveguide components and UHV compatible modular transmission lines of the LHCD system on ADITYA tokamak and discusses some of the initial results.     

三支节液态调配器ICRH时的阻抗匹配分析

基于传输线理论,采用三支节液态调配器以达到托卡马克离子回旋共振加热(ICRH)时射频源和天线负载间的阻抗匹配。分析了其阻抗匹配过程,并根据阻抗匹配条件得到天线输入阻抗变化时,三支节液态调配器的优化调配参数。利用数值模拟验证了在其他实验参数相同的条件下,三支节液态调配器的优化调配参数能使天线系统获得良好的匹配状态。     

Electromagnetic disruption analysis of 2.45 GHz LHW antenna in EAST under different plasma configurations

The 2.45 GHz lower hybrid wave (LHW) antenna is one of the key components for plasma heating and current drive on experimental advanced superconducting tokamak (EAST). In the lower hybrid current drive (LHCD) experiment, the microwave power is delivered to the plasma through the LHW antenna. During a plasma disruption, the eddy currents are induced in the antenna because of plasma current decay. These induced currents interact with the strong static magnetic field to produce forces and torques in the antenna which are one of key factors determining the design of the antenna. Therefore, this paper presents the key results of a transient electromagnetic (EM) analysis of the antenna during disruption events under different plasma configurations. Two plasma centered disruption scenarios are taken into account: exp quench and linear quench. The analysis was performed with MAXWELL, a computer code based on the finite element method. All the results are presented and discussed which will offer guidance for the design and manufacture of the antenna in future.     

Thermal Distributions of Multi-Junction Antenna and PAM Antenna

A multijunction antenna is under development for 4.6 GHz lower hybrid current drive system on experimental advanced superconducting tokamak (EAST). The antenna mouth is exposed to the high temperature plasma directly during tokamak discharge. The thermal distribution of the existing EAST 4.6 GHz multi-junction antenna is analyzed to evaluate the safety of the antenna under high power operation. Result shows that the maximum temperature is 628 °C at the antenna mouth. Then the result is also compared with that of a kind of passive active multijunction (PAM) antenna. The water channels in the multi-junction antenna are located on the upper and bottom of each module, while in the PAM antenna they are drilled behind the passive waveguides. The maximum temperature deposited on the port of PAM antenna is just 285.64 °C, at least two times lower than that of the multi-junction antenna.     

ICRH ITER-like antenna tested on TS commissioning,electrical modeling and load resilience studies

A prototype of ICRF antenna based on the load-resilient electrical layout anticipated for ITER has been built at CEA-Cadarache. It consists of two toroidally adjacent resonant double loops (RDLs) based on the conjugate-T concept proposed for the ITER ICRF array. This prototype has been recently validated in Tore Supra plasmas exhibiting fast density perturbations in front of the antenna. This paper reports on the load resilience properties of the antenna prototype, as well as the RF modeling and the commissioning. Significant effort on modeling, coupled to an extensive low power campaign, has allowed characterization of the antenna in both vacuum and plasma loading conditions. Plasma load modelings computed with the code TOPICA – very helpful to set up the matching points on plasmas – are found to be in good agreement with the experimental results. The main studies focus on load resilience properties have been carried out in L-mode plasmas. Supersonic molecular beam injection (SMBI), able to launch a series of very short/dense gas jets at Mach number up to 5, was used to mimic the sudden increases of the antenna coupling provoked by ELMs. The results are found to be in good agreement with RF circuit calculations that include 3D modeling.     

RF antenna analysis with the ICANT code

The ICANT code computes self-consistently the surface current distribution on a 3D antenna model radiating in a plasma or vacuum and has been used to analyze the coupling properties of various antenna models. In this work it is used to assess near-fields generated by different versions of the TCABR (Tokamak Chauffage Alfvén wave heating experiment in Brazil) antenna as well as coupling properties of the TEXTOR tokamak in Forshungszentrum Jülich. Two different strap models planned for the TCABR antenna are shown to be practically equivalent in terms of maximum electric field. Textor coupling calculations are close to experimental values.     

Commissioning the ICRF system and an ICRF assisted discharge cleaning at the KSTAR

Korean superconducting tokamak advanced research (KSTAR) is a national superconducting tokamak with the aim of a high beta operation based on advanced tokamak (AT) scenarios, and an ion cyclotron ranges of frequency (ICRF) heating is one of the essential tools to achieve this goal. The fabrication and high voltage (HV) test of the antenna and the matching system were finished in 2006 and the installation of the antenna, matching system and the transmitter at the KSTAR site was completed in 2007. Antenna conditioning was carried out to improve the HV holding condition of the antenna installed on the KSTAR and to check on the electro-magnetic (EM) interference with other equipments such as the superconducting magnet monitoring system and other machine and/or plasma diagnostic systems. The first KSTAR tokamak experimental campaign started by a vacuum pumping, a cryostat cooling and an ICRF system contributed to the successful tokamak shots through an ICRF assisted discharge cleaning of the vacuum vessel. In this paper, the installation processes of the ICRF system (with an emphasis on the quality assurance procedures of KSTAR), as well as the results from the first RF discharge experiment for the discharge cleaning and FWEH (fast wave electron heating) experiment for the KSTAR 1st experimental campaign are outlined.     

Impact of Toroidal Effect on Lower Hybrid Current Drive in Tokamak

The main topics concerning lower hybrid wave heating （LHH） and lower hybrid current drive （LHCD） in tokamak systems are presented. The inherent properties of tokamak systems give the ‘gap＇ filling on Brambilla＇s spectrum, which are conducive to LHCD, but, on the other hand, induce a consumption of wave energy by the trapped electrons, which reduce the current drive efficiency. The methods for the enhancement of the current drive efficiency may be derived from detailed analyses by drawing upon the ray tracing technology on toroidal geometry and the Fokker-Planck theory on velocity space.     

Status of the ITER Ion Cyclotron H&CD system

The ongoing design of the ITER Ion Cyclotron Heating and Current Drive system (20 MW, 40–55 MHz) is rendered challenging by the wide spectrum of requirements and interface constraints to which it is subject, several of which are conflicting and/or still in a high state of flux. These requirements include operation over a broad range of plasma scenarios and magnetic fields (which prompts usage of wide-band phased antenna arrays), high radio-frequency (RF) power density at the first wall (and associated operation close to voltage and current limits), resilience to ELM-induced load variations, intense thermal and mechanical loads, long pulse operation, high system availability, efficient nuclear shielding, high density of antenna services, remote-handling ability, tight installation tolerances, and nuclear safety function as tritium confinement barrier. R&D activities are ongoing or in preparation to validate critical antenna components (plasma-facing Faraday screen, RF sliding contacts, RF vacuum windows), as well as to qualify the RF power sources and the transmission and matching components. Intensive numerical modeling and experimental studies on antenna mock-ups have been conducted to validate and optimize the RF design. The paper highlights progress and outstanding issues for the various system components.     

Temperature Distribution at the Lower Hybrid Wave Antenna on the Superconducting Tokamak HT－7

The radiation constant of the plasma and the temperature distribution at the Lower Hybrid Wave(LHW) antenna on the superconducting tokamak HT-7 axe calculated from the engineering point of view and the result provides an important reference to the design of a new antenna.     

多网共站址建设的移动通信基站电磁辐射防护区域及防护距离划分的探讨

随着多网共站址基站的建设越来越多,按主瓣模式划出的电磁辐射防护区域和防护距离已经不能适应新的变化。本文根据天线发射的电磁能量分布特性提出了一种新的简洁适用的电磁辐射防护区域划分方式和相关参数的确定,通过理论计算得出它的防护距离,并与实际测量的结果相比较,结果表明该方式能够较好的反映实际情况。     

Benchmark Simulations of Gyro-Kinetic Electron and Fully-Kinetic Ion Model for Lower Hybrid Waves in Linear Region

Particle-in-cell(PIC)simulation method has been proved to be a good candidate to study the interactions between plasmas and radio-frequency waves.However,for waves in the lower hybrid range of frequencies,a full PIC simulation is not efficient due to its high computational cost.In this work,a gyro-kinetic electron and fully-kinetic ion(GeFi)particle simulation model is applied to study the propagations and mode conversion processes of lower hybrid waves(LHWs)in plasmas.With this method,the computational efficiency of LHW simulations is greatly increased by using a larger grid size and time step.The simulation results in the linear regime are validated by comparison with the linear theory.     

反应堆压力容器下腔室交混特性的数值模拟方法研究

反应堆冷却剂系统蒸汽管道发生破口事故后,硼溶液在反应堆压力容器下腔室的对流交混特性对于反应堆安全分析及事故后缓解与抑制策略制定均有重要作用。本文基于实验结果分析了反应堆压力容器下腔室的交混特性及浓度扩散过程,采用数值模拟方法结合实验数据比较了几种主要模型计算结果的准确性与可靠性。分析结果表明,压力容器下腔室的交混特性呈现出外围扩散特征,温度梯度法与组分输运模型具备描述浓度梯度扩散过程的能力,但在细节分布上仍存在进一步改善与优化的空间。     

Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code

In this paper,mass attenuation coefficients of concrete,bricks and cement plaster,as shielding materials,are calculated at 59.5,356,662,1173,1274 and 1333 keV by using the MCNP-X (version 2.4.0) code.The numerical simulation results are compared with previous Monte Carlo studies,experimental results and XCOM data.The effects of barite on mass attenuation coefficients are investigated.The mass attenuation coefficients increase with the barite content.Thus,our results agree well with experimental studies on gamma ray shielding of barite.It is flexible for the MN method to change the barite rates in material by small increments,which is experimentally difficult.Also,modeled geometry can be used for future approaches such as new designs and new structures especially in investigating new barite-containing materials to build nuclear reactors or high-energy radiation therapy facilities.     

EAST ICRF天线驱动结构改进设计

针对ICRF天线原有的驱动结构由于无自锁而导致天线移动过程中无法精确定位的缺点,给出了两种新的驱动结构设计方案,两种方案主要由步进电机和涡轮蜗杆减速器组成,均具有启动速度慢,推、拉力大,能精确定位的特点。在设计过程中,对两种驱动结构的启动转矩、丝杠的强度和稳定性进行了校核,通过理论计算分析,两种驱动结构设计均满足设计要求。整个驱动结构改进设计方案和方法可为其他同类装置提供有益的借鉴。