电子回旋波Ohkawa机制电流驱动计算

从电子回旋波电流驱动的机制出发,理论推导出了Boozer-Fisch电流与Ohkawa电流的计算表达式,并给出了具体的计算方法。数值模拟结果表明:电子回旋波的波功率沉积在托卡马克高场侧的离轴位置时,Ohkawa电流较小,Boozer-Fisch电流能达到较大值;波功率沉积在低场侧的离轴位置时,通过调整波参数,有效抑制Boozer-Fisch电流,能充分利用Ohkawa电流的优势使离轴驱动电流同样能达到较大值。     

用电子回旋加热和电流驱动长脉冲改善TCV托卡马克的中心电子约束

通过用电子回旋加热（ECH）和电流驱动（ECCD）调整电流分布来改善TCV托卡马克的中心电子能量约束。单靠轴上反向ECCD仅以瞬变方式可实现上述目标。用致稳磁流体动力学模的离轴ECH两步步骤和产生平的或反转的电流分布的轴上反向ECCD来获得稳定工况。这种中心温度高达9keV(归一化βN-0.6时）的高约束状态已持续了整个加热脉冲持续时间，或200倍于电子能量约束时间和5倍于电流再分布时间。     

在DⅢ—D上利用离轴电子回旋电流驱动改善电流分布

在DⅢ-D托卡马克上已测得因电子回旋波吸收而产生的局域非感应电流。从利用动态斯塔克效应光谱学测得的内磁场可看到非感应电流的清晰迹象。通过比较有和没有电子回旋波功率的情况下的总放电电流分布与欧姆放电电流分布,估算了非感应电流的大小和位置,在磁轴附近测得的电流与福克-普朗克计算是一致的,但是当电流驱动的位置移到1/2半径处时电流则超过了预计的值。     

EAST上快波电流驱动的数值模拟

针对EAST全超导托卡马克的参数,利用射线追踪法在离子回旋共振频段（ICRF）发射机的工作频段内进行快波电流驱动的数值模拟,找到了一组适合于快波电流驱动的参数。模拟结果表明,发射频率只要避开基频吸收和二次谐频吸收,电流驱动的效果就很明显。     

低混杂电流驱动理论和实验的最新进展

本文简要概述了为未来实验铺平道路的低混杂电流驱动（ＬＨＣＤ）实验里程碑。讨论了电流驱动效率随电子温度的定标。强调了波传播在确定功率沉积分布中的作用,并讨论了控制电流密度分布的方法。报道了用ＬＨＣＤ从实验上获得的负中心剪切位形的模拟。结果发现,模拟结果与实验结果良好一致,因而证明对ＬＨＣＤ理论的了解已达到一定高度。     

A remotely steered millimetre wave launcher for electron cyclotron heating and current drive on ITER

High-power millimetre wave beams employed on ITER for heating and current drive at the 170 GHz electron cyclotron resonance frequency require agile steering and tight focusing of the beams to suppress neoclassical tearing modes. This paper presents experimental validation of the remote steering (RS) concept of the ITER upper port millimetre wave beam launcher. Remote steering at the entrance of the upper port launcher rather than at the plasma side offers advantages in reliability and maintenance of the mechanically vulnerable steering system. A one-to-one scale mock-up consisting of a transmission line, mitre bends, remote steering unit, vacuum window, square corrugated waveguide and front mirror simulates the ITER launcher design configuration. Validation is based on low-power heterodyne measurements of the complex amplitude and phase distribution of the steered Gaussian beam. High-power (400 kW) short pulse (10 ms) operation under vacuum, diagnosed by calorimetry and thermography of the near- and far-field beam patterns, confirms high-power operation, but shows increased power loss attributed to deteriorating input beam quality compared with low-power operation. Polarization measurements show little variation with steering, which is important for effective current drive requiring elliptical polarization for O-mode excitation. Results show that a RS range of up to −12° to +12° can be achieved with acceptable beam quality. These measurements confirm the back-up design of the ITER ECRH&CD launcher with future application for DEMO.     

Electron Cyclotron Harmonic Wave Heating in Tokamak Plasmas with Different Polarization Modes

Electron cyclotron heating on HL-2A has been simulated by TORAY-GA with a second harmonic extraordinary wave and a fundamental ordinary wave. The results show that the wave absorption of the second harmonic extraordinary wave is better than that of the fundamental ordinary wave. In order to understand the interaction mechanism between electrons and the two different polarization modes, the energy exchange between electrons and the two modes are theoretically analyzed, and it is found that the coupling intensity described by the Bessel function and different polarizations of the two modes are the main reasons leading to the above phenomenon. The theoretical results of this study fit well with the simulated and numerical results.     

电子回旋波在非圆截面托卡马克等离子体中的传播与功率沉积

通过求解等离子体平衡方程、波迹方程和准线性Fokker-Planck方程,数值模拟了电子回旋(EC)波在非圆截面托卡马克等离子体中的传播轨迹和功率沉积。模拟结果表明:当EC波从顶部发射时,相比于圆截面的EC波波迹,非圆截面的波迹会向等离子体弱场侧偏移,增大等离子体中心电子密度,波迹也会偏向弱场侧,相应的波功率沉积有所降低;当EC波O模从中平面弱场侧发射时,随着平行折射率的增大,波迹弯曲幅度变大,增大到一定数值时会折回弱场侧穿出,波功率沉积随极向发射角的增大而降低,环向发射角约取10°时,波功率沉积达到最大。     

Varying Electron Cyclotron Resonance Heating on the Levitated Dipole Experiment

Plasmas in the Levitated Dipole Experiment (LDX) are formed and sustained currently via two electron cyclotron resonance heating (ECRH) sources: 2.5 kW at 2.45 GHz and 2.5 kW at 6.4 GHz. An important topic being investigated is how varying the ECRH affects the confinement and stability of the plasma. We report the results of using different operational combinations of our RF sources, such as varying the power composition, changing the power levels, and sequencing of the onset time.     

Electron Cyclotron Heating (ECH) of Tokamak Plasmas

Electron cyclotron heating (ECH) is one of the intense methods of plasma heating, and which utilizes the collisionless electron-cyclotron-resonance-interaction between the launched electromagnetic waves (called electron cyclotron waves) and electrons which are one of the constituents of the high temperature plasmas. Another constituent, namely the ions which are subject to nuclear fusion, are heated indirectly but strongly and instantly (in about 0.1 s) by the collisions with the ECH-heated electrons in the fusion plasmas. The recent progress on the development of high-power and high-frequency millimeter-wave-source enabled the ECH experiments in the middle size tokamaks such as JFT-2M (Japan), Doublet III (USA), T-10 (USSR) etc., and ECH has been demonstrated to be the sure and intense plasma heating method. The ECH attracts much attention for its remarkable capabilities; to produce plasmas (pre-ionization), to heat plasmas, to drive plasma current for the plasma confinement, and recently especially by the localization and the spatial controllability of its heating zone, which is beneficial for the fine controls of the profiles of plasma parameters (temperature, current density etc.), for the control of the magnetohydrodynamic instabilities, or for the optimization/improvement of the plasma confinement characteristics. Here, the present status of the ECH studies on tokamak plasmas are reviewed.     

Evaluation of electron cyclotron current drive performance for CFETR

A number of simulations of electron cyclotron current drive (ECCD) have been carried out for the China Fusion Engineering Test Reactor (CFETR) using the C3PO/LUKE code to investigate the performance and optimize schemes of power injection for the design of the launcher. The operation ranges of the toroidal field, cutoff density, and resonance layer location are given at different source frequencies in CFETR phases I and II. A comparison of ECCD performance between the horizontal and top port launch is presented. ECCD efficiency (r_EC) estimated for CFETR phase I isr_EC=0.21 for top port launch andr_EC=0.20 for horizontal port launch. The ECCD efficiency and second-harmonic absorption is calculated at different wave frequencies (from 170 to 230 GHz) in CFETR phase II. It is found that the highest driven efficiency is obtained at 210 GHz with the toroidal field of 6.5 T, and the second-harmonic absorption increases rapidly with the increase of frequency.     

One-Dimensional Vertical Electron Cyclotron Emission Imaging Diagnostic for HT-7 Tokamak

At the first stage of the electron cyclotron emission imaging （ECEI） diagnostic project on HT-7, a 16-channel vertical-resolved ECEI diagnostic has been developed and installed on HT-7 tokamak to measure electron cyclotron emission with a temporal resolution of 0.5 usec. The system works at a fixed frequency of 97.5 GHz. The sample volumes of the system are aligned vertically with a vertical channel spacing of 11 mm, and can be shifted across the plasma cross-section by varying the toroidal magnetic field. The high spatial resolution of the system is achieved by utilizing a low-cost linear mixer/receiver array and an optical imaging system. The focus location may be shifted horizontally when translating one of the optical imaging elements. The details of the system design and laboratory testing of the ECEI optics are presented together with the preliminary experimental results.     

Suppression of Neoclassical Tearing Modes Towards Stationary High-Beta Plasmas in JT-60U

Results from stabilization of neoclassical tearing modes （NTMs） in JT-60U are described. NTM stabilization and confinement improvement have been demonstrated by employing a real-time NTM stabilization system, where the identification of the location of an NTM and the optimization of the injection angle of the electron cyclotron wave are performed in real time. Also, a high-beta plasma with the normalized beta of 3 has been sustained by suppressing NTM by applying the electron cyclotron current drive （ECCD） before the onset （＇preemptive ECCD＇）. In addition, a simulation code for analysis of the NTM evolution has been developed by combining the modified Rutherford equation with the transport code TOPICS. It is found that the simulation well reproduces the NTM behavior in JT-60U. The simulation also shows that the ECCD width is also important for NTM stabilization, and that the EC wave power for complete stabilization can be reduced by narrowing the ECCD profile.