磁螺度(helicity)注入电流驱动实验的平衡反演

磁螺度注入是一种国际上正处于探索性研究阶段的极富吸收力的电汉驱动方案,尤其对于球环堆芯更具有至和关重要的意义。对磁螺度注入电流驱动实验进行平衡反演工作,将实验数据进行理论分析研究,拟合所有的测量数据以确立实际的等离子体位形,平衡的磁拓扑结构以及环向电流的空间分布,从而确定闭合橛面区的驱动电流大小以及等离子体的性质,计算结果表明等离子体具有托卡马克型ｑ分布,环向电汉分布呈中空形,磁面结构为有三角形变     

Oscillating-field current-drive experiments in a reversed field pinch

Oscillating-field current drive (OFCD) is a steady-state magnetic helicity injection method to drive net toroidal current in a plasma by applying oscillating poloidal and toroidal loop voltages. OFCD is added to standard toroidal induction to produce about 10% of the total current in the Madison symmetric torus. The dependence of the added current on the phase between the two applied voltages is measured. Maximum current does not occur at the phase of the maximum helicity injection rate. Effects of OFCD on magnetic fluctuations and dissipated power are shown.     

Spheromak formation by steady inductive helicity injection

A spheromak is formed for the first time using a new steady state inductive helicity injection method. Using two inductive injectors with odd symmetry and oscillating at 5.8 kHz, a steady state spheromak with even symmetry is formed and sustained through nonlinear relaxation. A spheromak with about 13 kA of toroidal current is formed and sustained using about 3 MW of power. This is a much lower power threshold for spheromak production than required for electrode-based helicity injection. Internal magnetic probe data, including oscillations driven by the injectors, agree with the plasma being in the Taylor state. The agreement is remarkable considering the only fitting parameter is the amplitude of the spheromak component of the state.     

J-TEXT装置纵场电源系统及其调试

J-TEXT装置的纵场磁体是由十六个近似圆形的常规铜线圈串联而成。纵场电源系统需要为纵场磁体提供最大电流为160kA、平顶时间为500ms的准梯形电流波形,以在等离子体中心产生最大为3T的磁场。基于原TEXT-U纵场电源的电路结构,重新设计和改造了电源的控制系统和保护系统。目前,纵场电源系统已经通过了测试,在J-TEXT装置首轮放电运行中,该系统可输出92.5kA的平顶电流,在等离子体中心产生了约1.74T的磁场。     

Generation of noninductive current by electron-Bernstein waves on the COMPASS-D Tokamak

Electron-Bernstein waves (EBW) were excited in the plasma by mode converted extraordinary (X) waves launched from the high field side of the COMPASS-D tokamak at different toroidal angles. It has been found experimentally that X-mode injection perpendicular to the magnetic field provides maximum heating efficiency. Noninductive currents of up to 100 kA were found to be driven by the EBW mode with countercurrent drive. These results are consistent with ray tracing and quasilinear Fokker-Planck simulations.     

HL-1装置的物理调试(1985)

自1985年4月起正式开展HL-1装置的物理调试,其目的是获得平衡、稳定和比较干净的等离子体,并在此基础上开展初步的物理实验研究。在纵向磁场2.3T下获得等离子体电流135kA,平顶时间150-200ms。等离子体电流的持续时间出乎意料地长达1s,其详细的物理原因尚待深入研究。其它等离子体参数的初步结果为n_e≈ 2.8×10~(13)cm~(-3),T_e≈350-500eV,τ_E≈10ms。     

Radial transport and electron-cyclotron-current drive in the TCV and DIII-D tokamaks

Calculation of electron-cyclotron-current drive (ECCD) with the comprehensive CQL3D Fokker-Planck code for a TCV tokamak shot gives 550 kA of driven toroidal current, in marked disagreement with the 100-kA experimental value. Published ECCD efficiencies calculated with CQL3D in the much larger, higher-confinement DIII-D tokamak are in excellent agreement with experiment. The disagreement is resolved by including in the calculations electrostatic-type radial transport at levels given by global energy confinement in tokamaks. The radial transport of energy and toroidal current are in agreement.     

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基于QNX实时操作系统的IDE编译平台,设计开发了J-TEXT装置纵场电源的实时控制系统。该系统具有良好的实时性、可靠性和稳定性,成功控制纵场电源产生了92.5kA、平顶时间为1s的准梯形脉冲电流,在等离子体中心产生1.74T的磁场,满足了J-TEXT装置目前放电实验的需要。     

HL-1装置主机的工程调试

本文叙述了HL-1装置主机在工程调试和等离子体放电中所涉及的主要技术问题。文中详述了场形和变压器芯柱伏秒数的一些测量结果,并阐述了主机的工作状况和一些技术性能。目前该装置已运行于B_t=2.3T,I_p=135kA参数下,运行情况表明:HL-1装置主机有着较好的技术性能,基本上满足物理实验的要求。     

Flux conversion and evidence of relaxation in a high-beta plasma formed by high-speed injection into a mirror confinement structure

High-beta plasmoids can survive the violent dynamics of supersonic reflection off mirror structures, producing a stable high-beta field-reversed configuration (FRC). This shows both the robustness of FRCs and their tendency to assume a preferred plasma state, possibly conforming to a relaxation principle. The key observations are (1) approximate preservation of the magnetic helicity, (2) substantial conversion from toroidal to poloidal magnetic flux, (3) substantial toroidal flow, and (4) a high-beta quiescent final state. These results are from the Translation, Confinement, and Sustainment experiment where a disorganized plasmoid is injected at super-Alfvenic speed into a confinement chamber. After successive reflections from end mirrors, the plasmoid settled into a near-FRC state with high beta and low toroidal magnetic field. The flux conversion and helicity preservation are inferred by an interpretive model.     

Current clamp at zero level in JT-60U current hole plasmas

It is found that no current is driven in a central region of a tokamak plasma once the central current density becomes nearly zero ("current hole"), in spite of high electric conductivity, at the current drive by a toroidal electric field and a radio-frequency wave in experiments on the JT-60U tokamak. This is a new, stiff, self-organized structure of a magnetic field in an axisymmetric toroidal plasma.     

爆磁压缩装置经组合功率调节系统产生高电压的实验研究

 介绍了以爆磁压缩装置为脉冲功率能源,经变压器和爆炸金属丝断路开关组合功率调节系统,在电阻负载上产生高电压的实验研究。实验结果为：在100W 水电阻负载两端得到了约800kV的高电压脉冲,脉宽约100ns。此项工作拓宽了爆磁压缩装置的应用范围。     

利用环向电场提升等离子体电流以改善约束状态

利用一个小的环向涡旋脉冲电场（４．４Ｖ／ｍ，０．４５ｍｓ）成功地将ＨＴ－６Ｍ托卡马克等离子体电流从第一平顶（５５ｋＡ）提升到６０ｋＡ的第二平顶。其电流上升率大于１２ＭＡ／ｓ，电流上升时间远小于经典趋肤时间，实验中观察到了标志等离子体约束改善的明显物理现象。等离子体电流提升后，粒子约束时间提高了２．１倍，能量约束时间提高了１．６倍。 关键词：     

Demonstration of plasma startup by coaxial helicity injection

The first successful results on the transfer of a coaxial helicity injection (CHI) produced discharge to inductive operation are reported. CHI-assisted plasma startup is more robust than inductive only operation. After hand off for inductive operation, the initial 90 kA of CHI-produced current drops to 40 kA, then ramps up to 170 kA, using only 30 mV s, more than 30% higher than that produced by induction alone. These significant performance enhancing results were obtained on the HIT-II spherical torus experiment (major/minor radius of 0.3/0.2 m).     

HL-2M 环向场线圈水冷数值模拟与分析

建立了环向场线圈的水冷计算模型,根据热传导和对流换热方程进行了数值模拟分析。计算结果表明：指形接头与铜板的界面接触热阻和接触电阻对指形接头的温升影响较大,但在平顶电流为140kA 及其电流平顶7s 时,由焦耳热引起的最高温升40℃以下,故环向场线圈的温度均不会超过80℃,且15min 后TF 线圈温度均降至30℃以下。在平顶电流为190kA 时,线圈通电持续时间可根据界面实测接触热阻、接触电阻以及线圈初始温度来确定。     

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The water-cooled model of the toroidal field coils was established calculated according to the heat conduction and the convective heat transfer equation. The results show that the thermal contact resistance and the electrical contact resistance of the interface between the finger joint and the copper plate had a larger effect on the temperature rise of the finger joint. At maximum current of 140kA and the current flattop 7s, the maximum temperature rise of the toroidal coils with the finger joint was below 40??, so the maximum temperature of the coils wouldn’t exceed 80??, and the temperature of the toroidal field was below 30?? after an interval of 15min. However, at maximum current of 190kA, the current flattop time was determined by the thermal contact resistance, the electrical contact resistance and initial temperature.     

HL-2M 装置环向场线圈的工程研制与调试

介绍了 HL-2M 装置环向场(TF)线圈的工程设计、关键制造工艺及其调试结果。目前，TF 线圈最大通电电流达到 42kA，对应 TF 线圈产生的磁场为 0.66T，满足 HL-2M 装置初始放电需求。      

Current drive for rotamak plasmas

Experiments which have been undertaken over a number of years have shown that a rotating magnetic field can drive a significant non-linear Hall current in a plasma. Successful experiments of this concept have been made with a device called rotamak. In its original configuration this device was a field reversed configuration without a toroidal magnetic field but with a vertical field to establish the MHD equilibrium. However, modifications have shown that current can also be driven if a central current-carrying rod is used to provide an applied toroidal field. The new rotamak has then a spherical tokamak magnetic field structure. Article presented at the International Conference on the Frontiers of Plasma Physics and Technology, 9–14 December 2002, Bangalore, India.     

Enhanced confinement and quasi-single-helicity regimes induced by poloidal current drive

Enhanced confinement regimes with quasihelical symmetry are reproducibly obtained in the modified reversed field pinch eXperiment (RFX)-mod by reducing the level of internal chaos through the combination of a smooth magnetic boundary (through a virtual shell scheme) and the oscillating poloidal current drive technique. The plasma moves from a chaotic multiple helicity towards a quasi-single-helicity regime with a magnetic island showing high temperature and soft x-ray emissivity. The chaos reduction involves also the plasma outside the island allowing for a global enhanced confinement with an improvement up to 50%.     

Injection of Intense Relativistic Electron Beams into a Toroidal Geometry

Two experimentally verified methods are presented for the injection of high-current relativistic electron beams (30 kA, 400 kV) into strong toroidal magnetic fields (1-8 kGauss). Injection is accomplished by contouring the current flow in the stalk of a field-emission cathode to perturb the flux lines only during beam generation. On conclusion of the emission process the perturbed lines can return to their original positions thereby trapping the beam.