HL-2A装置偏滤器位形研究

1研究方法 等离子体边界是托卡马克平衡运行时等离子体截面的极向磁通函数的等高线，它决定等离子体位形。位形是托卡马克装置实验和工程设计的重要参数，它是由等离子体电流及其分布以及外极向场线圈电流配置共同决定的。     

场反向等离子体排除磁通量的测量

场反向位形是紧凑环位形中比较好的一种磁约束位形。等离子体完全由极向磁场约束(没有环向场)。实验证明,场反向位形可以长时间稳定地约束等离子体。它具有环形系统的约束特点,又具有开端系统的简单性。目前已成为研究磁约束等离子体的重要课题之一。 在场反向位形实验中,一个简单而重要的诊断工具就是用差分磁环探针,用以测量场反向位形等离子体所排除的磁通量。等离子体的一般行为可以通过测量排除磁通量数据得到。     

用初-边值方法研究具有固定边界的等离子体Kink不稳定性

本文解出了具有固定边界的平衡等离子体磁面方程的解析解和数值解。用简化的Lax-Wendroff方法求出了压力、速度和磁场的扰动值。得到了线性增长率、平均β和平均β_p以及安全因子。我们发现:1.具有凹向电流剖面的等离子体比具有均匀电流剖面的等离子体更稳定,而具有凸向电流剖面的等离子体是最不稳定的;2.具有逆磁电流的等离子体比具有顺磁电流的等离子体更稳定。 关键词：     

HL-2M 装置磁测量系统设计及初始放电实验结果

介绍了 HL-2M 装置上满足等离子体放电的磁测量系统的物理设计,主要包括磁探针、磁通环以及 电流测量系统的设计。通过 HL-2M 装置典型的放电位形参数对磁探针的极向布局、有效面积,磁通环的极向布 局以及测量等离子体电流的罗氏圈互感值进行了初步设计。目前,HL-2M 装置已经完成初始等离子体放电。各个 子系统均能达到其测量目标。      

平衡电流位形对电阻壁模稳定性影响的数值模拟

数值研究平衡电流位形对电阻壁模式稳定性的影响.研究发现,对于不同的电流位形,当等离子体边缘处安全因子一定时,最不稳定的电阻壁模的环向模数和极向模数相同.在同一壁位置下,非均匀电流位形驱动的电阻壁模的线性增长率比均匀电流位驱动的电阻壁模的线性增长率大.等离子体速度流在不同的初始电流位形下对电阻壁模稳定性的影响不同.由于磁力线在壁上的挤压,经过线性演化后,电阻壁模进入非线性演化并达到饱和状态,非均匀电流位形下的扰动磁能比均匀电流位形下的扰动磁能饱和度低.     

KTX反场箍缩装置中等离子体小破裂现象研究

在科大反场箍缩磁约束实验装置(KTX)实验中，观测并研究等离子体的显著位移及其带来的小破裂现象。通过分析H_α 谱线、软X 射线辐射以及磁探针数据，发现其主要特征是破裂前等离子体电流重心的缓慢外移，在小破裂后等离子体电流重心在百微秒时间迅速反向移动，重新达到稳定位形。同时，等离子体小破裂伴随着m=1 的边界磁场扰动、稳定壳上显著变化的涡流、以及H_α 谱线和软X 射线辐射的增强。通过对KTX 小破裂实验数据的分析与统计，得出回弹位移与等离子体位移成线性关系。对等离子体电流分布及稳定壳涡流，建立了唯象电路模型，得出了和实验相一致的结论，确定了稳定壳上快速变化的涡流是等离子体小破裂后回复平衡的重要因素。     

由磁测量确定环流器等离子体截面形状的方法

一、引言在环流器实验中,等离子体柱截面形状和位置是位形基本参数。尤其对非圆截面和放电期间截面变化的装置,为调节、控制成形、分析等离子体内外电流分布变化引起的位形和稳定性改变,边界磁面形状位置是不可缺少的信息。本文用给定极向磁场,由拟合计算的方法来确定等离子体边界。     

EAST低混杂波功率沉积和电流驱动剖面控制的数值模拟

对原有的低混杂波电流驱动模拟程序进行改进,使之能够研究EAST上如何控制低混杂波功率沉积和电流驱动分布.在EAST非圆截面的平衡位形下,应用改进后的程序详细计算不同低混杂波功率谱、等离子体密度和温度分布对低混杂波功率沉积位置和电流驱动剖面分布的影响.通过计算发现,选取合适的低混杂波功率谱,等离子体温度分布和密度分布可以对功率沉积位置和电流驱动分布的剖面进行控制;调节等离子体温度分布可以很好的控制低混杂波近轴电流驱动分布和离轴电流驱动分布.     

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欧姆驱动条件下,托卡马克等离子体中的电流由欧姆驱动电流和等离子体内部的自恰电流构成。在简单的Spitzer电阻率模型下,欧姆驱动的环向电流密度剖面,主要由每一时刻的电子温度剖面和有效电荷数Zeff的剖面决定。讨论并给出了确定了平衡位形的基本方程,在大环径比近似下,给出了存在锯齿振荡条件下的环向电流剖面和小的非圆变形的平衡解。     

HL—2A装置LHCD的运行区域与驱动电流分布控制

本文利用低杂波电流驱动（LHCD）的理论和实验结果,讨论了电流驱动效率和电流分布控制与等离子体参量及入射波谱的关系,强调了波传播在确定功率沉积分布区域中的作用,并讨论了控制电流密度分布的方法,探索在HL－2A装置上实现中心负磁剪切位形的可能性。     

Evidence for separatrix formation and sustainment with steady inductive helicity injection

The first sustainment of toroidal plasma current of 50 kA at up to 3 times the injected currents, added in quadrature, using steady inductive helicity injection is described. Separatrix currents-currents not linking the helicity injectors-are sustained up to 40 kA. Decreases in the n=1 toroidal mode of the poloidal magnetic field at higher current amplifications indicate more quiescent, direct toroidal current drive. Results are achieved in HIT-SI (with a spheromak of major radius 0.3 m) during deuterium operations immediately after helium operation. These results represent a breakthrough in the development of this new current drive method for magnetic confinement fusion.     

CT-6托卡马克研究(Ⅰ)——实验装置的研制和调试

托卡马克是一种产生高温环形等离子体的聚变实验装置,也是一类复杂的现代化的电物理装备。CT-6是我国首先投入运行的小型托卡马克装置,其主要参数为:大半径45cm;小半径9.2cm;环向磁场2TL;等离子电流30kA;经过调试阶段,达到了预期目标,产生了平衡、稳定的电子温度为250eV左右的环形高温等离子体。CT-6由电磁系统(包括环向场、涡旋场、平衡场)、超高真空系统(包括环形真空室和抽气机组)、电源控制系统和诊断测量系统等部份组成,它是由中国科学院物理研究所、电工研究所及其他许多单位协作研制成功的。本文描述CT-6装置的设计、结构、工程研制和调试过程,以及有关的试验结果。 关键词：     

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：     

托卡马克等离子体不同平衡位形下的电子回旋波电流驱动

在给定的等离子体总电流和中心电流密度条件下,数值求解平衡方程,求出不同拉长比和三角形变因子的托卡马克等离子体温度、密度、磁场分布,然后通过求解波迹方程和Fokker-Planck方程,分别计算这些位形下的电子回旋波波迹和电流驱动.结果表明：电子回旋波X模从顶部发射时,随着拉长比的增大,波迹会向弱场侧偏移.电子回旋波X模从弱场侧发射时,电子回旋波在等离子体中传播沉积的功率份额随着拉长比的增大而增加,驱动电流位置随着三角形变因子的增大向等离子体中心移动.驱动电流位置随环向和极向发射角的减小向中心移动,对应的电流密度峰值也变大.     

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.     

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.     

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.     

Initial Measurements of Plasma Potential in the Core of the MST Reversed Field Pinch with a Heavy Ion Beam Probe

Measurement of the plasma potential in the core of MST marks both the first interior potential measurements in an RFP, as well as the first measurements by a Heavy Ion Beam Probe (HIBP) in an RFP. The HIBP has operated with (20-110) keV sodium beams in plasmas with toroidal currents of (200-480) kA over a wide range of densities and magnetic equilibrium conditions. A positive plasma potential is measured in the core, consistent with the expectation of rapid electron transport by magnetic fluctuations and the formation of an outwardly directed ambipolar radial electric field. Comparison between the radial electric field and plasma flow is underway to determine the extent to which equilibrium flow is governed by E×B. Measurements of potential and density fluctuations are also in progress.Unlike HIBP applications in tokamak plasmas, the beam trajectories in MST (RFP) are both three-dimensional and temporally dynamic with magnetic equilibrium changes associated with sawteeth. This complication offers new opportunity for magnetic measurements via the Heavy Ion Beam Probe (HIBP). The ion orbit trajectories are included in a Grad-Shafranov toroidal equilibrium reconstruction, helping to measure the internal magnetic field and current profiles. Such reconstructions are essential to identifying the beam sample volume locations, and they are vital in MST's mission to suppress MHD tearing modes using current profile control techniques. Measurement of the electric field may be accomplished by combining single point measurements from multiple discharges, or by varying the injection angle of the beam during single discharges.The application of an HIBP on MST has posed challenges resulting in additional diagnostic advances. The requirement to keep ports small to avoid introducing magnetic field perturbations has led to the design and successful implementation of cross-over sweep systems. High levels of ultraviolet radiation are driving alternative methods of sweep plate operation. While, substantial levels of plasma flux into the HIBP diagnostic chambers has led to the use of magnetic plasma suppression.     

Experimental evidence of momentum transport induced by an up-down asymmetric magnetic equilibrium in toroidal plasmas

The first experimental evidence of parallel momentum transport generated by the up-down asymmetry of a toroidal plasma is reported. The experiments, conducted in the Tokamak à Configuration Variable, were motivated by the recent theoretical discovery of ion-scale turbulent momentum transport induced by an up-down asymmetry in the magnetic equilibrium. The toroidal rotation gradient is observed to depend on the asymmetry in the outer part of the plasma leading to a variation of the central rotation by a factor of 1.5-2. The direction of the effect and its magnitude are in agreement with theoretical predictions for the eight possible combinations of plasma asymmetry, current, and magnetic field.     

The effect of toroidal field on the rotating magnetic field current drive in rotamak plasmas

A rotamak is one kind of compact spherically shaped magnetic-confinement device. In a rotamak the plasma current is driven by means of rotating magnetic field （RMF）. The driven current can reverse the original equilibrium field and generate a field-reversed-configuration. In a conventional rotamak, a toroidal field （TF） is not necessary for the RMF to drive plasma current, but it was found that the present of an additional TF can influence the RMF current drive. In this paper the effect of TF on the RMF current drive in a rotamak are investigated in some detail. The experimental results show that addition of TF increases the RMF driven current greatly and enhances the RMF penetration dramatically. Without TF, the RMF can only penetrate into plasma in the edge region. When a TF is added, the RMF can reach almost the whole plasma region. This is an optimal strength of toroidal magnetic field for getting maximum plasma current when Bv and radio frequency generator power are fixed. Besides driving current, the RMF generates high harmonic fields in rotamak plasma. The effect of TF on the harmonic field spectra are also reported.[第一段]