SWIP—PFP装置反场箍缩位形研究

ＳＷＩＰ－ＲＦＰ装置是具有金属真空室的环形反场箍缩（ＲＦＰ）装置。在初始气压，初始环场，可控辅助反场和等离子体自反效应的不同情况下，做了反场建立条件的实验。在有自反效应和可控辅助反场时间配合的三种运动情况下，反场箍缩放电已实现。本文给出了反场箍缩位形实验预测的结果，实验测出反场箍缩位形的等离子体电幅值，脉冲长度与相关因素的依赖关系。实验结果表明在无功率短路情况下，等离子体存在时间τｐ≥０．３ｍｓ。     

SWIP—RFP装置反场箍缩等离子体约束改善实验

在ＳＷＩＰ－ＲＦＰ装置上改善真空和预电离条件后，提高了等离子体温度，增加了等离子体的维持时间和反场箍缩磁场位形约束的维持时间，增长了等离子体的能量约束时间，从而表明了ＲＦＰ等离子体的能量约束和ＲＦＰ磁场位形的约束均得到了改善。     

沿极小势能轨迹从q〉1至q〈1位形演变

本文给出了沿极小势能轨迹从类托卡马克至反场箍缩(RFP)的演变。在反场箍缩条件下可允许用强等离子体电流充分加热等离子体到点火温度,而不需要辅助的中性束或射频加热系统。     

场反向位形中等离子体的动力箍缩

本文给出了一组动力箍缩方程,它描述了场反向位形中等离子体的动力箍缩和加热。数值结果有可能为进一步开展实验提供理论依据。     

SWIP—RFP装置慢斜升放电的反场箍缩实验

在硅化后的良好器壁条件下，采用慢斜升放电模式，获得了具有高电流密度和较高温度的反场箍缩（ＲＦＰ）等离子体，在实验中观测到磁通长时间的持续增长，随等离子体电流增大而增大，并出现与环向磁通相伴的ＭＨＤ扰动现象，实验证实，斜升放电的ＲＦＰ等离子体存在“发电机”效应，ＲＦＰ位形维持时间长达８００μｓ，等离子体电流约１００ｋＡ，电子和离子温度分别达到７０ｅＶ和８５ｅＶ。     

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。     

增长反场装置位形维持时间的实验研究

在预电离、空芯变压器功率续流、真空室放电清洗、碳化和蒸钛条件下，得到反场箍缩（ＲＦＰ）和超低安全因子（ＵＬＱ）的实验结果。等离子体性质改善，等离子体电流出现平顶，其幅值增加。杂质被有效控制，等离子体温度增高。     

环形反场箍缩平衡和稳定

在环形坐标系中,求出了反场箍缩平衡方程的解析解,并验证了Suydam条件和充分稳定性判据。这些数值结果与HBTXI和TPE-IR(M)的实验结果一致。     

基于箍缩装置的高能量密度物理实验研究进展

基于脉冲功率技术的箍缩装置能够在cm空间尺度和百ns时间尺度产生极端的高温、高压、高密度以及强辐射环境。中物院流体物理研究所在已建成的10 MA级的大型箍缩装置上开展多种负载构型的高能量密度物理实验研究。利用Z箍缩动态黑腔创造出了惯性约束聚变研究所需的高温辐射场;研究了金属箔套筒和固体套筒的内爆动力学特性;利用中低Z材料内爆获得了可观的K壳层线辐射并用于X射线热-力学效应实验研究;磁驱动准等熵加载和冲击加载为材料动态特性研究提供了新的实验能力;采用环形二极管和反射三极管技术的轫致辐射源获得了高剂量（率）的X射线和γ射线;利用磁驱动的径向金属箔模拟了天体物理中恒星射流的形成及其辐射的产生。此外,还介绍了利用反场构型磁化靶聚变装置开展的预加热磁化等离子体靶形成等实验结果。     

箍缩背光照相

 利用PPG-Ⅰ脉冲功率装置（500 kV,400 kA,100 ns）驱动X箍缩负载,得到了μm量级的亚纳秒脉冲X射线辐射点源。在阴阳极轴线和回流柱上同时安装X箍缩负载,前者可作为背光照相的X射线点源;后者可作为被拍照的目标X箍缩。获得了X箍缩发展过程不同时刻的时间序列图像,在背光照相的图像中可以清晰观察到X箍缩交叉点处等离子体的外爆、箍缩以及最终的崩溃阶段。将阴阳极轴线上的X箍缩负载用Z箍缩丝阵负载代替,实现了对丝阵负载Z箍缩放电起始阶段的X射线背光照相,观察到了最初的各单丝电爆炸、等离子体膨胀及融合过程,同时观察到了双丝Z箍缩发展过程中的等离子体不稳定性。实验结果有助于深入理解Z箍缩发展的物理过程,同时可为有效的模拟建模分析提供基本的实验数据。     

Self-reversal phenomena of toroidal current by reversing the external toroidal field in helicity-driven toroidal plasmas

In order to understand self-organization in helicity-driven systems, we have investigated the dynamics of low-aspect-ratio toroidal plasmas by decreasing the external toroidal field and reversing its sign in time. Consequently, we have discovered that the helicity-driven toroidal plasma relaxes towards the flipped state. Surprisingly, it has been observed that not only toroidal flux but also poloidal flux reverses sign spontaneously during the relaxation process. The self-reversal of the magnetic fields is attributed to the nonlinear growth of the n=1 kink instability of the central open flux.     

Experimental Studies on the Sustainment of Splieromak Plasmas by an Inductive Drive of the Toroidal Current

Sustainment of spheromak plasmas produced in an external equilibrium field has been demonstrated with a center current transformer (ohmic heating (OH) coil) which is used to inductively drive the toroidal current of the plasma. The OH coil is covered by a cylindrical metal liner. It provides the stability against the tilt and shift motions of spheromaks at the expense of the simple connection of its geometry. Since the spheromak is characterized by the elimination of external toroidal fields in association with nonconservation of a toroidal flux during magnetic relaxation, the metal liner was made electrically disconnected from the main vacuum vessel (spheromak mode). In the experiments, existense of the dynamo effect, meaning automatic generation of toroidal flux similar to that of a reversed field pinch (RFP), is observed. Measured MHD activity consists of multihelicity helical modes with toroidal mode numbers N = 1-3. In order to investigate the difference between spheromaks and RFP's in the MHD activity during sustainment, experiments have also been made with the metal liner of the OH coil connected with the vessel (RFP mode). The dynamics of the MHD activities observed are compared with those obtained from the three-dimensional MHD simulations by Katayama and Katsurai [18], and their implication in the dynamo effect is discussed.     

Effects of three-dimensional electromagnetic structures on resistive-wall-mode stability of reversed field pinches

In this Letter, the linear stability of the resistive wall modes (RWMs) in toroidal geometry for a reversed field pinch (RFP) plasma is studied. Three computational models are used: the cylindrical code ETAW, the toroidal MHD code MARS-F, and the CarMa code, able to take fully into account the effects of a three-dimensional conducting structure which mimics the real shell geometry of a reversed field pinch experimental device. The computed mode growth rates generally agree with experimental data. The toroidal effects and the three-dimensional features of the shell, like gaps, allow a novel interpretation of the RWM spectrum in RFP's and remove its degeneracy. This shows the importance of making accurate modeling of conductors for the RWM predictions also in future devices such as ITER.     

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：     

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.     

OHTE: A Helical Pinch with Pitch Reversal

The OHTE configuration is obtained by surrounding a reversed field pinch (RFP) with a stellarator-like helical winding whose pitch is chosen to enhance field line pitch reversal. The helical coil current needed to form a separatrix boundary is calculated analytically for a simple plasma model, which gives results in close agreement with a numerical two-dimensional (2-D) MHD equilibrium code. Basic properties of the field line transform, which is predominantly in the axial or toroidal direction, are investigated. The 2-D equilibrium code is used to investigate the effects of current profiles and high beta, and the OHTE is compared with the RFP. These calculations show that the helical winding can significantly enlarge the parameter space for interchangestable finite-? equilibria with pitch reversal while avoiding axial current reversal.     

托卡马克中等离子体柱的位移稳定性

本文考虑托卡马克中纵场的作用以及等离子体柱和与之有互感的外迴路的相互作用,在圆截面,瘦环假设下,得到了自由运动时相对于沿水平方向、垂直方向的位移,以及小半径变化的一般稳定条件。由于强纵场的影响,一般来说,等离子体柱的小半径总是随着大半径的变化而改变,以维持通过等离子体角向电流迴路的磁通不变。对于这种扰动,当考虑到外迴路电流变化以后,稳定区域超过公式0关键词：     

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.     

Toroidal plasma rotation induced by the dynamic ergodic divertor in the TEXTOR tokamak

The first results of the Dynamic Ergodic Divertor in TEXTOR, when operating in the m/n=3/1 mode configuration, are presented. The deeply penetrating external magnetic field perturbation of this configuration increases the toroidal plasma rotation. Staying below the excitation threshold for the m/n=2/1 tearing mode, this toroidal rotation is always in the direction of the plasma current, even if the toroidal projection of the rotating magnetic field perturbation is in the opposite direction. The observed toroidal rotation direction is consistent with a radial electric field, generated by an enhanced electron transport in the ergodic layers near the resonances of the perturbation. This is an effect different from theoretical predictions, which assume a direct coupling between rotating perturbation and plasma to be the dominant effect of momentum transfer.