HL—1装置等离子体粒子平衡的光谱研究

本文描述HL-1装置器壁碳化,观察了碳化前后氢的约束时间和再循环现象,同时还观察了加抽气孔栏条件下粒子约束时间和再循环的变化。实验表明,碳化后氢的再循环增大,使用抽气孔栏可以控制壁附近边缘等离子体的粒子密度,粒子约束时间比不用抽气孔栏增大17.7％,再循环系数减小13.2％。     

Runaway electron generation decrease during a major disruption by limiter biasing in tokamaks

The high-energy current of runaway electrons during a major disruption in tokamak reactors can cause serious damage to the first wall of the reactors and reduce their life time. Therefore, finding a method to minimize runaway electron generation during a major disruption is much needed. Tokamak limiter biasing is one of the methods that can be used for controlling the radial electric field and can induce a transition to an improved confinement state. This paper attempts to examine the effect of limiter biasing on the generation of runaway electrons during a major disruption. To do so, a horizontal biased limiter placed on the tokamak was used. Main parameters such as plasma current, loop voltage, emitted hard X-ray intensity, magnetohydrodynamic (MHD) oscillation and H_α radiation and spectrum of hard X-rays, in the presence and absence of negative and positive limiter biasing, were measured. The results show that the application of limiter biasing during a major disruption can reduce runaway electron generation.     

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在HL-2A装置孔栏位形放电的等离子体实验中,电子回旋辅助加热期间观察到了等离子体约束改善的现象,并对等离子体从低约束模式(L模)向约束改善模式转换时的等离子体线平均电子密度、等离子体储能、分界面内辐射功率、能量约束时间、Hα辐射等进行了研究。同时,分析了电子密度和等离子体辐射功率的空间分布随时间的演化。对改善约束的相关功率(辅助加热、欧姆加热功率和损失功率)进行了分析,并研究了等离子体约束改善转换时的边界净输入功率(阈值)与电子线平均密度和环向磁场的关系。     

HL-2A装置的约束改善和边界净输入功率分析

在HL-2A装置孔栏位形放电的等离子体实验中,电子回旋辅助加热期间观察到了等离子体约束改善的现象,并对等离子体从低约束模式(L模)向约束改善模式转换时的等离子体线平均电子密度、等离子体储能、分界面内辐射功率、能量约束时间、H_α辐射等进行了研究。同时,分析了电子密度和等离子体辐射功率的空间分布随时间的演化。对改善约束的相关功率(辅助加热、欧姆加热功率和损失功率)进行了分析,并研究了等离子体约束改善转换时的边界净输入功率(阈值)与电子线平均密度和环向磁场的关系。     

HL-1装置活动孔栏的表面探针分析

在HL-1装置的活动孔栏上敷设了硅收集探针、高镍钢(GH39,0.3mm)和铝(LFM,0.5mm)材料探针。在首轮物理调试期间的十万余次低温放电清洗和四百余次功率放电辐照后,对孔栏表面进行了弧烧蚀观察和表面探针的SIMS分析,推测出了HL-1装置孔栏刮离层等离子体的平均密度为10~(11)cm~(-3)。     

HL-1装置掠入射真空紫外杂质谱线观测

本文叙述用掠入射谱仪在HL-1装置上所做的真空紫外光谱测量。根据杂质谱线的相对强度变化,说明可动石墨孔栏和蒸钛技术对控制等离子体杂质有一定效果。通过分析谱线、软X射线和m=2模式信号扰动之间的关系,指出杂质对等离子体不稳定性的影响。     

Design and construction of hot limiter biasing system for the tokamak

A hot limiter biasing system with a simplified fast switch circuit was designed, constructed, and installed on the IR-T1 tokamak, and then the negative voltage applied to a hot limiter inserted inside the tokamak fixed limiter and the plasma current, poloidal, and radial components of the magnetic fields, loop voltage, diamagnetic flux, and the ion saturation currents in the absence and presence of the biased limiter were measured. Results of measurements of biasing effects on the plasma equilibrium behavior and edge plasma rotation are compared and discussed.     

HL—1装置偏压电极类H模能量约束时间研究

能量约束时间是衡量环流器等离子体约束性能的重要参数。分析表明，在加偏压电Ｌ模过渡到类Ｈ模的过程中，如果等离子体的辐射损失功率与总损失功率之比显著变化，则扣除辐射损失的能量约束时间的增量是一种更好的衡量约束得到改善的尺度。在这种考虑之下，我们讨论ＨＬ－１等离子体偏压电极Ｌ模－类Ｈ模过的能量约束及电子热传导特性。     

HL-1M装置边缘等离子体结构研究

描述HL-1M装置上几种典型放电中的边缘等离子体物理实验结果.利用马赫/朗缪尔6探针组、静电4探针组、20组三探针阵列研究了低杂波电流驱动、超声分子束注入、多发弹丸注入和中性束注入放电中的粒子约束性能、等离子体旋转和边缘静电雷诺胁强的变化对改善约束的影响.给出了雷诺胁强和极向相速度的关系.结果表明，雷诺胁强的径向变化可以自发产生托卡马克等离子体的剪切极向流.LHCD能使低密度放电的粒子约束增加1至2倍.弹丸注入后，粒子约束时间和极向旋转至少可增加1倍，而SMBI可使粒子约束时间增加约一个数量级并取得高性能等离子体. 关键词： 粒子约束 雷诺胁强 极向流剪切 马赫/朗缪尔6探针组     

Analyses of edge plasma characteristics in HL-2A

The edge plasma characteristics are studied by both a movable array of Mach/Reynolds stress/Langmuir 10-probes in the boundary region and the fixed flush probe arrays on the 4 divertor neutralization plates at the same toroidal cross-section in the HL-2A tokamak. The dependence of the Reynolds stress on poloidal flow in the edge plasma is analysed. The result indicates that the sheared poloidal flow in tokamak plasma can be induced by the radial gradient of Reynolds stress. In the divertor experiments of HL-2A, the profiles of the electron temperature, density and floating potential on divertor plates are measured by the flush probe arrays. The edge electron temperature in divertor configuration is higher than that in limiter configuration. The temperature asymmetry between outer and inner target plates is observed. The result of magnetic surface reconstructed from 18 Mirnov coils signals is presented. Both the particle recycling and the impurity flux in the bulk plasma during divertor discharges are discussed. Neutral gas pressure in divertor chamber, measured by fast ionization gauge during divertor discharge, is given.     

Operation of a tokamak reactor in the radiative improved mode

The operation of a nuclear fusion reactor has been simulated within a model based on experimental results obtained at the TEXTOR-94 tokamak and other facilities in which quasistationary regimes were achieved with long confinement times, high densities, and absence of the edge-localized mode. The radiative improved mode of confinement studied in detail at the TEXTOR-94 tokamak is the most interesting such regime. One of the most important problems of modern tokamaks is the problem of a very high thermal load on a divertor (or a limiter). This problem is quite easily solved in the radiative improved mode. Since a significant fraction of the thermal energy is reemitted by an impurity, the thermal loading is significantly reduced. As the energy confinement time τ_E at high densities in the indicated mode is significantly larger than the time predicted by the scaling of ITERH-98P(y, 2), ignition can be achieved in a facility much smaller than the ITER facility at plasma temperatures below 20 keV. The revealed decrease in the degradation of the confinement time τ_E with an increase in the introduced power has been analyzed.     

One-Dimensional Transport Code Modeling of the Divertor-Limiter Region in Tokamaks

A model of the divertor-limiter scrapeoff region has been incorporated into the BALDUR one-dimensional tokamak transport code. Simulations of the proposed Toroidal Fusion Test Reactor (TFTR), and Poloidal Divertor (PDX) experiments and existing Alcator-A tokamak experiments have been carried out for ohmic and neutral beam heated cases. In particular, we have studied how the edge conditions and energy-loss mechanisms in PDX depend upon plasma density, and compared our results with analytic estimates. The sensitivity of the results to changes in the transport coefficients and scrapeoff model is discussed with particular reference to the power loading on the TFTR limiter.     

HL-2M 装置限制器系统设计及工艺研究

HL-2M 装置设计有 8 套固定极向限制器和 1 套活动极向限制器,其主要功能是进一步加强保护真空 室及其内部件,同时活动限制器还将提供不同孔栏位形用于等离子体物理实验。根据 HL-2M 装置总体运行需求, 活动限制器结构设计可移动有效距离为 120mm,活动限制器移动精度可控制在±0.1mm 以内。基于激光跟踪仪测 量方法对 HL-2M 装置限制器系统完成了高精度的安装,限制器的面向等离子体关键位置安装精度优于±0.5mm, 通过初始等离子体放电实验表明其运行状态均正常。      

HL-1M装置逃逸电子的定标律

使用一维数值模型, 推断了逃逸能量ε_r与逃逸约束时间τ_r的关系。模拟结果给出能量ε_r 和放电参数的定标律。在HL- 1M 装置中不同实验条件下测量了硬X 射线谱, 研究了逃逸电子能量 ε_r模拟的定标律, 并推导出HL- 1M 装置放电的逃逸电子的约束时间与逃逸电子扩散系数。     

Design and fabrication of emissive biased limiter and its effect on tokamak plasma

In this paper, an emissive-biased limiter (EBL) was designed and fabricated then the magneto hydrodynamic activity was investigated based on Mirnov oscillations and hard X-ray spectroscopy through the tokamak plasma biasing. The EBL is positioned at r/a=0.92, and the biased voltage, which is varied from?250 to 250 V, applied between the head of the emissive limiter and vacuum chamber. Furthermore, the effects of the biased limiter for both negative and positive applied voltages are measured, and the results are compared with cold-biased limiter. As the results of IR-T1 tokamak suggest, in emissive negative polarity, the duration of plasma current is increased, compared with no bias, cold positive and emissive positive polarities. The amplitude of Mirnov fluctuations in emissive negative polarity is larger and more regular, compared with emissive positive polarity. The amplitude of the hard X-ray fluctuation in emissive negative polarity is very low compared with cold negative, cold positive and emissive positive polarities which leads to minimum energy loss.     

The structure of chaotic magnetic field lines in a tokamak withexternal nonsymmetric magnetic perturbations

We consider the effects of external nonsymmetric magnetostatic perturbations caused by resonant helical windings and a chaotic magnetic limiter on the plasma confined in a tokamak. The main purpose of both types of perturbation is to create a region in which field lines are chaotic in the Lagrangian sense: two initially nearby field lines diverge exponentially through many turns around the tokamak. The equilibrium field is obtained from the equations of magneto-hydrodynamic equilibrium written down in a polar toroidal coordinate system. The magnetic fields generated by the resonant helical windings and the chaotic magnetic limiter are obtained through an analytical solution of Laplace equation. The magnetic field line equations are integrated to give a Hamiltonian mapping of field lines that we use to characterize the structure of chaotic field lines. In the case of resonant windings, we obtained the map by both numerical integration and a Hamiltonian formulation. For a chaotic limiter, we analytically derived a symplectic map by using a Hamiltonian formulation     

HL-1托卡马克放电辐照的因科镍和铝的表面效应研究

核聚变能是最有希望的一种新能源,我国自行设计与建造的核聚变装置——HL-1已于1985年投入运行。研究核聚变装置中等离子体与器壁、孔栏材料相互作用日益受到广泛重视,因为这种反应造成等离子体的污染及聚变装置材料灼损坏。同时,这一研究还将提供等离子体边界层的性能参数,为下一代装置的器壁材料选择和结构设计提供参考。本文研究了镍基合金和铝探针在HL-1装置的等离子体括削层内,经等离子体辐照后的表面形貌及表面组分的变化。     

Edge Turbulence During Limiter Biasing Experiments in the TJ-II Stellarator

The influence of limiter biasing on plasma confinement, turbulence and plasma flows has been investigated in the TJ-II stellarator. Experimental results show that it is possible to modify global particle confinement and edge plasma parameters with both positive and negative biasing. Significant and minor modifications in the structure of plasma fluctuations have been observed during the transition to improved confinement regimes induced by limiter biasing. These results show evidence of electric field induced improved confinement via multiple mechanisms. The investigation of the relaxation of plasma potential and electric fields shows evidence of two different characteristic decay times.     

HL-1装置等离子体平衡的实验研究

用对称磁探针测量了HL-1装置等离子体环的水平位移和垂直位移,经微机数据处理系统即时给出了位移随时间的变化曲线,并对装置的杂散场情况作了讨论。实验表明,平衡场和杂散垂直场的合成场能保证等离子体平衡在孔栏中心附近的位置。     

Diffusive Losses and Scaling Law for Large Tokamaks

Under plasma conditions aimed for in the next generation of tokamak devices, it is necessary to consider a multi-parameter model for diffusive energy losses which would limit the temperatures and confinement times attainable. In this paper, we study a model for plasma diffusion in a reactor size tokamak considering various plasma parameters (like density, temperature, spatial gradients, collisional effects, etc.) and also topological elements of the magnetic configuration (like magnetic shear, magnetic curvature, etc.).