托卡马克高约束运行模式和磁约束受控核聚变

磁约束受控核聚变是最终解决人类能源问题的有希望的途径之一.托卡马克的高约束运行模式可以大大降低下一代磁约束聚变实验装置和将来的聚变示范反应堆的规模和造价.文章简要介绍了托卡马克高约束模式的特征,实现条件及亟待研究解决的科学技术问题,包括触发高约束模式的物理机理,功率阈值与等离子体参数的关系等,以及在高约束运行模式下观察到的边缘局域模的驱动机制、控制或缓解技术等.     

托卡马克高约束运行模式和磁约束受控核聚变

磁约束受控核聚变是最终解决人类能源问题的有希望的途径之一.托卡马克的高约束运行模式可以大大降低下一代磁约束聚变实验装置和将来的聚变示范反应堆的规模和造价.文章简要介绍了托卡马克高约束模式的特征,实现条件及亟待研究解决的科学技术问题,包括触发高约束模式的物理机理,功率阈值与等离子体参数的关系等,以及在高约束运行模式下观察到的边缘局域模的驱动机制、控制或缓解技术等.     

等离子体交换不稳定性的模耦合理论

本文研究部分电离等离子体中交换不稳定性的爆炸型模耦合。从磁流体动力学方程出发,导出交换模相干三波相互作用的模耦合方程,分析产生爆炸不稳定的可能的耦合类型,具体讨论产生爆炸不稳定的条件。结果表明,非线性效应能使交换模达到饱和状态表现为小幅度的正弦型扰动,也能通过模耦合而导致大幅度扰动的爆发。本文的分析,适用于磁镜位形的等离子体和电离层等离子体。 关键词：     

HL-2A托卡马克上的边缘局域模特性初步研究

高约束模式(H模)下自发产生的边缘局域模(ELM),虽然利于控制等离子体密度和排出杂质粒子从而实现H模放电的稳态运行,但是ELM爆发携带的大量粒子和能量会对装置的第一壁材料造成很大的损坏,所以在下一代聚变装置上使用之前很多装置已经开始了对ELM的研究.在HL-2A装置上观察到了不同的ELM,扰动幅度小的ELM引起的等离子体储能损失小于3%,ELM之间的时间间隔约为3 ms,表现出Ⅲ型ELM的特征;扰动幅度较大的ELM的爆发对等离子体电流、等离子体密度及储能都有很明显的扰动,对等离子体储能的扰动大于10%,ELM爆发的频率随通过等离子体磁分界面的净加热功率的增加而增加,表现出明显的Ⅰ型ELM的特征.ELM先兆有不对称性,在弱场侧磁探针信号能观测到,但强场侧却观测不到;ELM先兆的频率约为45 kHz,观测到的最长的先兆先于ELM前约10ms出现.     

HL-2A等离子体垂直振荡缓解边缘局域模实验观测

在HL-2A 装置实验中，通过对水平场加入方波扰动，实现了等离子体垂直运动。当等离子体向上垂直运动时，观察到了边缘局域模(ELM)缓解现象。研究发现，等离子体向上运动过程中边缘不断形成新的闭合磁面，导致等离子体体积膨胀，进而使台基宽度增加。此外，ELM 缓解期间杂质和工作气体再循环有所增加。等离子体向上运动过程中体积膨胀、工作气体再循环及杂质增加可能是导致ELM 缓解的主要物理因素。该实验可为未来聚变实验装置ELM 的控制提供一些参考。     

东方超环托卡马克高约束模式边界等离子体输运数值模拟研究

利用SOLPS5.0模拟研究东方超环托卡马克（EAST）高约束模式时的刮削层等离子体. 在高约束模式放电实验参数（第36291炮）的限制下,通过调整上游区径向反常输运系数来实现高约束模式模拟,在上游电子密度和温度与实验符合的条件下能够很好地进行下游区模拟. 在实现高约束模拟的基础上又分别研究了漂移项对偏滤器靶板能流不对称性的影响和上游能流衰减宽度对靶板能流密度峰值的影响. 通过模拟发现,漂移是导致EAST放电内外靶板不对称性的主要原因,增大上游能流衰减宽度可以明显降低入射到靶板的峰值热流,并且偏滤器区辐射以及与中性粒子的相互作用减小了能流的衰减宽度对达到靶板能流的影响. 关键词： 托卡马克 高约束模式 SOLPS5.0 漂移     

HL—1M装置锁模不稳定性研究

在大型托卡马克装置中,各种线圈安装的微小偏差将会引起严重的误差场不稳定性,导致锁模类在大破坏,因此,锁模不稳定性是研究误差场不稳定性的基础。本文分析了H-1M装置锁模不稳定性的产生条件及其特点,并提出抑制锁模不稳定性的参考建议。     

低杂波注入对剥离气球模的作用

基于BOUT++代码研究了托卡马克高约束模等离子体中低杂波(LHW)注入对边缘台基区剥离气球模(P-B模)线性和非线性特性的影响.模拟中分别考虑了LHW驱动的常规主等离子体电流和刮削层螺旋电流丝(HCF)产生三维扰动磁场对P-B模的作用.线性结果表明,LHW驱动的主等离子体电流通过降低平衡的归一化压强梯度和磁剪切,使得线性环向模谱整体向高模数和低增长率的方向移动.非线性模拟表明,由于线性模谱的展宽,LHW驱动的主等离子体电流对P-B模不同模式具有整体的抑制效果,可以降低边缘局域模(ELM)造成的台基能量损失;LHW驱动HCF产生的三维扰动磁场可以通过增强不同模式之间的耦合,促进主模之外的其他模式增长来降低ELM造成的能量损失.研究发现,HCF产生的三维扰动磁场促进增长的P-B模式集中在较高模数,当P-B模的主导模式远离此模数区间,ELM能量损失降低更明显.研究结果有助于深入理解LHW控制ELM实验中的物理机制.     

反磁剪切等离子体中的电阻交换模不稳定性

具有内部输运垒（ITB）的反磁剪切（RS）等离子体位形是在托卡马克中获得高参数的最具前景的途径之一。这种位形不仅改善等离子体约束,而且可以改进象气球模和新经典撕裂模等这类宏观模的稳定性。然而,反磁剪切区域的高压强可以驱动电阻交换模不稳定性,从而破坏中心区的等离子体高参数。为了研究电阻交换模不稳定性的性质,并确定其在RS等离子体中发展的区域,我们利用在HL－2A中使用中性束注入建立的RS位形来分析电阻交换模不稳定性。     

ITER边缘局域模线圈研制焊接形变测量研究

针对ITER边缘局域模(ELM)线圈在研制和焊接过程中的焊接形变测量问题,提出了一种基于激光扫描和逆向建模技术的线圈焊接形变量检测方法.实验表明,该方法对曲面的检测精度可以优于0.1mm,有效地解决了焊接过程中的焊接形变定量检测难题.在ITER ELM线圈焊接工艺改进和评定中,用该方法完成了焊接过程中线圈和工装的形变量...     

Nonlinear Simulations of the Bump-on-Tail Instabilities in Tokamak Plasmas

We reproduce nonlinear behaviors,including frequency chirping and mode splitting,referred to as bump-on-tail instabilities.As has been reported in previous works,the generation and motion of phase-space hole-clump pairs in a kinetically driven,dissipative system can result in frequency chirping.We provide examples of frequency chirping,both with and without pure diffusion,in order to illustrate the role of the diffusion effect,which can suppress holes and clumps;Asymmetric frequency chirpings are produced with drag effect,which is essential to enhance holes,and suppress clumps.Although both diffusion and drag effect suppress the clumps,downward sweepings are observed,caused by a complicated interaction of diffusion and drag.In addition,we examine the discrepancies in frequency chirping between marginally unstable,and far from marginally unstable cases,which we elucidate by means of a dissipative system.In addition,mode splitting is also produced via BOT code for a marginal case with large diffusion.     

Properties of the Tokamak Edge Plasma

A short review of some features of the edge plasma in limiter tokamaks is given. The limits of the simple 1-D SOL model and the relation between the core plasma are discussed. MARFE phenomena and detached plasma are closely connected with the particle and energy balance of the SOL. Their occurrence is based on the relation of plasma parameters of the edge plasma to those of the core. Important problems of plasma wall interactions are the detection of the impurity sources and sinks and the study of the impurity transport and shielding. The non-uniform character of plasma wall interactions and their dependence on the discharge performance still renders difficult any theoretical forecast of impurity distribution and transport and calls for better diagnostics.     

Plasma Response to Resonant Perturbations at Tokamak Edge

In certain circumstances, plasma response suppresses magnetic islands expected at perturbed resonant magnetic surfaces. We investigate the plasma response to the resonant magnetic perturbations in a large aspect ratio tokamak perturbed by external resonant helical windings, considering polar toroidal coordinates for which analytical toroidal equilibrium solutions and perturbing fields are available. We apply an empirical approach to mimic the plasma screening effects by introducing presumed plasma current sheets on the resonance surfaces to cancel the RMP effects. Numerical examples show the effect of plasma response reducing magnetic islands at the plasma edge and also regularizing field lines around the resonant surface. The distribution of connection lengths along the plasma cross section indicates that the plasma response increases the connection lengths since more toroidal turns are performed until a field line reaches the tokamak wall.     

Plasma Edge Biasing on CASTOR Tokamak Using LHCD

The interaction of high power lower hybrid waves with tokamak plasma results in a range of favourable but also unfavourable effects. This article deals with the effects observed by Langmuir probes on the small tokamak CASTOR. The most pronounced effects found are positive biasing of the whole plasma periphery and the formation of a negative "well" of floating potential in front of the launcher.     

Edge Plasma Biasing Experiments on the CASTOR Tokamak: Spectroscopic Investigation and Microwave Measurements

The effects of edge plasma biasing have been recently investigated by different spectroscopic diagnostics on the CASTOR tokamak. Measurements in visible, VUV and XUV ranges complement the knowledge of processes during a biasing phase, and confirm the occurrence of several types of plasma biasing regimes — so called radiating regime, non-radiating regime, and reduced H regime. The use of edge plasma biasing to study the possibility of Electron Bernstein Wave conversion has been demonstrated.     

Observations of Edge Plasma on HL-2A Tokamak

The edge plasma characteristics are studied by a movable array of Mach/Reynolds stress/Langmuir 10-probes and fast reciprocating 4-probes in the boundary region. These probes can measure edge plasma temperature, density, poloidal electric field, radial electric field, Reynolds stress, poloidal rotation velocities and their profiles obtained by changing the radial positions of the probe array in different discharges. Measurement resuits are used to analyze plasma confinement, turbulent fluctuations and their correlation. The fixed flush 3-probe arrays are mounted on the 4-divertor neutralization plates at the same toroidal cross-section in divertor chamber. These probes are used to measure the profiles of the electron temperature, density and float potential in divertor chamber.     

托卡马克等离子体高分辨率光谱诊断

通过压电晶体驱动法布里－珀罗干涉仪实现波长扫描，在单次托卡马克放电过程中完成了离子温度的时间分辨测量，实验表明，该方法光谱分辨率高，并且避免了因多次重复放电引起的不准确性。     

Parametric Instabilities of Waves in Magnetized Plasmas

Results from kinetic theory are reformulated in order to generalize previous equations for wave-wave interactions in magnetized plasmas.     

辅助加热下HL-2A边界层等离子体数值模拟

以二维边界等离子体流体模拟代码B2.5为核心,编制适合于具有封闭偏滤器位形特征托卡马克的边界层网格划分代码和计算后处理代码.模拟分析HL-2A托卡马克有约3MW辅助加热功率时的边界等离子体特性.结果表明,偏滤器靶板前形成了致密低温等离子体,偏滤器运行于高再循环状态.