EAST远红外激光干涉仪与密度爬升实验研究

利用EAST装置单道远红外HCN激光干涉仪测量了等离子体中心道(R=1.82m)线平均电子密度。通过充气加料连续提升主等离子体密度,首次在EAST装置上观察到偏滤器等离子体的三种不同状态：低再循环(偏滤器靶板处等离子体温度较高,密度较低),高再循环(偏滤器靶板处等离子体温度较低,密度较高)和脱靶(偏滤器靶板处等离子体温度和密度都很低)等离子体状态。分析了EAST偏滤器在这三种不同状态下的物理现象。     

HL-2A装置偏滤器物理分析及其实验的初步证实

采用偏滤器物理分析的“两点”模型,分别计算了HL-2A装置线性状态和高再循环状态的边缘等离子体参数,包括偏滤器靶板的等离子体温度、密度和入射功率,以及上游等离子体温度、密度和平行功率密度的衰减长度。用该模型对线性状态预计的靶板温度和密度与实验结果进行了比较,结果符合较好。     

托卡马克实验与工程——HL-2A装置偏滤器物理分析和实验的初步结果

偏滤器等离子体物理分析主要是确定靶板上的温度和密度、功率分散、内外非对称性，以及杂质和中性粒子的控制能力等等。上述参数可以随放电密度和加热功率的变化而划分为3个不同的状态，即线性状态、高再循环状态和脱离状态。描述偏滤器性能的主要参数是温度、密度和功率的衰减长度(λr，λn,λp)，以及聚变产物排除装置的时间。     

HL-2A装置偏滤器的脱靶等离子体实验

在HL-2A装置偏滤器靶板上采用嵌入式静电三探针阵列和偏滤器室内的电动扫描四探针组测量了同一极向截面的内外中性化板上和偏滤器室内的电子温度、密度、悬浮电位、空间电位、电场、电子压强及其分布,研究了偏滤器中等离子体参数的分布及非对称性和脱靶等离子体运行模式下的等离子体行为,开展了偏滤器脱离靶板等离子体的实验研究。利用主真空室的快速往复扫描三台阶式六探针系统测量了主等离子体边缘和偏滤器室内的等离子体温度、密度、粒子通量和中性粒子密度等参数,研究了脱靶等离子体的形成过程、物理特性、控制方法,以及对主等离子体性能的影响。     

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用HL-2A装置下偏滤器靶板上的14组嵌入式静电三探针阵列和外偏滤器室的电动扫描四探针组,测量了同一环向截面的内外中性化板上的电子温度、密度、悬浮电位及其分布,以及电子回旋加热(ECRH)实验期间的等离子体行为。研究了偏滤器中等离子体参数的分布及非对称性以及等离子体的形成、物理特性和改善粒子的约束特性。     

偏滤器运行模式对托卡马克边缘区等离子体平行流的影响

我们使用一维流体模型,根据在不同偏滤器运行模式下静压强沿着磁力线方向的分布变化,讨论了偏滤器运行模式对托卡马克边缘区等离子体平行流的影响.低再循环模式下,静压强从X点 (X-point)附近的刮削层区域开始明显下降,变化趋势与密度变化趋势一致;等离子体平行流的马赫数在偏滤器区域逐步变大,变化从平缓到迅速.高再循环模式下,静压强在靶板附近的区域迅速下降,在其他区域变化非常小;等离子体平行流的马赫数仅在靠近靶板附近的区域迅速变大,在其他区域变化平缓.在弱脱靶模式下的静压强变化与高再循环模式下类似,不过静压强在X-point附近的刮削层区域开始出现下降的趋势,导致等离子体平行流的马赫数在X-point处的值比在高再循环模式下大.强脱靶模式下,静压强在刮削层区域开始明显下降,在远离靶板的偏滤器区域,静压强迅速下降的地方,观察到高马赫数等离子体平行流.静压强迅速下降引起动压强迅速上升来维持总的压强守恒是在强脱靶状态 下产生高马赫数平行流的一种可能驱动机理.     

EAST 钨偏滤器外靶板热工水力分析

为提高EAST 偏滤器的抗热载和排热能力,将偏滤器第一壁的材料由原来的石墨改为钨,在结构上,靶板采用了类ITER 的单块结构,支撑和冷却采用一体化的盒式结构。确定了EAST 钨偏滤器的冷却结构后,通过水管的流固耦合传热模型,分析了外靶板在紊流冷却方式下的散热情况。同时计算了在水冷系统失效的情况下,偏滤器外靶板的危险区域在3、5、8、10MW·m^-2 热流密度下的瞬态温度分布情况。结果表明,水流速度在4m·s^-1 时, 水管可以承受峰值功率10MW·m^-2 的热流密度,能够很好地满足EAST 装置运行的排热要求。     

HL-2A装置送气和加料的脱靶特性

HL-2A装置辐射偏滤器实验采用边缘补充送气和分子束加料等方法来提高主等离子体密度,降低边缘等离子体温度、增加辐射功率分额,获得脱靶等离子体。偏滤器室内进行主动补充送气或者注入惰性气体杂质,降低偏滤器等离子体温度,获得脱靶等离子体,并首次获得了超声分子束注入产生脱靶等离子体的实验结果。利用HL-2A装置偏滤器同一极向截面内外中性化板上安装的嵌入式探针阵列和偏滤器室安装的电动探针系统,测量了偏滤器靶板上和偏滤器室的等离子体参数及其分布,并进行了相关分析和改善约束以及偏滤器脱靶等离子体运行模式下等离子体行为的研究。     

用B2程序模拟HL-2A装置附着状态等离子体

用大型边缘多流体二维等离子体输运数值模拟程序B2模拟了HL-2A装置外偏滤器以及与之相连的刮削层内的等离子体。在不同的中心密度运行区，纯氢放电的HL-2A偏滤器可以形成不同的再循环运行模式，即线性或高再循环模式。通过控制模拟刮削层与芯部等离子体交界面处的等离子体参数，可实现对HL-2A装置再循环模式的控制。     

偏滤器等离子体中杂质对钨壁材料的侵蚀模拟研究

偏滤器是托卡马克中与等离子体直接接触的部件,为了保证装置的寿命,需要尽可能地减小等离子体对偏滤器靶板的侵蚀.本文用粒子模拟的方法研究了不同等离子体温度情况下碳和铍两种杂质离子对钨偏滤器侵蚀速率的影响.模拟首先得到稳定的鞘层结构、入射到靶板的离子流和能流密度,并通过统计获得了入射离子的能量和角度分布,最终根据这些物理参量,采用经验公式计算出钨靶板的侵蚀速率.研究表明,在等离子体温度不太高的情况下,钨靶板的热侵蚀几乎不起作用,而由于杂质离子对钨的物理溅射阈值较低,并且会通过鞘层加速获得能量,因此其对钨壁材料的物理溅射是导致靶板侵蚀的主要原因,另外靶板材料的侵蚀速率随着等离子体温度升高以及杂质含量增大而急剧增大.     

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.     

Numerical analysis of high Mach flow and flow reversal in the experimental advanced superconducting tokamak divertor

The B2-Eirene (SOLPS 4.0) code package is used to investigate the plasma parallel flow, i.e., the scrape-off layer (SOL) flow, in the experimental advanced superconducting tokamak (EAST) divertor. Simulation results show that the SOL flow in the divertor region can exhibit complex behaviour, such as a high Mach flow and flow reversal in different plasma regimes. When the divertor plasma is in the detachment state, the high Mach flow with approaching or exceeding sonic speed is observed away from the target plate in our simulation. When the divertor plasma is in the high recycling state, the flow reversal with a small Mach number (|M|< 0.2) is observed near the X-point along the separatrix region. The driving mechanisms for the high Mach flow and the reversed flow are analysed theoretically through momentum and continuity equations, respectively. The profile of the ionization sources is shown to be a possible formation condition causing the complex behaviour of the SOL flow. In addition, the effects of the high Mach flow and the flow reversal on the impurity transport are also discussed in this paper.     

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.     

Diagnostics for first plasma study on EAST tokamak

The first plasma was obtained in the EAST on September 26th, 2006. Single-null (SN) and double-null (DN) diverted plasmas were achieved successfully in the EAST tokamak on January 22nd, 2007. The employed plasma diagnostics for first plasma study of EAST are as follows: a vertical one-channel far-infrared (FIR) hydrogen cyanide (HCN) laser interferometer for measuring the line average density, a 10-channel soft X-ray array for intensity measurement, a 16-channel heterodyne Electron Cyclotron Emission (ECE) for measuring the electron temperature profile, a 8-channel XUV bolometer array to measure plasma radiation losses, a 3-channel hard X-ray array for intensity measurement, an electromagnetic measurement system, a 35-channel Hα radiation array, 20 probes for divertor plasma, a one-channel visible bremsstrahlung emission, an impurity optical spectrum measurement system and two optical spectroscopic multi-channel analyzers (OMA). The first experimental results of diagnostic systems are summarized in this Letter.     

L–H power threshold studies with tungsten/carbon divertor on the EAST tokamak

The power threshold for low (L) to high (H) confinement mode transition achieved by radio-frequency heating and molybdenum first wall with lithium coating has been experimentally investigated on the EAST tokamak for two sets of divertor geometries and materials: tungsten/carbon divertor and full carbon divertor. For both sets of divertors, the power threshold was found to decrease with gradual accumulation of the lithium wall coating, suggesting the important role played by the low Z impurities and/or the edge neutral density on the L–H power threshold. When operating in the upper single null configuration, with the ion grad-B drift direction away from the primary X-point, a lower normalized power threshold is observed in EAST with the tungsten/carbon divertor, compared to the carbon divertor after intensive lithium wall coating. A newly installed cryopump increasing the pumping efficiency also plays an important part in the observed lower threshold. In addition, the H-mode in the Quasi-Snowflake divertor configuration has been obtained on EAST, exhibiting higher L–H power threshold compared to the lower single null configuration with similar I_P/B_T pairs.     

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介绍了EAST超导托卡马克偏滤器的最新冷却模块结构。利用FLUENT有限元软件对不同参数下的模型进行了稳态热分析,定量研究了冷却模块换热能力随各参数的变化规律。针对EAST装置给出了初步优化的参数范围,为水冷钨铜偏滤器的设计制造提供了参考。这对于托卡马克装置及聚变堆偏滤器研究具有十分重要的意义。