HL-2A装置偏滤器室中性气体压强规的研制

HL-2A装置是我国第一个带偏滤器的托卡马克装置，偏滤器运行是一个新课题。在偏滤器研究中，偏滤器室中性气体压强的诊断与控制具有重要意义。为此，我们研制了可工作在强磁场下的快响应电离规(简称：快规)和配套真空计，对HL-2A装置偏滤器室的中性气体压强进行了测量。     

HL-2A装置改造方案磁流体平衡的数值模拟

对HL-2A装置的改造方案进行数值模拟,获得了放电初始阶段零场区域设计的最佳方案、等离子体限制器平衡位形、单零偏滤器平衡位形和双零偏滤器平衡位形以及从气体击穿到等离子体电流平顶的等离子体平衡位形的演化过程。计算结果表明,该装置设计方案能够满足装置预期的设计参数要求。     

HL-2A 装置偏滤器改造的初步设计

根据HL- 2A 装置的结构特点, 提出了HL- 2A 装置偏滤器系统改造的基本方向。对HL- 2A 极向场线圈系统进行了优化设计, 计算了单零平衡位形, 进行了开放式偏滤器的结构设计, 并对新的偏滤器系统进行了热分析和结构分析。结果表明, 新的偏滤器系统新的偏滤器系统能够满足具有一定拉长比和三角形变的等离子体放电要求。     

HL-2A装置偏滤器室中性气体压强的研究

采用自行研制的可工作在强磁场下的快响应电离规(简称：快规)对HL-2A装置偏滤器室的中性气体压强进行了测量和研究。     

HL-2A装置初始运行阶段杂质和辐射行为的初步研究

作为国内第一个带有偏滤器的托卡马克装置，在HL-2A装置的起始运行阶段，了解等离子体中存在的杂质种类和辐射水平、评估杂质的含量以及在偏滤器位形和孔栏位形下杂质辐射行为的变化都是很重要的。在HL-2A装置的初始运行阶段，壁处理主要是采用常规的辉光放电清洗（GDC）；在偏滤器运行阶段也使用过蒸钛来减少下偏滤器室的杂质以利于偏滤器位形的建立；但未使用硅化等可能破坏初始器壁条件的壁处理手段。     

HL-2A装置等离子体可见光成像系统

在HL-2A装置上研制了等离子体可见光成像系统,用于孔栏、偏滤器位形放电的诊断。该成像系统由彩色摄像机、观察窗和转向镜、广角收集和准直透镜组、采集卡和计算机组成。本文描述了系统的布局和各部件参数的匹配,报道了观测到的实验结果。等离子体成像系统能监视放电的整个过程,实时显示可见光辐射图形,特别在识别孔栏与偏滤器位形放电的诊断中发挥了重要作用,成为HL-2A装置放电的重要诊断手段。     

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对HL-2A装置限制器位形和偏滤器位形下放电气体分别为氘和氦时的等离子体热辐射测量结果做了初步分析,分析结果表明：在偏滤器室注入惰性气体能够有效的降低到达靶板的热辐射;超声分子束注入时,观测到注入粒子在等离子体中输运过程;氦放电时的辐射比值明显高于氘放电时的比值;真空室器壁的处理能够有效地降低辐射损失,硅化对器壁条件的改善效果明显。     

HL-2A装置改造方案中的磁流体平衡的数值模拟

针对HL-2A装置改造中的HL-2M方案进行的一种数值模拟，模拟放电初始阶段零场区域的设计、等离子体平衡位形的演化和稳态阶段的单零偏滤器平衡位形、结果表明，该装置设计方案能够满足装置设计要求。     

HL-2A装置等离子体水平位移控制

HL-2A装置是带封闭偏滤器的磁约束托卡马克实验装置，于2002年底建成并通过国家验收。2003年在各子系统准备充分和等离子体水平位移反馈控制系统投入运行后，实现了首次重复的偏滤器位形等离子体放电实验。     

HL-2A偏滤器运行模式的探针测量

在HL-2A装置的偏滤器位形运行模式下,用偏滤器靶板上的平面型嵌入式静电探针阵列测量了同一环截面的内外和上下四个中性化板上的电子温度、密度、悬浮电位分布。偏滤器运行模式下的边缘电子温度高于孔栏运行模式下的边缘的电子温度。比较了内外靶板之间的温度不对称性。给出了由18个米尔诺夫线圈信号重建获得的磁分界面,并用强磁场快速电离规测量了偏滤器室的中性气体压强变化。测量结果表明,在偏滤器运行模式下,主真空室中边缘粒子再循环降低,杂质通量水平下降。     

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.     

Neutral Pressure Measured by Fast Ionization Gauge in HL-2A

A special fast ionization gauge is developed to measure the neutral gas pressure in the main chamber and the divertor chamber of the HL-2A tokamak during discharges in order to research on particle behaviors, and to control the neutral gas pressure actively in the divertor chamber to further obtain radiation or detached divertor discharges     

Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

A hybrid method for tokamak MHD equilibrium configuration reconstruction is proposed and employed in the modified EFIT code. This method uses the free boundary tokamak equilibrium configuration reconstruction algorithm with one boundary point fixed. The results show that the position of the fixed point has explicit effects on the reconstructed divertor configurations. In particular, the separatrix of the reconstructed divertor configuration precisely passes the required position when the hybrid method is used in the reconstruction. The profiles of plasma parameters such as pressure and safety factor for reconstructed HL-2A tokamak configurations with the hybrid and the free boundary methods are compared. The possibility for applications of the method to swing the separatrix strike point on the divertor target plate is discussed.     

The first results of divertor discharge and supersonic molecular beam injection on the HL-2A tokamak

HL-2A tokamak is the first tokamak with divertors in China. The plasma boundary and the position of the striking point on the target plates of the HL-2A closed divertor were simulated by the current filament code and they were in agreement with the diagnostic results in the divertor. Supersonic molecular beam injection (SMBI) system was first installed and tested on the HL-2A tokamak in 2004. In the present experiment low pressure SMBI fuelling on the HL-2A closed divertor was carried out. The experimental results indicate that the divertor was operated in the `linear regime' and during the period of SMB pulse injection into the HL-2A plasma the power density convected at the target plate surfaces was 0.4 times of that before or after the beam injection. It is a useful fuelling method for decreasing the heat load on the neutralizer plates of the divertor.     

HL-2A单零偏滤器的位形特征

利用积分方法对多种电流剖面下HL2A装置单零偏滤器位形特征进行了计算研究。积分方法的优点是可以在任意电流剖面下求解具有X-点的自由边界的Grad-Shafranov方程。对HL2A装置而言,大体上可以在合理设定的分界面形状下,经几次叠代计算出各组极向场线圈(垂直场,三对多极场和多极补偿场以及水平场)中的电流。HL-2A的单零偏滤器位形基本上是圆截面加上在X-点附近的局部形变。对刮离区和偏滤器靶板区磁力线特性进行了分析以确定偏滤器的品质。     

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.     

HL-2A偏压偏滤器物理设计

根据已有的理论模型,推算出了HL-2A偏压偏滤器的理论电流为1．5kA、偏压电压为200V,并对HL-2A偏压偏滤器做出了初步设计。HL-2A装置采用偏压后,有可能降低L-H模转变阈功率,增加偏滤器等离子体密度、压强和滞留时间,改善约束,改善内外靶板功率沉积的非对称性,提高排灰效率及提高偏滤器性能。