Study on divertor plasma behavior through sweeping strike point in new lower divertor on EAST

A series of L-mode discharges have been conducted in the new ‘corner slot’ divertor on the Experimental Advanced Superconducting Tokamak (EAST) to study the divertor plasma behavior through sweeping strike point. The plasma control system controls the strike point sweeping from the horizontal target to the vertical target through poloidal field coils, with keeping the main plasma stability. The surface temperature of the divertor target cools down as the strike point moves away, indicating that sweeping strike point mitigates the heat load. To avoid the negative effect of probe tip damage, a method based on sweeping strike point is used to get the normalized profile and study the decay length of particle and heat flux on the divertor target λ_js, λ_q. In the discharges with high radio-frequency (RF) heating power, electron temperature T_e is lower and λ_js is larger when the strike point locates on the horizontal target compared to the vertical target, probably due to the corner effect. In the Ohmic discharges, λ_js, λ_q are much larger compared to the discharges with high RF heating power, which may be attributed to lower edge T_e.     

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为了实现 EAST 装置真空室内的内窥多关节机械臂的实时高精度控制,提出了一种逆运动学算法,即建立机械臂多变量的方程组,转化成为矩阵的特征值问题求解。为了验证和满足实际控制的需要,还基于 VC++6.0 开发了 MFC 运动学算法程序。结果表明,该算法能在 ms 级别内得到机械臂的所有运动学逆解。     

EAST极紫外空间分辨光谱分析软件的开发

基于Matlab软件的图形用户界面开发环境(GUIDE)设计开发了一套交互式界面，可以自动读取、解析原始数据，开展波长标定，将谱强度与谱仪系统空间测量位置以及EAST实验放电时间等信息相关联，从而快速、便捷地计算杂质离子发出的线光谱强度的空间分布并绘图。该空间分辨光谱分析软件的开发和应用大大提高了谱仪数据处理和分析的便捷性和效率，保证了放电期间数据处理的准实时性。     

EAST新型下偏滤器冷却结构 传热性能数值模拟

为实现EAST装置超400s长脉冲高约束模、10MW加热功率下的稳态运行，需对现有的下碳偏滤器进行升级改造，拟采用钨串结极水冷却系统，热通量控制在水冷钨铜第一壁材料允许的稳态的10MW·m^-2。在对下钨偏滤器的冷却结极传热性能进行数值模拟仿真研究的基础上，研究了多种以钨串单元为基础的冷却结极，提出了一种新型下钨偏滤器水冷结极设计，幵建立了满足传热要求的EAST装置新型下钨偏滤器单元结构模型。     

EAST快速极紫外光谱仪绝对强度的原位标定

磁约束等离子体中杂质(特别是高Z杂质)的存在将大大增强等离子体辐射功率损失，破坏等离子体的约束性能。杂质行为的定量研究首先要求对杂质测量的光谱诊断系统进行绝对强度标定，获得灵敏度响应曲线。介绍了EAST托卡马克上的快速极紫外光谱仪系统绝对强度的原位标定方法。在波长范围20～150Å内，通过对比极紫外(EUV)波段连续轫致辐射强度的计算值和测量值得到光谱仪的绝对强度标定。在此过程中，首先由(523±1) nm范围内可见连续轫致辐射强度的绝对测量值计算出有效电荷数Z_eff，进而结合电子温度和密度分布计算EUV波段连续轫致辐射强度；EUV波段连续轫致辐射强度的测量值即为不同波长处探测器的连续本底计数扣除背景噪声计数值。对于较长波段范围130～280Å，通过对比等离子体中类锂杂质离子(Fe23+，Cr21+，Ar15+)和类钠杂质离子(Mo31+，Fe15+)发出的共振谱线对(跃迁分别为1s22s 2S_1/2-1s22p 2P_{1/2, 3/2}及2p63s 2S_1/2-2p63p 2P_{1/2, 3/2})强度比的理论和实验值进行相对强度标定。其中共振谱线对强度比的理论值由辐射碰撞模型计算得到，模型中处在各个能级的离子数主要由电子碰撞激发，去激发以及辐射衰变三个过程决定。两种方法相结合，实现了光谱仪20～280Å范围的绝对强度标定。考虑轫致辐射、电子温度及电子密度的测量误差，绝对标定误差约为30%。在绝对标定的基础上，我们对杂质特征谱线强度进行绝对测量，并将测量结果与杂质输运程序结合ADAS(Atomic Data and Analysis Structure)原子数据库计算得到的模拟值进行比较，进而估算等离子体中的杂质浓度。     

Numerical simulation of electron cyclotron current drive characteristics on EAST

Electron cyclotron current drive （ECCD） will be applied in the EAST tokamak during its the new campaign. In order to provide theoretical predictions for relevant physical experiments, some numerical simulations of ECCD with the parameters of EAST have been can＇ied out by using TORAY-GA code based on the understanding of ECCD mechanisms. ECCD efficiencies achieved in different plasma and electron cyclotron （EC） wave parameters are given. The dependences of ECCD characteristics on EC wave injection angle, toroidal magnetic field, plasma density, and temperature are presented and discussed.     

Observation and analysis of halo current in EAST

Plasma in a typically elongated cross-section tokamak （for example, EAST） is inherently unstable against vertical displacement. When plasma loses the vertical position control, it moves downward or upward, leading to disruption, and a large halo current is generated helically in EAST typically in the scrape-off layer. When flowing into the vacuum vessel through in-vessel components, the halo current will give rise to a large J × B force acting on the vessel and the in-vessel components. In EAST VDE experiment, part of the eddy current is measured in halo sensors, due to the large loop voltage. Primary experimental data demonstrate that the halo current first lands on the outer plate and then flows clockwise, and the analysis of the information indicates that the maximum halo current estimated in EAST is about 0.4 times the plasma current and the maximum value of TPF × Ih/Ip0 is 0.65, furthermore Ih/Ipo and TPF × Ih/Ipo tend to increase with the increase of Ip0. The test of the strong gas injection system shows good success in increasing the radiated power, which may be effective in reducing the halo current.     

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EAST NBI束线综合测试台已研制完成并具备一台兆瓦级离子源测试运行的全套电源设备,包括离子源灯丝电源、弧电源、加速器电源、抑制极电源、偏转磁体电源及缓冲器电源等。介绍了EAST兆瓦级离子源进行起弧放电调试运行的方式,叙述了各套离子源电源系统的设计结构、技术特点及运行控制方式,分析了离子源电源系统稳定可靠运行需要解决的各个难点,给出了EAST束线样机进行高功率及长脉冲束引出测试运行的实验结果。     

EAST中加热功率对弹丸注入加料效率的影响

介绍了 EAST 装置气动加速氘弹丸注入加料系统和不同加热功率条件下弹丸加料效率的实验结果。 当等离子体加热功率从 1MW 逐渐增加到 10MW 时,弹丸加料效率从 60%降低到 10%。加热功率的升高导致弹 丸粒子的沉积深度 λp/a 降低达 50%左右,从而导致大量的弹丸粒子沉积在等离子体边界。