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为了测量EAST磁体位移的变化,采用计算机视觉处理方法构筑三维测量模型,利用边缘检测算法对图像采集系统获得的图片进行识别和检测,最终得出位移的变化值,从而可以在等离子体磁场位形控制中通过补偿修正这些变化。该测量方法解决了EAST装置冷质磁体位移测量的难题。     

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介绍了EAST偏滤器充气系统的改进措施,压电阀与冷屏一起安装在EAST颈管中,以缩短充气管道,将充气系统的延迟时间减少约200ms。冷屏起冷却阀门并屏蔽电磁场的作用。讨论了在准稳态条件下,延迟时间给偏滤器热流反馈控制带来的负面效应。在中性束加热条件下,通过在外靶板注入 Ar/D2(1：4)混合气体研究了靶板离子饱和流和热流分布的变化及充气对主等离子体的影响,得到了靶板离子饱和流显著降低、热流减少的结果。     

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利用多阵列高时空分辨的软X射线阵列成像系统对EAST芯部固有杂质驱动的蛇形振荡进行时间动态演化和空间结构反演研究,研究了实验上发现的两种时空行为明显不同的两类蛇形振荡,一类具有字母V或W形状的动态频谱,空间上为理想近圆状热芯结构;另外一类蛇形振荡和锯齿崩塌共存,振荡的频谱呈现手掌状,空间上为很大的电阻性月牙形磁岛结构。结果表明,锯齿共存的蛇形振荡的饱和径向扰动位移通常比无锯齿的蛇形振荡大,并且会触发边界的新经典撕裂模。     

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为了实现对低杂波系统天线的保护需要测量天线温度,根据天线的特征,选择了K型热电偶作为测量工具,使用快速温度巡检仪采集8路热电偶信号,温度数据由软件远程读取显示;为了克服托卡马克带来的电磁干扰,测量回路使用了光纤通信的方法。结果表明,这种方式能够准确实时地反映出天线温度变化,为日后开展天线热保护工作奠定了基础。     

Reduction of impurity confinement time by combined heating of LHW and ECRH in EAST

The core impurity confinement properties are experimentally investigated in the Experimental Advanced Superconducting Tokamak(EAST) plasma heated by lower hybrid wave(LHW) and electron cyclotron resonance heating(ECRH)(LHW+ECRH).It is shown that the impurity confinement time(τ_(imp)) in the L-mode plasma jointly heated by LHW and ECRH is weakly dependent on electron density but strongly dependent on the heating power,thus it is shorter than that in LHW-only heated L-mode plasma with the similar plasma parameters.The combined heating of LHW and ECRH can reduce the collisionality and indicates a more effective heating method for core τimp reduction and normalized poloidal beta(βP) ~(im)provement.It should be emphasized that in this high β_P operation window the small ELM regime can be accessed,and an L-mode level τ_(imp)(40 ms-80 ms) and high β_N(～1.7) can be obtained simultaneously.It means that this typical small ELMy H-mode regime has an advantage in avoiding the serious tungsten accumulation,and will be competitive in future long-pulse steady-state and high-performance operation with high-Z material plasma-facing components.     

Modeling of beam ions loss and slowing down with Coulomb collisions in EAST

This paper uses the implicit Monte-Carlo full-orbit-following parallel program ISSDE to calculate the prompt loss and slowing down process of neutral beam injection (NBI)-generated fast ions due to Coulomb collisions in the equilibrium configuration of Experimental Advanced Superconducting Tokamak (EAST). This program is based on the weak equivalence of the Fokker-Planck equation under Rosenbluth MacDonald Judd (RMJ) potential and Stratonovich stochastic differential equation (SDE). The prompt loss with the LCFS boundary and the first wall (FW) boundary of the two co-current neutral injection beams are studied. Simulation results indicate that the loss behavior of fast ions using the FW boundary is very different from that of the LCFS boundary, especially for fast ions with a large gyration radius. According to our calculations, about 5.11% of fast ions generated by perpendicular injection drift out of the LCFS and then return inside the LCFS to be captured by the magnetic field. The prompt loss ratio of fast ions and the ratio of orbital types depend on the initial distribution of fast ions in the P_ζ-$\varLambda$ space. Under the effect of Coulomb collisions, the pitch-angle scattering and stochastic diffusion happens, which will cause more fast ion loss. For short time scales, among the particles lost due to collisions, the fraction of banana ions reaches 92.31% in the perpendicular beam and 58.65% in the tangential beam when the fraction of banana ions in the tangential beam is 3.4% of the total ions, which means that the effect of Coulomb collisions on banana fast ions is more significant. For long time scales, the additional fast ion loss caused by Coulomb collisions of tangential and perpendicular beams accounted for 16.21% and 25.05% of the total particles, respectively. We have also investigated the slowing down process of NBI fast ions.     

A divertor plasma configuration design method for tokamaks

The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber.It is important to construct the proper plasma equilibrium with a desired plasma configuration.In order to construct the target configuration,a shape constraint module has been developed in the tokamak simulation code(TSC),which controls the poloidal flux and the magnetic field at several defined control points.It is used to construct the double null,lower single null,and quasi-snowflake configurations for the required target shape and calculate the required PF coils current.The flexibility and practicability of this method have been verified by the simulated results.     

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介绍了EAST装置新型离子回旋加热(ICRH)天线电流带的设计结构。通过对电流带实际工况的计算得出电流带的工作温度分布,以此来模拟实际工作条件下电流带的热载荷承受能力以及对电流带结构的影响。论证了在实际工况热载荷条件(0.2MW)下,电流带辐射面温度及电流带整体结构强度满足设计要求。     

升级EAST快控电源控制器研制

针对EAST快控电源缩短电流响应时间的要求,升级的快控电源控制器采用TMS320F28335替代原快控电源支路控制器中的TMS320F2812,实现响应和输出脉冲宽度调节(PWM)控制上的载波相移,提高系统等效开关频率,减小输出电压响应延时。经过实验验证,升级的快控电源控制器实现预定目标,有助于提升EAST装置抑制等离子体垂直位移不稳定性的能力。     

EAST偏振干涉仪电子密度跳变修正程序的开发

分析了EAST装置偏振干涉仪系统进行电子密度测量时存在的密度跳变信号,开发了密度跳变信号修正程序.结果表明,通过该程序跳变的电子密度数据可以得到有效的修正.