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通过对托卡马克中模拟积分器积分误差的分析,设计了一种由数字信号处理部件动态抑制这些误差的斩波式积分器,并在实验中获得了长时间、低漂移的积分效果。     

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利用毕奥萨伐尔定律,通过对EAST内部等离子体电流的运动状态的研究,建立了EAST内部的磁场数学模型,并利用Matlab对实验数据的拟合分析,对模型进行了分析验证.通过误差分析,进而改进模型,研究表明改进后的模型与实验数据能较好吻合,误差较小.相关研究和结论对托卡马克真空室内磁场测量具有一定的指导意义,为进一步研究基于MEMS技术的超导托卡马克装置电磁测量诊断系统的微纳磁敏传感器奠定理论基础.     

EAST装置中70m双绞线对信号衰减的研究

为了分析EAST装置电磁测量系统中70m双绞线给测量信号带来的影响,建立了电磁线圈和双绞线的等效电路模型。设计了有双绞线模型和没有双绞线模型的两种电路模型,并对这两种模型在simolorer6.0软件中进行了仿真,通过分析这两种模型的传递函数和仿真输出的电压峰峰值,证明了70m双绞线对EAST中电磁测量系统的影响是可以忽略的。     

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.     

Effect of passive structure and toroidal rotation on resistive wall mode stability in the EAST tokamak

If βN exceeds no-wallβN, the plasma will be unstable because of external kink and resistive wall mode(RWM). In this article, the effect of the passive structure and the toroidal rotation on the RWM stability in the experimental advanced superconducting tokamak(EAST) are simulated with CHEASE and MARS codes. A model using a one-dimensional(1D)surface to present the effect of the passive plate is proved to be credible. The no wall βN limit is about 3li, and the ideal wall βN limit is about 4.5li on EAST. It is found that the rotation near the q = 2 surface and the plasma edge affects the RWM more.     

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讨论了用于磁场测量的磁感应线圈的有效感应面积和积分器的积分时间这两个参数的精确标定,描述了两种标定系统的测量原理以及其相应的特点。     

磁探针参数的标定

为了标定EAST装置电磁测量系统中的磁探针位置偏差和回路增益,通过分析该装置中的误差源,设计了极向场线圈的通电模式。运用格林函数等算法程序对测量数据进行预处理,利用简化的泰勒线性展开,结合带权重的最小二乘法对数据进行多次循环迭代,拟合出磁探针的位置偏差和回路增益。实验结果表明,使用该方法标定是合理的。     

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为了标定EAST装置电磁测量系统中的磁探针位置偏差和回路增益,通过分析该装置中的误差源,设计了极向场线圈的通电模式。运用格林函数等算法程序对测量数据进行预处理,利用简化的泰勒线性展开,结合带权重的最小二乘法对数据进行多次循环迭代,拟合出磁探针的位置偏差和回路增益。实验结果表明,使用该方法标定是合理的。     

HT-7超导托卡马克调制电流改善等离子体约束

 在HT-7超导托卡马克上进行了电流调制改善等离子体约束物理实验，获得了初步的实验结果。对电流调制时的径向电场进行了数值计算和讨论。当等离子体环向电流以适当的频率和幅值周期性调制时，低模数的磁流体不稳定性得到明显的抑制，等离子体中心电子温度增加了33%，等离子体电子密度分布明显陡化，能量约束时间增加了27%~45%。杂质辐射周期性减少,粒子约束时间增加了2倍。在等离子体边界产生更强的径向负电场。     

Characterization of plasma current quench during disruption in EAST tokamak

A preliminary analysis of plasma current quenching is presented in this paper based on the disruption database.It demonstrates that 26.8%of discharges have been disrupted in the last 2012 campaign,in addition,the plasma disruptive rate grows with the increase of plasma current.The best-fit linear and instantaneous plasma current quench rate is extracted from the recent EAST disruptions,showing that an 80%-30%interval of the maximum plasma current is well fit for the EAST device.The lowest area-normalized current quench time is 3.33 ms/m~2 with the estimated plasma electron temperature being 7.3 eV~ 9.5 eV.In the disruption case the maximum eddy current goes up to 400 kA,and a fraction of currents are respectively driven on the upper and lower outer plate with nearly 100 MPa-200 MPa stress in the leg.