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。     

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破裂诱发的Halo电流会流进内真空室结构,对偏滤器支撑结构有较大的破坏。通过安装在偏滤器支撑结构上的罗柯夫斯基线圈对EAST中Halo电流进行了研究。通过分析不同位置的Halo电流信号,发现这些Halo电流具有环向不对称性,环向不对称因子为2.5, 的最大值是0.65。这些结果对EAST真空室电磁载荷分析有着重要的意义。     

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基于EAST超导托卡马克实验装置,给出了HALO电流计算方法和计算过程,并通过自由能方法模拟得出了等离子体电流、HALO电流在等离子体破裂过程中随时间的演化过程。     

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采用1.5维的放电模拟程序TSC结合蒙特卡罗程序NUBEAM对使用中性束加热的EAST放电全过程进行数值模拟研究。分析了典型实验参数条件下的中性束的加热及电流驱动效果。讨论了不同背景等离子体密度对中性束加热及电流驱动效果的影响。模拟结果表明,中性束的注入使得背景等离子体温度有了较大幅度的提升,并能驱动出一定份额的非感应电流;适当降低背景等离子体密度有助于提高中性束的加热及电流驱动效率。     

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用有限元软件Fluent对EAST超导磁体电流引线中氦气流阻进行了计算。计算中对氦气模型进行了简化和分段,相邻两段模型间采用流量边界条件和压力边界条件进行耦合。计算结果表明:氦气的压力降主要集中在靠近室温端;气体模型厚度越薄,氦气压力降越大;通过电流引线的电流越大,氦气的压力降越大;在引线片凸纹的狭窄处氦气速度很大,在靠近室温端时最大可以达到21m.s-1左右。     

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应用改进后的低杂波电流驱动程序对EAST进行了低杂波电流驱动的数值模拟。通过模拟发现,波注入位置、功率谱、等离子体温度和密度对低杂波的功率沉积和电流驱动剖面分布有很大影响。通过选取合适的低杂波功率谱、等离子体温度和密度,可以实现对其功率沉积和电流驱动剖面分布的控制。     

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用TSC程序模拟了EAST装置等离子体放电的全过程。模拟中考虑了自举电流，并加入了离子回旋共振加热ICRH和快波电流驱动FWCD，得到了中心电子温度4.5keV、中心离子温度3.8keV、中心电子密度1.2×1020m–3的D形截面的等离子体。根据模拟结果对EAST装置进行了伏秒数分析，并研究了不同等离子体电流上升时间、有效电荷数Zeff对放电的影响。     

高温等离子体中固体弹丸消融过程的研究

本文求得了弹丸消融过程的自洽解析解。结果表明:Parks的弹丸消融理论需要修正;弹丸消融速率由消融物云和表面蒸发层共同控制;入射电子通过消融物云时慢化效应并不显著;消融物离开弹丸表面时一般呈部分电离态;聚变堆条件下,弹丸表面可能会出现激波。     

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中性束注入是等离子体加热和电流驱动的重要方式之一,对EAST中性束注入的精确模拟对未来物理实验至关重要.采用ONETWO和NUBEAM程序模拟4MW、80keV中性束同向注入,不同的等离子体密度剖面导致不同的电子和离子加热、穿透功率损失、束驱动电流以及中子发射等.等离子体密度在以上的物理参数的演化中起着重要的作用.对EAST两种密度方案下中性束注入的效果进行了分析和讨论,并对未来中性束实验提供了一些预言性的建议和方案.     

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.     

中高能电子的散射全截面测量装置

以电子束流光学系统为重点,介绍一台500～4250eV电子的绝对散射全截面测量装置,给出了电子枪和五圆筒透镜的电子光学设计,提供实验对电子光学系统的检验,提出对装置的改进设想。     

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给出了EAST极向场磁体电源失超保护系统的设计方案,描述了两种失超保护开关——直流快速开关和爆炸开关采用的两级换流结构的设计和工作原理,分析了这种结构在换流过程中的规律,该结构有效地解决了开关开断直流大电流的难点。通过模拟实验证明了该失超保护系统满足设计要求。     

First principles simulation technique for characterizing single event effects

This paper develops a new simulation technique to characterize single event effects on semiconductor devices. The technique used to calculate the single event effects is developed according to the physical interaction mechanism of a single event effect. An application of the first principles simulation technique is performed to predict the ground-test single event upset effect on field-programmable gate arrays based on 0.25 μm advanced complementary metal-oxide-semiconductor technology. The agreement between the single event upset cross section accessed from a broad-beam heavy ion experiment and simulation shows that the simulation technique could be used to characterize the single event effects induced by heavy ions on a semiconductor device.     

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.     

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.     

掺铒光纤吸收截面和辐射截面的简单估算方法

提出了一种利用损耗谱测试数据直接计算吸收和辐射截面的近似方法，并实际计算了一些掺铒光纤的截面特性。这对掺铒光纤放大器的理论分析和优化设计有着重要的意义。