相干结构Blob在HT-7托卡马克边界的传播

相干结构Blob的间歇爆发清晰地反映在HT-7托卡马克边界探针的离子饱和流信号中,Blob的径向传播在近刮削层堆积出一个温度和密度的平台区,使密度和温度分布偏离了指数分布。条件平均方法提示了间歇脉冲结构空间分布的均匀性,Blob内部等离子体参数远高于背景等离子体参数,并且呈现出涡旋的形态。最后闭合磁面附近的数据显示,Blob的间歇爆发导致了边界约50%的粒子输运和能量输运。实验结果表明:相干结构在剪切层受到了扭曲,在刮削层区域沿离子的逆磁漂移方向传播。

HMDSO/H_2等离子体化学气相沉积非晶包覆纳米α-SiC薄膜的实验研究

本文利用六甲基二硅氧烷(HMDSO)作为先驱物质、氢气为稀释气体,进行了等离子体化学气相沉积碳硅薄膜的实验研究。运用X射线衍射、拉曼光谱、扫描电子显微镜和X射线光电子能谱对薄膜的成份和结构进行了分析。结果表明,在生长温度为750℃的条件下成功地得到了纳米-αSiC沉积,碳化硅晶粒被包覆在非晶的SiOxCy∶H成分中。薄膜由椭球状的颗粒组成,且随着HMDSO比例的增加,薄膜的结晶度和表面均匀性都得到改善。高流量氢气和HMDSO单体的使用被认为有效地促进了-αSiC晶体的形成。

EAST中性束注入快离子损失研究

利用经典导心轨道程序ORBIT,结合平衡程序EFIT和输运程序TRANSP,计算了EAST中性束注入后快离子的损失情况。结果表明,4MW(80keV)氘离子的损失份额为29%,2MW(50keV)氘离子的损失份额为31%,损失的快离子有很强的局域性。

面向聚变堆的托卡马克稳态先进运行模式的发展

人类文明和经济的持续快速发展有赖于新能源的发现和广泛应用。清洁、高效、几乎无尽的核聚变能源可以成为当前化石能源的有效替代,能够成为人类的终极能源。名为托卡马克(Tokamak)的磁约束装置是当前人类用于研究核聚变产生能源的主要方式之一。为了提高其运行的安全性和经济性,科学家们设计了多种能够使聚变等离子体长时间稳态运行的先进运行模式。这类运行模式的长足发展依赖于高温等离子体物理和核聚变相关技术等领域的研究进展,尤其是对于自举电流和外部驱动电流的研究。托卡马克稳态先进运行模式将成为未来国际热核聚变实验堆(International Thermonuclear Experimental Reactor,ITER)和中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)主要的运行模式。

Observation of Electron Energy Pinch in HT-7 ICRF Heated Plasmas

Inward energy transport （pinch phenomenon） in the electron channel is observed in HT-7 plasmas using off-axis ion cyclotron resonance frequency （ICRF） heating. Experimental results and power balance transport analysis by TRANSP code are presented in this article. With the aids of GLF23 and Chang-Hinton transport models, which predict energy diffusivity in experimental conditions, the estimated electron pinch velocity is obtained by experimental data and is found reasonably comparable to the results in the previous study, such as Song on Tore Supra. Density scanning shows that the energy convective velocity in the electron channel has a close relation to density scale length~ which is qualitatively in agreement with Wang＇s theoretical prediction. The parametric dependence of electron energy convective velocity on plasma current is still ambiguous and is worthy of future research on EAST.

Structural Evolution of SiC Films During Plasma-Assisted Chemical Vapour Deposition

Evolution of chemical bonding configurations for the films deposited from hexam- ethyldisiloxane （HMDSO） diluted with H2 during plasma assisted chemical vapour deposition is investigated. In the experiment a small amount of CH4 was added to adjust the plasma environment and modify the structure of the deposited films. The measurements of Raman spectroscopy and X-ray diffraction （XRD） revealed the production of 6H-SiC embedded in the amorphous matrix without the input of CH4. As CH4 was introduced into the deposition reaction, the transition of 6H-SiC to cubic SiC in the films took place, and also the film surfaces changed from a structure of ellipsoids to cauliflower-like shapes. With a further increase of CH4 in the flow ratio, the obtained films varied from Si-C bonding dominant to a sp^2/sp^3 carbon-rich composition.

零维系统模型改进及其对EAST稳态运行区的分析和预测

零维系统模型已广泛应用于下一代托卡马克装置设计以及聚变反应堆等离子体性能的预测和分析,但普遍采用物理近似和经验公式会导致较大的系统性误差.本文通过引入等离子体平衡程序使主要等离子体分布参数及其计算基于磁面信息,引入Sauter模型的自举电流系数与碰撞率变化关系改进自举电流计算,利用EAST上的实验结果对改进后的模型进行验证,零维系统模型计算结果与动理学平衡分析结果基本符合.利用改进模型从已有实验结果出发,对EAST上实现500 kA等离子体电流的稳态、长脉冲运行区所需要的加热/电流驱动功率及其能够达到的归一化比压进行了分析和预测.计算结果表明,EAST在7.0—9.5 MW加热/驱动功率,约束改善因子H98为1.25—1.35,归一化密度f_(nG)约为0.9的参数范围内可以实现500 kA等离子体电流且自举电流份额在50%以上的稳态运行;9.5 MW加热/驱动功率,H_(98)为1.0—1.4,f_(nG)为0.8—1.0的参数范围可以实现较高性能的长脉冲或稳态运行.综合来说,提升等离子体约束性能,可在较低的加热/驱动功率下实现同样等离子体参数的完全非感应运行,扩展等离子体运行区,是实现高参数等离子体稳态运行最为有效的途径.

Numerical study of fast ion behavior in the presence of magnetic islands and toroidal field ripple in the EAST tokamak

A peculiar first orbit loss type was found apart from the normal ones when we use ORBIT code to simulate fast ion orbits in the EAST tokamak. Fast ion orbits were studied in the presence of toroidal field （TF） ripple and magnetohydro- dynamic （MHD） perturbations. We analyzed the properties of the drifted orbits in detail and compared their differences, finding that the combined effects of ripple and magnetic islands are much greater than the effects of either one of them alone. Then we investigated the orbitdeviations as a function of pitch angle in different radial positions. The modeling results demonstrate that the loss of trapped particles is mainly caused by the ripple, while MHD＇perturbation mainly plays an important role in the passing particles. Furthermore we modeled the loss rate using different equilibriums. Results prove that a higher beta can indeed improve the confinement of fast ions, while a little change in the q profile can make the topologies of magnetic islands become quite different and results in quite different total particle losses.

Realization of minute-long steady-state H-mode discharges on EAST

In the 2016 EAST experimental campaign,a steady-state long-pulse H-mode discharge with an ITER-like tungsten divertor lasting longer than one minute has been obtained using only RF heating and current drive,through an integrated control of the wall conditioning,plasma configuration,divertor heat flux,particle exhaust,impurity management,and effective coupling of multiple RF heating and current drive sources at high injected power.The plasma current（Ip - 0.45 MA） was fully-noninductively driven（Vloop 〈 0.0 V） by a combination of-2.5 MW LHW,-0.4 MW ECH and -0.8 MW ICRF.This result demonstrates the progress of physics and technology studies on EAST,and will benefit the physics basis for steady state operation of ITER and CFETR.

Observation of Blobs and Holes in the Boundary Plasma of EAST Tokamak

Intermittent convective transport at the edge and in the scrape-off layer （SOL） of EAST was investigated by using fast reciprocating Langmuir probe. Holes, as part of plasma structures, were detected for the first time inside the shear layer. The amplitude probability distribution function of the turbulence is strongly skewed, with positive skewed events （＂blobs＂） prevailing in the SOL region and negative skewed events （＂holes＂） dominant inside the shear layer. The statistical properties coincide with previous observations from JET. The generation mechanism of blobs and holes is also discussed. In addition burst structure and dynamics character of them are also presented.

Reciprocating Probe Measurements of L-H Transition in LHCD H-Mode on EAST

As the power available in the initial phase of the ITER operation will be limited, accessing the high confinement mode （H-mode） with low heating power will be a critical issue. In the recent experiment on EAST, the H-mode was obtained for the first time with lower hybrid current drive （LHCD） wave only. Reciprocating Langmuir probe measurements at the outer midplane showed that the electron density ne and electron tempel：ature Te in the scrape-off layer （SOL） were significantly reduced in the ELM-free phase, resulting in the increase of lower-hybrid wave （LHW） reflection. It was found that the power loss Ploss was comparable during the L-H transition, by comparing the adjacent L-mode and H-mode discharge. The Da emission, Te and ne decreased rapidly in the time scale of about 1 ms, and the radial electric field Er turned positive in this process near the last closed flux surface. Multiple L-H-L transitions were observed during a single shot when the applied LHW power was marginal to the threshold. The floating potential （Vf） had negative spikes corresponding with the Da signal, and Er oscillation evolved into several intermittent negative spikes just before the L-H transition. In some shots, dithering was observed just before the L-H transition.

Simulations of Neutral Beam Ion Ripple Loss on EAST

Predictions on the ripple loss of neutral beam fast ions on EAST are investigated with a guiding center code, including both ripple and collisional effects. A 6% to 16% loss of neutral beam ions is predicted for typical EAST experiments, and a synergistic enhancement of fast ion loss is found for toroidal field （TF） ripples with collisions. The lost ions are strongly localized and will cause a maximum heat load of - 0.05 MW/m^2 on the first wall.

Alfvén Instabilities Excited by Energetic Particles in a Parameter Regime Similar to EAST Operation

The kinetic excitation of ideal magnetohydrodynamic （MHD） Alfvén instabilities is investigated for operations at the EAST tokamak. The instabilities include α-induced toroidal Alfvén eigenmodes （αTAE; here, α =-q2 Rdβ/dr, with q being the safety factor, β the ratio between the plasma and magnetic pressures, R the major radius, and r the minor radius）, toroidicity-induced Alfvén eigenmodes （TAE）, and the energetic particle continuum mode （EPM）. The αTAE, trapped by α-induced potential wells along the magnetic field line, can be readily destabilized by energetic particles due to negligible continuum damping via wave energy tunneling. It is shown for the geometry and the parameters similar to those of the EAST equilibrium that αTAE is different not only from the EPM by the potential-well determined frequency, but also from the TAE by the broad frequency spectrum outside the toroidal frequency gap.

Numerical and Experimental Evaluation of Shine-Through Loss and Beam Heating Due to Neutral Beam Injection on EAST

This research applies experimental measurements and NUBEAM,ONETWO and TRANSP modules to investigate the shine-through(ST)loss ratio and beam heating percentage of neutral beam injection on EAST.Measurements and simulations confirm that the ST loss ratio increases linearly with beam energy,and decreases exponentially with plasma density.Moreover,using the multi-step fitting method,we present analytical quantitative expressions of ST loss ratio and beam heating percentage,which are valuable for the high parameter long-pulse experiments of EAST.

Intermittent Bursts in the Boundary Plasma of HT-7

Intermittent characteristics of turbulence induced by coherent structures （blobs） was clearly observed in the ion saturation current signal, density fluctuation, particle flux and heat flux in HT-7. It is obvious that ion saturation current signal has deviated from Gaussian distribution and the skewness （S） and flatness （K） of signal increase radially outwards in the scrape-off layer （SOL）. Using conditional analysis （CA）, asymmetric character of the intermittent bursts are demonstrated. Owing to the radial propagation of the coherent structures, the particle density profile in SOL is non-exponential and flat outwards from the last close flux surface （LCFS）. It is found around LCFS that the large burst fluctuations （above 2.5 rms） are responsible for about 50% of the total particle transport. Burst events move radially outwards with Ee ~ B velocity, and the blob size can be calculated as 5r ~ V^rc. Our experiment shows that the blob size, life time and drift velocity experienced a pronounced decorrelation in the shear layer. The electrostatic Reynolds stress components become very strong and show a radially steep gradient in the proximity of the shear layer. These experimental findings may imply that the coherent structures are titled by the developed shear flow in the E × B shear layer.

Fishbone Mode Excited by Deeply Trapped Energetic Beam Ions in EAST

This paper describes the fishbone mode phenomena during the injection of highpower neutral beams in EAST（Experimental Advanced Superconducting Tokamak）.The features of the fishbone mode are presented.The change in frequency of the mode during a fishbone burst is from 1 kHz to 6 kHz.The nonlinear behavior of the fishbone mode is analyzed by using a prey-predator model,which is consistent with the experimental results.This model indicates that the periodic oscillations of the fishbone mode always occur near the critical value of fast ion beta.Furthermore,the neutral beam analysis for the discharge is done by using the NUBEAM module of the TRANSP code.According to the numerical simulation results and theoretical calculation,it can be concluded that the fishbone mode is driven by the deeply trapped energetic beam ions in EAST.

Neutron Yields Based on Transport Calculation in EAST ICRF Minority Heating Plasmas

Neutron diagnostics, including flux and energy spectrum measurements, have been applied on the experimental advanced superconducting tokamak （EAST）. The absolute calibration of neutron yields has been achieved by a calculation method using the Monte Carlo automatic modeling （MCAM） system and the Monte Carlo N-Particles （MCNP） code. Since the neutron yield is closely related with the ion density and temperature, it is a good measure of plasma performance, especially the wave heating effect. In ion cyclotron range of frequencies （ICRF） experiments, the increase in the ion temperature derived by the neutron yield indicates an effective plasma heating. Minority protons damp a large fraction of the total wave power, and then transfer part of the energy to deuterium by collisions. Neutron spectrum measurements also indicate that no tail is created by high energy deuterons during ICRF heating. However, the ion temperature derived by the neutron yield is consistent with the result by using a poloidal X-ray imaging crystal spectrometer （PXCS）, showing a reliable transport calculation.

Estimation of Neutral Density in Edge Plasma with Double Null Configuration in EAST

In this work, population coefficients of hydrogen＇s n = 3 excited state from the hydrogen collisional-radiative （CR） model, from the data file of DEGAS 2, are used to calculate the photon emissivity coefficients （PECs） of hydrogen Balmer-α （n = 3 →n = 2） （Hα）. The results are compared with the PECs from Atomic Data and Analysis Structure （ADAS） database, and a good agreement is found. A magnetic surface-averaged neutral density profile of typical double-null （DN） plasma in EAST is obtained by using FRANTIC, the 1.5-D fluid transport code. It is found that the sum of integral Dα and Hα emission intensity calculated via the neutral density agrees with the measured results obtained by using the absolutely calibrated multi-channel poloidal photodiode array systems viewing the lower divertor at the last closed flux surface （LCFS）. It is revealed that the typical magnetic surface-averaged neutral density at LCFS is about 3.5×10^16 m^-3 .

A Dip Structure in the Intrinsic Toroidal Rotation Near the Edge of the Ohmic Plasmas in EAST

Ion＇s toroidal velocity, vt, in both the outermost 4 cm of the confined region and the scrap-off layer of Ohmic L-mode plasmas in EAST was measured using Mach probes. At about 1 cm inside the separatrix a local minimum in vt was observed, from which a cocurrent rotation increased both inwards and outwards. The radial width of the vt dip was 1 cm to 2 cm, and both the density and electron temperature profiles exhibited steep gradients at this dip position. It was observed in both divertor and limiter configurations. To find out its origin, the toroidal torques induced by neutral friction, neoclassical viscosity, collisional perpendicular shear viscosity, ion orbit loss and turbulent Reynolds stress were estimated using the measured parameters. Our results indicate that in this particular parameter regime the neutral friction was the dominant damping force. The calculated cocurrent toroidal torque by the neoclassical viscosity dominates over those from the collisional perpendicular shear viscosity, ion orbit loss and turbulent Reynolds stress. These results are potentially important for the understanding of boundary conditions for the intrinsic toroidal momentum in tokamak plasmas.

Divertor Plasma Properties for a Lower Single-Null Discharge in EAST

Divertor plasma properties for lower single-null （LSN） configuration in EAST, under a water-cooling graphite wall condition, are presented. A typical shot is selected for analyzing electron temperature, density and power flux at targets. Both higher electron density and lower electron temperature are found at the inboard target, compared to those at the outboard target. A higher power flux is also found to be at the outboard target because of in-out asymmetries for LSN-shaped discharge.