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利用红外相机对HL-2A装置外偏滤器靶板的表面温度进行了测量,得到了具有一定时空分辨的红外热图。用一维热传导模型对热点处的温升进行数据处理,得到了轰击点上的热负荷演变曲线。分别对辐射偏滤器、ECRH加热、中性束注入、破裂四种放电情况下的热负荷曲线进行了分析,并就辐射偏滤器和破裂两种放电的热负荷与靶板探针测得的结果进行了比较。     

Investigation of lower hybrid current drive during H-mode in EAST tokamak

H-mode discharges with lower hybrid current drive (LHCD) alone are achieved in EAST divertor plasma over a wide parameter range. These H-mode discharges are characterized by a sudden drop in D_α emission and a spontaneous rise in main plasma density. Good lower hybrid (LH) coupling during H-mode is obtained by putting the plasma close to the antenna and by injecting D₂ gas from a pipe near the grill mouse. The analysis of lower hybrid current drive properties shows that the LH deposition profile shifts off axis during H-mode, and current drive (CD) efficiency decreases due to the increase in density. Modeling results of H-mode discharges with a general ray tracing code GENRAY are reported.     

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。     

边界局域模对EAST钨偏滤器靶板腐蚀程度的数值模拟研究

在高约束模式下发生的边界局域模会释放高能量等离子体,其中主要部分会辐照到面积相对较小的偏滤器靶板,偏滤器钨靶板发生热腐蚀的可能性最大.本文建立了包括了熔化、汽化和热辐射效应的一维热传导模型,采用数值模拟的方法,研究了EAST未来偏滤器钨靶板在边界局域模作用下的热腐蚀程度.根据现有的边界局域模热流数据和多种未来可能的高能量边界局域模热流数据,计算了钨靶板的表面温度分布.结果显示当前的第一类边界局域模作用在钨靶板上,在高约束模式运行时间取32 s情况下,靶板表面温度从350 K增加到373 K,表明在当前的参数范围内,只要避免其他更严重的瞬时事件如破裂的发生,边界局域模还不会带来严重的威胁;如果边界局域模的能量增加到接近未来托卡马克边界局域模的能量范围1 MJ/m2,沉积时间为600μs,表面最大熔化厚度将达到6.8—6.9μm.     

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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介绍了EAST装置上的384道(极向24道径向16道)的外差混频式电子回旋辐射成像诊断系统及其在EAST及其复杂的电磁环境中的运行情况。在低杂波电流驱动期间,高灵敏度的电子回旋辐射成像系统受到严重干扰以至于无法提供正确的实验数据。通过优化系统各模块的接地、外加多层铜网屏蔽等措施,使得ECEI系统屏蔽效能与改善之前相比提高了40dB,基本保障了EAST装置上电子回旋辐射成像诊断的正常工作。     

EAST 装置电子回旋辐射二维成像系统的屏蔽优化

介绍了EAST 装置上的384 道(极向24 道径向16 道)的外差混频式电子回旋辐射成像诊断系统及其在EAST 及其复杂的电磁环境中的运行情况。在低杂波电流驱动期间,高灵敏度的电子回旋辐射成像系统受到严重干扰以至于无法提供正确的实验数据。通过优化系统各模块的接地、外加多层铜网屏蔽等措施,使得ECEI 系统屏蔽效能与改善之前相比提高了40dB,基本保障了EAST 装置上电子回旋辐射成像诊断的正常工作。     

HL-2M装置常规偏滤器与雪花减偏滤器热工水力分析对比

采用SOLPS程序模拟预测HL-2M装置常规和雪花减偏滤器靶板上的热通量。当流入边缘等离子体区域的热功率约为10MW时,利用CFX/ANSYS软件分析这两类偏滤器各结构、冷却水温度分布及形变和热应力分布情况。结果表明:等离子体总功率相同,雪花减偏滤器靶板上的最高温度比常规偏滤器低169℃;雪花减偏滤器结构所承受的最大热应力和形变比常规偏滤器低约3/7。不改变热负载剖面分布,按一定比例提升热流密度或延长放电时间,雪花减偏滤器体现出比常规偏滤器靶板温升低、冷却水温均衡等优点。因此,雪花减偏滤器能处理更多流进偏滤器区域的热能,有效地降低偏滤器工程设计要求。     

EAST 钨偏滤器外靶板热工水力分析

为提高EAST 偏滤器的抗热载和排热能力,将偏滤器第一壁的材料由原来的石墨改为钨,在结构上,靶板采用了类ITER 的单块结构,支撑和冷却采用一体化的盒式结构。确定了EAST 钨偏滤器的冷却结构后,通过水管的流固耦合传热模型,分析了外靶板在紊流冷却方式下的散热情况。同时计算了在水冷系统失效的情况下,偏滤器外靶板的危险区域在3、5、8、10MW·m^-2 热流密度下的瞬态温度分布情况。结果表明,水流速度在4m·s^-1 时, 水管可以承受峰值功率10MW·m^-2 的热流密度,能够很好地满足EAST 装置运行的排热要求。     

Impact of Sheath Boundary Conditions and Magnetic Flutter on Evolution and Distribution of Transient Particle and Heat Fluxes in the Edge-Localized Mode Burst by Experimental Advanced Superconducting Tokamak Simulation

To study the evolution and distribution of the transient particle and heat fluxes during the edge-localized modes(ELMs) burst on the experimental advanced superconducting tokamak(EAST), the BOUT++six-field two-fluid model with sheath boundary conditions(SBCs) and magnetic flutter terms in the parallel thermal conduction is used to simulate the evolution of the profiles and growing process of the fluxes at divertor targets. Although SBCs hardly play a role in the linear phase, in the nonlinear phase both SBCs and magnetic flutter can change the dominant toroidal mode. SBCs are able to broaden the frequency distribution of the turbulence. The magnetic flutter increases the ELM size from 2.8% to 8.4%, and it doubles the amplitudes of the radial heat and particle transport coefficients at outer midplane(OMP), at around 1.0 m~2 s~(-1). It is then able to increase the particle and heat flux at the divertor targets and to broaden the radial distribution of the parallel heat flux towards the targets.     

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In order to improve the anti-thermal load and heat dissipation performance of the divertor of EAST, its first wall material is changed to tungsten from graphite. In the structure, outer target adopts the ITER-like monoblock, bracing and cooling structure adopts incorporate cassette. After establishing the cooling structure of EAST tungsten divertor, the flows-solid coupling heat conduction model of water-pipes is used to analyze the heat dissipation situation of outside target in the form of turbulent flow. While the cooling system comes to failure, a series of heat flux value 3MW·m^-2, 5MW·m^-2, 8MW·m^-2, 10MW·m^-2 are applied in the hazardous area to analyze transient conditions and real temperature distribution. The results shows that if the water flows at 4m·s^-1, the cooling pipes can withstand the heat flux with peak power in 10MW·m^-2. It can well meet the needs in heat dissipation of EAST experiment.     

东方超环托卡马克高约束模式边界等离子体输运数值模拟研究

利用SOLPS5.0模拟研究东方超环托卡马克（EAST）高约束模式时的刮削层等离子体. 在高约束模式放电实验参数（第36291炮）的限制下,通过调整上游区径向反常输运系数来实现高约束模式模拟,在上游电子密度和温度与实验符合的条件下能够很好地进行下游区模拟. 在实现高约束模拟的基础上又分别研究了漂移项对偏滤器靶板能流不对称性的影响和上游能流衰减宽度对靶板能流密度峰值的影响. 通过模拟发现,漂移是导致EAST放电内外靶板不对称性的主要原因,增大上游能流衰减宽度可以明显降低入射到靶板的峰值热流,并且偏滤器区辐射以及与中性粒子的相互作用减小了能流的衰减宽度对达到靶板能流的影响. 关键词： 托卡马克 高约束模式 SOLPS5.0 漂移     

东方超环上低杂波驱动等离子体环向旋转实验研究

旋转和旋转剪切能抑制磁流体不稳定性和增强等离子体约束.低杂波电流驱动作为未来聚变堆上可能的旋转驱动手段,探索低杂波在现有托卡马克装置上驱动等离子体旋转的驱动机制,可以为未来的聚变堆上旋转预测提供重要参考.在东方超环托卡马克装置上,早期发现了2.45 GHz的低杂波能有效驱动等离子体旋转的现象,认为是边界旋转的改变导致芯部旋转的同电流方向的增加造成的.更高频率下4.6 GHz低杂波电流驱动可以更有效地驱动同电流方向的等离子体旋转.本论文分析在欧姆背景等离子体下,不同功率的低杂波对等离子体环向旋转的影响,研究安全因子剖面变化对环向旋转的关系,利用功率调制获得了低杂波驱动旋转实验中的环向动量输运系数变化情况,发现环向动量扩散系数(χφ)、环向动量箍缩系数(Vpinch)的数值大小趋势是从芯部向靠外的区域逐渐变大.这与低杂波驱动环向旋转时,环向旋转速度由靠外的区域向芯部传递的特性吻合.     

Modeling of Large ELM Suppressions for High Confinement Plasma in D Ⅲ-D

The H-mode discharges with high edge pressure gradients are expected for the economic feasibility of future fusion reactors. However, the high edge pressure gradients easily produce ELM instability , which generally can expel large, heat and particle loading to the divertor targets. These ELMs limit the core plasma performance and reduce the lifetime of divertor target plates. The transports of heat and particles outward across plasma boundary are useful to control density and impurity profiles for achieving steady state, high performance plasmas. Consequently, any technique to eliminate or mitigate large fast ELM impulses must replace the transient heat and particle transports with another slow process. Such a technique is high priority for a burning plasma device such as ITER.     

COMPASS-D magnetic equilibria with lh and NBI current drive

Plasma equilibria are investigated numerically, using the ACCOME and ASTRA codes, on the COMPASS-D tokamak (R ₀ = 0:56 m, a = 0:17 m, B _T = 1:2 T, I _p = 200 kA, k = 1:7, δ_x = 0:4) for the planned Neutral Beam Injection (NBI) and Low Hybrid Current Drive (LHCD) systems. The LH system provides P _LH = 0:4 MW at n _∥ = 2:1 and f _LH = 1:3 GHz. The NBI system has two 40 keV deuterium beams in co-or counter-directions with a total power of 0.6 MW. The COMPASS-D tokamak can typically operate in two configurations-single null divertor (SND) and single null divertor with a higher triangularity (SNT). Higher triangularity provides access to higher confinement and improved stability, and leads to larger n _∥ up-shifts for better slow LH wave absorption.We investigate the range of densities n = 2 ÷ 6 × 10¹⁹ m^?3. Both the LH and NB driven currents decrease with density. The magnetic shear reverses with off-axis beam incidence. In the given plasma parameter range, typically up to 60 kA of bootstrap current is driven and with NB co-injection up to 80 kA of NB current is driven. LHCD is weak at f = 1:3 GHz and BT = 1:2 T, but at n = 3 × 10¹⁹ m^?3 the LH driven current is about 40 kA, so that the required plasma current of 200 kA is supported almost non-inductively.     

Features of the repetition frequency of edge localized modes in EAST

This paper presents the features of the edge localized modes (ELMs) observed in the 2010 experimental campaign on the Experimental Advanced Superconducting Tokamak (EAST). The first high-confinement mode (H-mode) at an H-factor of H_{IPB98(y, 2)}～ 1 has been obtained with about 1 MW lower hybrid wave (LHW) heating power on the EAST tokamak. The ELMs in EAST are Type III ELMs with high frequency (several hundred Hertz) and low amplitude. ELM features for the following two types of EAST discharges are investigated: discharges with only LHW and those with both LHW and ion cyclotron resonance frequency (ICRF) wave. The ELMs are observed in a wide q ₉₅ window ranging from 2.6 to 5.0, and the ELM frequencies decrease with the safety factor, q ₉₅. In contrast to most observations, the ELM frequency in EAST appears to be weakly proportional to the power through the separatrix. When the ICRF wave is injected, the ELM frequency increases. The control of the ELM frequency and amplitude has been achieved by puffing impure argon gas into the EAST discharge.     

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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.     

Experimental investigation on divertor tungsten sputtering with neon seeding in ELMy H-mode plasma in EAST tokamak

Neon (Ne) seeding is used to cool the edge plasma by radiation to protect the divertor tungsten (W) target in the Experimental Advanced Superconducting Tokamak (EAST). The W sputtering in the outer divertor target with Ne seeding is assessed by the divertor visible spectroscopy system. It is observed that the W sputtering flux initially increases with Ne concentration in the divertor despite the decreasing plasma temperature. After reaching a maximum around 25 eV, the W sputtering rate starts to decrease, presenting a suppression effect. The effect on the divertor W sputtering flux and yield due to the competition between the increase of the Ne concentration and the decrease of the plasma temperature is discussed. The results show that enough Ne seeding is essential to effectively reduce the electron temperature and thus to suppress W sputtering. Moreover, ELM suppression is observed when Ne and W impurities enter the core plasma, which could be correlated to the enhanced turbulence transport in the pedestal.     

L–H power threshold studies with tungsten/carbon divertor on the EAST tokamak

The power threshold for low (L) to high (H) confinement mode transition achieved by radio-frequency heating and molybdenum first wall with lithium coating has been experimentally investigated on the EAST tokamak for two sets of divertor geometries and materials: tungsten/carbon divertor and full carbon divertor. For both sets of divertors, the power threshold was found to decrease with gradual accumulation of the lithium wall coating, suggesting the important role played by the low Z impurities and/or the edge neutral density on the L–H power threshold. When operating in the upper single null configuration, with the ion grad-B drift direction away from the primary X-point, a lower normalized power threshold is observed in EAST with the tungsten/carbon divertor, compared to the carbon divertor after intensive lithium wall coating. A newly installed cryopump increasing the pumping efficiency also plays an important part in the observed lower threshold. In addition, the H-mode in the Quasi-Snowflake divertor configuration has been obtained on EAST, exhibiting higher L–H power threshold compared to the lower single null configuration with similar I_P/B_T pairs.