极紫外波段Ar光谱分析在EAST偏滤器杂质屏蔽效应研究中的应用

在托卡马克偏滤器区域充入杂质气体是检验偏滤器杂质屏蔽效应的重要手段。利用快速极紫外EUV光谱仪对EAST托克马克装置上开展的偏滤器Ar杂质注入实验进行观测。结合NIST原子光谱数据库对2～50 nm范围内不同电离态Ar的线光谱进行了谱线识别,识别出Ar Ⅳ,Ar Ⅸ-Ⅺ,Ar ⅩⅣ-ⅩⅥ等若干个电离态的谱线。为了同时观测等离子体不同区域的Ar杂质行为,在杂质注入实验时重点监测Ar ⅩⅥ35.39 nm(Ar ⅩⅥ电离能918.4 eV,主要分布在等离子体芯部)和Ar Ⅳ44.22 nm(Ar Ⅳ电离能9.6 eV,主要分布在等离子体边界)这两条谱线。利用该两条谱线强度随时间演化的结果初步分析了偏滤器杂质屏蔽效应。在同一充气口不同等离子体位形下的实验结果表明偏滤器对于从偏滤器区域注入Ar杂质的屏蔽效果优于从主等离子体区域注入,并且下偏滤器及内冷泵的综合粒子排除能力优于上偏滤器。     

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.     

Study of multiple impurity seeding effect using SONIC integrated divertor code for JT-60SA plasma prediction

In order to study the potential impurity seeding operation regime of the future fusion devices, the first application of the integrated divertor code SONIC to the Ar + Ne mixed-impurity seeding operation of JT-60SA steady-state high-β plasma has been carried out. In the case, Ne is added to Ar-only seeding, the separatrix electron density has fell into the desired low separatrix electron density of the scenario. This is mainly because the D⁺ flow velocity towards the inner divertor has been increased by the Ne seeding. The resultant friction force transports Ar impurities towards the inner divertor region, while impurities are stagnated in the top of scrape-off layer (SOL) in the Ar-only seeding case. The higher impurity radiation power in the divertor regions and lower one in the SOL region above the X point have been obtained in mixed-impurity seeding cases, which show similar tendency as the Ar + Ne mixed-impurity seeding experiment in JT-60 U. At the core edge, Z_eff has been slightly increased and the radiation power has been decreased as the Ne seeding rate increases. The core plasma/impurity transport has been also evaluated by the TOPICS code using the impurity density at the core edge computed by the SONIC as a boundary parameter. The results show lower Z_eff and radiation power, and higher electron temperature in the core in the mixed-impurity seeding cases. Above possible contributors to the better energy confinement indicate that the mixed-impurity seeding operation might be more effective than Ar-only seeding operation.     

Evolution of the high-field-side radiation belts during the neon seeding plasma discharge in EAST tokamak

Divertor detachment achieved by injecting impurities or increasing density is always accompanied with various local radiation phenomena in the boundary or core plasma. This paper presents the formation and evolution of the high-field-side (HFS) radiation belts during the neon seeding plasma discharge in upper single null configuration with two directions of toroidal magnetic field in EAST tokamak. The neon mixed with deuterium seeding can induce the divertor detachment with strong radiation belts in the HFS scrape-off layer (SOL) region. With the increase of the radiation power, the plasma discharge will transit from H-mode to L-mode, and meanwhile the radiation belts move away from the near X-point to HFS SOL. When the radiation power is high enough, the radiation belts begin to move further to the other X-point along the HFS SOL, and even cause plasma disruption. The results indicate that the behavior of the radiation belts is related to the radiation power, plasma confinement performance and state of divertor detachment, which is useful for developing better feedback control methods to achieve high-performance radiative divertor operation mode.     

HL-2A装置上边界间歇性事件与湍流粒子输运的统计学研究

通过对粒子概率分布函数的计算,发现在高等离子体密度下边界间歇性事件的爆发频率有所增加。通过条件平均的手段,正负间歇性事件得以区分,并发现了二者在空间上的不同特征。不同密度梯度下的湍流粒子输运计算表明,间歇性事件与湍流粒子输运之间存在密切联系,间歇性事件的存在能够大大增加湍流粒子输运的大小。在高等离子体密度时,间歇性事件的强度有所增加,而与之相应地,湍流粒子输运的大小也有所增强。     

经典漂移对EAST钨杂质产生和输运特性影响的模拟研究

本文采用蒙特卡罗杂质输运程序DIVIMP,针对先进实验超导托卡马克(EAST)的上单零位形放电,模拟研究了不同漂移情况下(无漂移、离子BíB漂移向下/上)的钨杂质产生和输运特性。结果表明,经典漂移显著影响了钨杂质自偏滤器靶板的溅射通量及其在上游区域的含量。     

EAST边界和芯部杂质谱线的时间延迟研究

边界杂质注入是未来聚变装置ITER用于增强边界辐射，减少第一壁热负荷的一种重要方法。但部分注入的杂质会被输运到芯部，造成主等离子体辐射损失以及约束下降。光谱观测可以获取杂质种类、含量和分布等信息，在理解等离子体中杂质输运方面起着重要作用。在EAST（experimental advanced superconducting tokamak）偏滤器氩气（Ar）注入实验中，利用偏滤器可见光谱和芯部极紫外光谱监测边界的Ar1+离子谱线Ar Ⅱ(401.36 nm)和芯部的Ar15+离子谱线Ar ⅩⅥ(35.39 nm)，并获得两者强度随时间的变化。其中，Ar Ⅱ和Ar ⅩⅥ的电离能分别为27和918 eV，因此，Ar Ⅱ和Ar ⅩⅥ分别对应分布于等离子体边界和芯部Ar离子。为了分析二者谱线强度随时间变化的特征，发展了一种基于正则Pearson积矩相关系数的相关分析方法，计算得到两者谱线强度变化的相对延迟时间，以此表征杂质从边界向芯部输运的时间。结果显示，偏滤器注入Ar杂质后，芯部Ar ⅩⅥ辐射增长滞后于边界Ar Ⅱ辐射的增长，并且在具有较高的低杂波加热功率的放电中，两者的延迟时间较长，表明较高的低杂波加热功率可以延长杂质从边界向芯部输运的时间。     

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。     

偏滤器等离子体中杂质对钨壁材料的侵蚀模拟研究

偏滤器是托卡马克中与等离子体直接接触的部件,为了保证装置的寿命,需要尽可能地减小等离子体对偏滤器靶板的侵蚀.本文用粒子模拟的方法研究了不同等离子体温度情况下碳和铍两种杂质离子对钨偏滤器侵蚀速率的影响.模拟首先得到稳定的鞘层结构、入射到靶板的离子流和能流密度,并通过统计获得了入射离子的能量和角度分布,最终根据这些物理参量,采用经验公式计算出钨靶板的侵蚀速率.研究表明,在等离子体温度不太高的情况下,钨靶板的热侵蚀几乎不起作用,而由于杂质离子对钨的物理溅射阈值较低,并且会通过鞘层加速获得能量,因此其对钨壁材料的物理溅射是导致靶板侵蚀的主要原因,另外靶板材料的侵蚀速率随着等离子体温度升高以及杂质含量增大而急剧增大.     

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.     

EAST远红外激光干涉仪与密度爬升实验研究

利用EAST装置单道远红外HCN激光干涉仪测量了等离子体中心道(R=1.82m)线平均电子密度。通过充气加料连续提升主等离子体密度,首次在EAST装置上观察到偏滤器等离子体的三种不同状态：低再循环(偏滤器靶板处等离子体温度较高,密度较低),高再循环(偏滤器靶板处等离子体温度较低,密度较高)和脱靶(偏滤器靶板处等离子体温度和密度都很低)等离子体状态。分析了EAST偏滤器在这三种不同状态下的物理现象。     

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利用EAST装置单道远红外HCN激光干涉仪测量了等离子体中心道(R=1.82m)线平均电子密度。通过充气加料连续提升主等离子体密度,首次在EAST装置上观察到偏滤器等离子体的三种不同状态：低再循环(偏滤器靶板处等离子体温度较高,密度较低),高再循环(偏滤器靶板处等离子体温度较低,密度较高)和脱靶(偏滤器靶板处等离子体温度和密度都很低)等离子体状态。分析了EAST偏滤器在这三种不同状态下的物理现象。     

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.     

Accounting for Edge-Plasma Parameter Dynamics at JET Divertor Sputtering Estimation during Edge-Localized Modes

Physics of Atomic Nuclei - The sputtering of tungsten divertor tiles at the JET ITER-like wall (ILW) during edge-localized modes (ELMs) is one of the main sources of tungsten impurity in the core...     

CFETR不同位置充气下的辐射偏滤器模拟研究

利用边缘等离子体数值模拟程序SOLPS对氩杂质注入下中国聚变工程试验堆装置辐射偏滤器运行模式进行了模拟研究。在达到相同的总辐射功率(P_rad~170MW)时,四种不同充气方案下(从上游充入氘氩混合气体,从外偏滤器充入氘氩混合气体,从内偏滤器充入氘氩混合气体,从上游充入氘气的同时从外偏滤器充入氩气) 在外中平面的模拟区域内边界(ρ=0.9)处的有效离子电荷数Zeff分别为2.8、3.1、3.4、2.7。模拟结果与DIII-D及C-MOD的实验结论一致。当从上游充入氘气时,可以增强刮削层中的本底等离子体流,从而得到相对更好的杂质屏蔽效果;同时由于偏滤器靶板再循环杂质源占主导作用,注入氩气的位置对于模拟结果影响不大。     

Numerical analysis of high Mach flow and flow reversal in the experimental advanced superconducting tokamak divertor

The B2-Eirene (SOLPS 4.0) code package is used to investigate the plasma parallel flow, i.e., the scrape-off layer (SOL) flow, in the experimental advanced superconducting tokamak (EAST) divertor. Simulation results show that the SOL flow in the divertor region can exhibit complex behaviour, such as a high Mach flow and flow reversal in different plasma regimes. When the divertor plasma is in the detachment state, the high Mach flow with approaching or exceeding sonic speed is observed away from the target plate in our simulation. When the divertor plasma is in the high recycling state, the flow reversal with a small Mach number (|M|< 0.2) is observed near the X-point along the separatrix region. The driving mechanisms for the high Mach flow and the reversed flow are analysed theoretically through momentum and continuity equations, respectively. The profile of the ionization sources is shown to be a possible formation condition causing the complex behaviour of the SOL flow. In addition, the effects of the high Mach flow and the flow reversal on the impurity transport are also discussed in this paper.     

Diagnostics for first plasma study on EAST tokamak

The first plasma was obtained in the EAST on September 26th, 2006. Single-null (SN) and double-null (DN) diverted plasmas were achieved successfully in the EAST tokamak on January 22nd, 2007. The employed plasma diagnostics for first plasma study of EAST are as follows: a vertical one-channel far-infrared (FIR) hydrogen cyanide (HCN) laser interferometer for measuring the line average density, a 10-channel soft X-ray array for intensity measurement, a 16-channel heterodyne Electron Cyclotron Emission (ECE) for measuring the electron temperature profile, a 8-channel XUV bolometer array to measure plasma radiation losses, a 3-channel hard X-ray array for intensity measurement, an electromagnetic measurement system, a 35-channel Hα radiation array, 20 probes for divertor plasma, a one-channel visible bremsstrahlung emission, an impurity optical spectrum measurement system and two optical spectroscopic multi-channel analyzers (OMA). The first experimental results of diagnostic systems are summarized in this Letter.     

First observation of edge localized modes mitigation with resonant and nonresonant magnetic perturbations in ASDEX Upgrade

First experiments with nonaxisymmetric magnetic perturbations, toroidal mode number n=2, produced by newly installed in-vessel saddle coils in the ASDEX Upgrade tokamak show significant reduction of plasma energy loss and peak divertor power load associated with type-I edge localized modes (ELMs) in high-confinement mode plasmas. ELM mitigation is observed above an edge density threshold and is obtained both with magnetic perturbations that are resonant and not resonant with the edge safety factor profile. Compared with unperturbed type-I ELMy reference plasmas, plasmas with mitigated ELMs show similar confinement, similar plasma density, and lower tungsten impurity concentration.     

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。     

EAST快速极紫外光谱仪波长的原位标定及其应用

介绍了东方超环(experimental advanced supereonducting tokamak, EAST)托卡马克上的两套快速极紫外（EUV）光谱仪系统波长的原位标定方法、结果及其应用。这两套谱仪均为掠入射平场谱仪，时间分辨均为5 ms·frame-1。两套谱仪分别工作在20～500和10～130 Å的波段范围，由步进电机控制探测器在焦平面上移动实现整个观测波段上的波长扫描。利用这两套谱仪系统观测极紫外波段光谱，计算EAST中低-高Z杂质离子特征线辐射强度随时间的演化，监测和研究等离子体中杂质的行为。高Z杂质尤其是钨、钼等金属元素，发出的EUV波段光谱的构成非常复杂，准确识谱对谱仪精确的波长测量能力以及谱分辨能力要求很高，因此精确的波长标定是识别钨、钼等高Z杂质谱线以及研究它们行为的最关键的技术之一。利用EAST等离子体中类氢到类铍的低、中Z杂质的特征谱线以及它们的二阶甚至三阶谱线，结合谱仪系统的色散能力，对这两套快速极紫外光谱仪的波长进行了精确的原位标定。用于波长标定的杂质谱线有O Ⅷ 18.97 Å，O Ⅶ 21.60 Å，C Ⅵ 33.73 Å，Li Ⅲ 113.9 Å，Li Ⅲ 135.0 Å，Li Ⅱ 199.28 Å，Ar ⅩⅤ 221.15 Å，He Ⅱ 256.317 Å，He Ⅱ 303.78 Å，Ar ⅩⅥ 353.853 Å及C Ⅳ 384.174 Å等。利用波长标定的结果对观测到的EUV光谱进行谱线识别，两套谱仪观测到的绝大多数谱线波长与美国技术标准局(National Institute of Standards and Technology, NIST)数据库的标准波长相差分别小于0.08和0.03 Å。开发了谱仪波长原位标定程序模块，将这个模块内嵌到谱仪数据实时上传的交互式软件中，实现了全谱数据以及特征谱线强度随时间演化数据的实时处理和上传。同时利用开发的全谱分析交互式软件以及EAST上的数据查看软件，最终实现了快速EUV谱仪自采数据的准实时分析、读取和查看。