低杂波驱动电流改善等离子体约束的光谱测量

在ＨＴ－６Ｂ托卡马克低杂波驱动电流（ＬＨＣＤ）的同时，等离子体的粒子及能量约束也随之发生改善。我们从空间多道Ｈα线的测量推算出ＬＨＣＤ可将等离子体粒子约束时间提高１－５倍，介绍了我们的分析过程，ＨＴ－６Ｂ上的Ｈα线测量还表明粒子约束的改善程度与低杂波（ＬＨＷ）的注入功率无明显依赖关系；改善粒子约束的发生与超热电子的产生相对应，通过观察边界层ＯＩＩ两条不同激发电位的谱线强度比的变化，发现等离子体在约束改善的同时，具有边界电子温度梯度增大的类Ｈ模现象。 关键词：     

HL－1托卡马克杂质注入实验及杂质输运特性的研究

本文给出了ＨＬ－１托卡马克在通常欧姆放电和偏压诱发Ｈ模放电条件下，脉冲注入杂质气体的实验结果以及对杂质在通常欧姆等离子体和偏压诱发Ｈ模等离子体中的输运研究结果。实验结果表明，在ＨＬ－１上偏压诱发Ｈ模等离子体中对杂质的约束性能明显优于在通常欧姆等离子体中对杂质的约束性能。杂质输运的数值模拟结果说明，无论在通常欧姆等离子体中，还是在偏压诱发Ｈ模等离子体中，杂质的输运系数都比新经典理论预计的要大得多，输运是反常的。在偏压诱发的Ｈ模等离子体中引入杂质输运“位阱”概念，能够对杂质离子约束时间长的实验现象进行很好的描述。合理地解释了在偏压杂质注入实验中杂质辐射上升时间长、衰减慢的现象。     

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在HL-2A装置孔栏位形放电的等离子体实验中,电子回旋辅助加热期间观察到了等离子体约束改善的现象,并对等离子体从低约束模式(L模)向约束改善模式转换时的等离子体线平均电子密度、等离子体储能、分界面内辐射功率、能量约束时间、Hα辐射等进行了研究。同时,分析了电子密度和等离子体辐射功率的空间分布随时间的演化。对改善约束的相关功率(辅助加热、欧姆加热功率和损失功率)进行了分析,并研究了等离子体约束改善转换时的边界净输入功率(阈值)与电子线平均密度和环向磁场的关系。     

HL-2A装置的约束改善和边界净输入功率分析

在HL-2A装置孔栏位形放电的等离子体实验中,电子回旋辅助加热期间观察到了等离子体约束改善的现象,并对等离子体从低约束模式(L模)向约束改善模式转换时的等离子体线平均电子密度、等离子体储能、分界面内辐射功率、能量约束时间、H_α辐射等进行了研究。同时,分析了电子密度和等离子体辐射功率的空间分布随时间的演化。对改善约束的相关功率(辅助加热、欧姆加热功率和损失功率)进行了分析,并研究了等离子体约束改善转换时的边界净输入功率(阈值)与电子线平均密度和环向磁场的关系。     

HL—1M装置波加热和加料等离子体的辐射损失特性

等离子体的杂质将对等离子体的能量平衡产生很大的影响,杂质的增多将增加辐射损失功率,降低等离子体温度,使得等离子体约束性能变差。由于等离子体辐损失功率与等离子体中的杂质密度有一定的关系,我们测量到等离子体辐射损失功率和辐射功率密度分布就可以得到离子体中有关杂质的信息。     

辐射量热计在HT-6BTokamak上的测量

一、引言 在现行的托卡马克实验中,辐射损失和中性粒子损失是高温等离子体能量损失的主要通道之一。为了更好地了解托卡马克等离子体中能量平衡、辐射损失以及这些损失随等离子体参数的变化;了解等离子体中杂质含量和杂质输运以及等离子体与器壁的相互作用,辐射能量损失的时间特性、空间分布的测量显得很有必要。为     

SWIP—RFP装置反场箍缩等离子体约束改善实验

在ＳＷＩＰ－ＲＦＰ装置上改善真空和预电离条件后，提高了等离子体温度，增加了等离子体的维持时间和反场箍缩磁场位形约束的维持时间，增长了等离子体的能量约束时间，从而表明了ＲＦＰ等离子体的能量约束和ＲＦＰ磁场位形的约束均得到了改善。     

托卡马克能量约束及自举电流效应的初步考虑

基于Lee等人的离子温度梯度模导致的反常热能输运系数,本文研究了辅助加热托卡马克等离子体的能量约束行为,并对自举电流的效应作了初步考虑。结果表明,计算得到的能量约束时间随等离子体电流I_p和托卡马克大半径R增大而增长,随注入功率P_t、环向场B_t以及等离子体小半径α的增大而缩短。这些结果与Kaye-Goldston的经验约束定标具有相同的趋势。自举电流的存在总是导致能量约束时间的增加,当自举电流与总电流的比值γ较小时,能量约束时间的增加率约为γ/2。此外,自举电流将造成锯齿反转半径的减小。     

FEB-E脱靶等离子体偏滤器的数值模拟

为了提高ＦＥＢ－Ｅ偏滤器的杂质控制和增加ＦＥＢ－Ｅ偏滤器处离子与中性气体的相互作用,用喷 气和杂质注入的方法设计了动态气全靶偏滤器。高约束Ｈ模拟态下的脱靶等离子体沿删削层（ＳＯＬ）磁力线有大的辐射功率份额（５０％￣８０％）和大的等离子体压力下降（９０％）。偏滤器上等离子体压降系数用ＳＯＬ的两点输运模型和辐射模型估算。结果显示,压降系数不仅与辐射功率份额有关,而且与ＳＯＬ驻点密度紧密相连。     

用光谱方法研究HL－1装置的不同约束模式

在Ｈ模式和高密度模式（ＨＤＭ）下，用光谱方法研究了ＨＬ－１等离子体的约束状况。实验表明，在这两种模式下粒子约束时间都有明显改善．     

HL-2A偏压偏滤器物理设计

根据已有的理论模型,推算出了HL-2A偏压偏滤器的理论电流为1．5kA、偏压电压为200V,并对HL-2A偏压偏滤器做出了初步设计。HL-2A装置采用偏压后,有可能降低L-H模转变阈功率,增加偏滤器等离子体密度、压强和滞留时间,改善约束,改善内外靶板功率沉积的非对称性,提高排灰效率及提高偏滤器性能。     

First evidence of the role of zonal flows for the L-H transition at marginal input power in the EAST tokamak

A quasiperiodic Er oscillation at a frequency of <4 kHz, much lower than the geodesic-acoustic-mode frequency, with a modulation in edge turbulence preceding and following the low-to-high (L-H) confinement mode transition, has been observed for the first time in the EAST tokamak, using two toroidally separated reciprocating probes. Just prior to the L-H transition, the Er oscillation often evolves into intermittent negative Er spikes. The low-frequency Er oscillation, as well as the Er spikes, is strongly correlated with the turbulence-driven Reynolds stress, thus providing first evidence of the role of the zonal flows in the L-H transition at marginal input power. These new findings not only shed light on the underlying physics mechanism for the L-H transition, but also have significant implications for ITER operations close to the L-H transition threshold power.     

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基于托卡马克实验的L-H模转换过程中等离子体的输运特征,建立了一种简化的非线性等离子体输运模型。通过数值求解输运方程,得到了等离子体稳态温度分布剖面,成功模拟了托卡马克边缘输运势垒(ETB)的形成以及高辅助加热功率下的内部输运势垒(ITB)现象,并对比了有无输运势垒两种情况下托卡马克的能量约束效率。     

Favourable scenarios established by SMBI for the realization of the ELMy H-mode at HL-2A

The ELMy H-mode plasmas realized with the supersonic molecular beam injection(SMBI) are studied in relation to the energy confinement and the heating power for the L–H transition(P_(L-H) ) in the HL-2A tokamak. A database is assembled for this study based on the ELMy H-mode discharges during the experimental campaigns in the period 2009–2013at the HL-2A tokamak. The statistical results show that the SMBI is favourable for reaching the H-mode by reducing the heating power at the L–H transition and for the H-mode performance by improving the energy confinement compared with the ordinary gas puffing(GP). The reduction of P_(L-H) is about 20% when the density is low, and the energy confinement enhancement factor of H_(H98y2)= τ_E/τ_(th,98y2) ≈ 1.5 is achieved with the SMBI. Note that in the database the density dependence of P_(L-H) is non-monotonic with the ˉne,min≈ 3×10~(19) m~(-3) at which the P_(L-H) is minimum. Most of P_(L-H) data are on the low density branch where the P_(L-H) increases with the decrease in density. The minimum of the P_(L-H) in HL-2A is comparable to the ITPA multi-machine threshold power scaling P_(thr■scal08). The physics behind the reduction of the P_(L-H) with the SMBI is also investigated in relation to the change of the density gradient at the plasma edge, the gas fuelling efficiency, and the recycling.     

Influence of peripheral radial electric field on L-H transition in T-10 tokamak

In this paper the peripheral plasma behaviour during and after L-H transition on the tokamak T-10 is considered. Abrupt changes of Scrape-Off Layer (SOL) plasma parameters (ion saturation current, floating potential, electron temperature) are observed in regimes with transition to the improved plasma confinement. Such changes begin (5–150) ms prior to the L-H transition. The time delay of a transition depends on auxiliary plasma heating powerP _aux and plasma currentI _p (at constant toroidal magnetic field inductionB _t). Presented at the Workshop on the Role of Electric Fields in Plasma Confinement and Exhaust, Budapest, 18–19 June, 2000. This work is supported by Ministry of Atomic Energy of Russia (contract 69F) and by Ministry of Science and Technology of Russia (Federal Program “Controlled Thermonuclear Fusion and Plasma Processes”).     

Mean and oscillating plasma flows and turbulence interactions across the L-H confinement transition

A complex interaction between turbulence driven E × B zonal flow oscillations, i.e., geodesic acoustic modes (GAMs), the turbulence, and mean equilibrium flows is observed during the low to high (L-H) plasma confinement mode transition in the ASDEX Upgrade tokamak. Below the L-H threshold at low densities a limit-cycle oscillation forms with competition between the turbulence level and the GAM flow shearing. At higher densities the cycle is diminished, while in the H mode the cycle duration becomes too short to sustain the GAM, which is replaced by large amplitude broadband flow perturbations. Initially GAM amplitude increases as the H-mode transition is approached, but is then suppressed in the H mode by enhanced mean flow shear.     

The Role of Radial Electric Fields in the Tokamaks TEXTOR-94, CASTOR, and T-10

Radial electric fields (E _r) and their role in the establishment of edge transport barriers and improved confinement have been studied in the tokamaks TEXTOR-94 and CASTOR, where E _r is externally applied to the plasma in a controlled way using a biased electrode, as well as in the tokamak T-10 where an edge transport barrier (H-mode) is obtained during electron-cyclotron resonance heating (ECRH) of the plasma.The physics of radial currents was studied and the radial conductivity in the edge of TEXTOR-94 (R = 1.75 m, a = 0.46 m) was found to be dominated by recycling (ion-neutral collisions) at the last closed flux surface (LCFS) and by parallel viscosity inside the LCFS. From a performance point of view (edge engineering), such electrode biasing was shown to induce a particle transport barrier, a reduction of particle transport, and a concomitant increase in energy confinement. An H-mode-like behaviour can be induced both with positive and negative electric fields. Positive as well as negative electric fields were shown to strongly affect the exhaust of hydrogen, helium, and impurities, not only in the H-mode-like regime.The impact of sheared radial electric fields on turbulent structures and flows at the plasma edge is investigated on the CASTOR tokamak (R = 0.4 m, a = 0.085 m). A non-intrusive biasing scheme that we call "separatrix biasing" is applied whereby the electrode is located in the scrape-off layer (SOL) with its tip just touching the LCFS. There is evidence of strongly sheared radial electric field and E×B flow, resulting in the formation of a transport barrier at the separatrix. Advanced probe diagnosis of the edge region has shown that the E×B shear rate that arises during separatrix biasing is larger than for standard edge plasma biasing. The plasma flows, especially the poloidal E×B drift velocity, are strongly modified in the sheared region, reaching Mach numbers as high as half the sound speed. The corresponding shear rates ( 5×10⁶ s^-1) derived from both the flow and electric field profiles are in excellent agreement and are at least an order of magnitude higher than the growth rate of unstable turbulent modes as estimated from fluctuation measurements.During ECRH in the tokamak T-10 (R = 1.5 m, a = 0.3 m), a regime of improved confinement is obtained with features resembling those in the H-mode in other tokamaks. Using a heavy ion beam probe, a narrow potential well is observed near the limiter together with the typical features of the L-H transition. The time evolution of the plasma profiles during L-H and H-L transitions is clearly correlated with that of the density profile and the formation of a transport barrier near the limiter. The edge electric field is initially positive after the onset of ECRH. It changes its sign during the L-H transition and grows till a steady condition is reached. Similar to the biasing experiments in TEXTOR-94 and CASTOR, the experimentally observed transport barrier is a barrier for particles.     

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ArⅡ(401.36 nm)和芯部的Ar¹⁵⁺离子谱线ArⅩⅥ(35.39 nm),并获得两者强度随时间的变化。其中,ArⅡ和ArⅩⅥ的电离能分别为27和918 eV,因此,ArⅡ和ArⅩⅥ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ArⅩⅥ辐射增长滞后于边界ArⅡ辐射的增长,并且在具有较高的低杂波加热功率的放电中...