HT-7 Tokamak离子回旋波和低杂波等离子体逃逸电子行为研究

HT-7 Tokamak拥有离子回旋波(ICRF)和低杂波(LHW)两套加热系统.ICRF主要对加热离子有比较好的加热效果,LHW则主要是通过电子Landau阻尼加热电子.除此之外,在ICRF和LHW协同加热的条件下,可以对等离子体产生更有效的加热效果,增加等离子体的聚变反应截面,增加聚变中子产额.本文报道了LHW对改善ICRF和等离子体耦合的重要作用,ICRF和LHW加热等离子体中电子温度随时间的演化过程,计算了放电过程中电子逃逸的阈值能量,分析了逃逸电子的产生过程,以及放电过程中的中子产额.研究结果发     

ICRF快波模转换及快波传播

本文通过分析离子回旋频段(ICRF)快波在模转换区传播的物理过程,导出了一个新的快波近似——完全快波近似二阶波方程。数值计算表明,它能给出与求解高阶方程非常一致的结果,尤其是在弱回旋阻尼(k_1较小)情况下,完全快波近似比快波近似有更满意的结果。最后讨论了二次谐波加热和少数成份离子加热的实例。     

托卡马克等离子体的快波模转换和吸收

本文对托卡马克位形,用动力理论研究了非均匀热等离子体的ICRF快波模转换及有关的阻尼机制。结果表明,对于多种离子成分的等离子体,在离子-离子混杂共振层和二次谐波回旋共振层附近,存在快波和离子伯恩斯坦波(IBW)之间的模转换;模转换层附近的色散关系与k_(?),离子种类浓度以及等离子体密度有明显的相关性。适当选择这些参数可大大改善快波能量的吸收和吸收的局域性。而在一种离子成分的等离子体中、无模转换过程发生。     

快波模式转换电子加热

利用全波方法对环形轴对称托卡马克等离子体中快波模式转换电子加热的机理进行了讨论,并针对EAST超导托卡马克上未来ICRF实验中可能的快波模式转换电子加热方案进行了模拟计算,为进一步ICRF实验方案设计优化提供了理论依据。     

HT-7上射频波加热时中子辐射行为的研究

HT-7超导托卡马克进行DD等离子体放电时,中子的辐射与辅助加热射频波的类型(LHW加热、ICRF加热)及功率密切相关.利用BF₃与³He正比计数管组成的快速时间分辨中子注量监测系统,研究了不同类型的射频加热对于中子产生机理及高能离子形成的影响.LHW加热功率较低时,易形成逃逸,产生大量的光中子.特定频率的ICRF(27 MHz,24 MHz)加热时,聚变中子所占份额以及总的中子产额均随波功率的增大而显著增涨. 关键词： 射频加热 中子 托卡马克     

离子回旋共振加热的电子加热

理论分析和实验结果都证明在离子回旋共振加热情况下,电子能直接从波吸收能量,其能量吸收机制是郎道阻尼和飞行时间磁泵阻尼。本文从线性化波的一般理论,导出了电子吸收功率和吸收特征长度的解析表示式,与其他结果进行了比较并做了简短的讨论。     

离子回旋共振加热的离子加热

本文在直住几何位形下用线性化动力论得到了离子能量吸收及吸收特征长度的解析表示式，离子能量吸收的主要物理机制是回旋阻尼，波与离子的共振吸收条件是ω－ｌωｃｉ＝ｋⅡνⅡ，其中ω和ωｃｉ分别是波的频率和离子回旋频率，ｋⅡ和ｖⅡ是平行于主磁场方向的波矢和离子速度的分量，ｌ为整数。在等离子体参量慢变化的假定下，也得到了能量吸收半宽度的表示式。结合托卡马克的各种具体情况分别讨论了各种离子回旋共振加热模式的...     

MM—2U磁镜上ICRF系统中的天线参数测量及系统匹配

一、引言 目前用射频波对等离子体进行加热和稳定是受控核聚变研究中的重要课题之一。ICRF系统中的射频源技术已经比较成熟,现正向更大功率的方向发展。但是,用于等离子体实验研究的ICRF系统还有不少特殊问题需要解决。ICRF系统中传输、匹配、耦合所涉及到的物理和工程问题是相当复杂的,特别是作为ICRF系统负载的等离子体具有变参数,低阻抗的特性,这就更增加了工程设计和调试的难度,有许多问题有待于进一步深入研究解决。本文将从工程角度上,叙述ICRF系统中的设计和调试问题。     

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采用等离子体分层模型,利用WKB近似研究了离子回旋共振加热(ICRH)天线发射谱n||对离子回旋波在托卡马克等离子体的表面功率反射系数、吸收衰减的影响,数值模拟了不同天线发射谱n||条件下快波少数离子加热的效果.模拟结果表明,当其它实验参数一定时,ICRH天线发射合适的n||能提高天线与等离子体的耦合效率,增强少数离子加热的效果.     

用快波加热燃烧等离子体

在把离子伯恩斯坦波处理成对快阿尔芬波的响应下，导出了点火托卡马克等离子体的离子回旋共振加热的二阶模转换方程。这个二阶方程的数值积分表明，结果与由高阶方程的计算很好地一致。只有在弱阻尼的情况下，α粒子吸收的功率才是重要的。     

Destabilization of TAE modes by particle anisotropy

Plasmas heated by ICRF produce energetic particle distribution functions which are sharply peaked in pitch-angle. At moderate toroidal mode numbers, this anisotropy is the dominant instability drive when compared with the universal instability drive due to the spatial gradient. The universal drive, acting alone, destabilizes only co-propagating waves (i.e., waves propagating in the same toroidal direction as the diamagnetic flow of the energetic particles), but stabilizes counter-propagating waves (i.e., waves propagating in the toroidal direction opposite to that of the diamagnetic flow of the energetic particles). Nonetheless, in a tokamak, it is possible that particle anisotropy can produce a larger linear growth rate for counter-propagating waves, and provide a mechanism for preferred destabilization of the counter-propagating TAE modes that are sometimes experimentally observed.     

Review of ICRF Experiments

The current status of ICRF experiments is reviewed with emphasis on high-power heating results in tokamaks. The rationale for the use of the fast magnetosonic wave is described along with simplified models for the wave coupling and power absorption. Experimental results are presented which confirm the essential features of the theoretical model and suggest a highly favorable prognosis for scaling the heating process to a reactor.     

HL-2A装置的LHCD运行区域与驱动电流分布控制

讨论了低杂波电流驱动（LHCD）实验中电流驱动效率、电流分布控制与等离子体参数和入射波谱的关系,以及波的可近性对确定功率沉积分布的作用。讨论了控制电流密度分布的方法及在HL－2A装置上实现中心负剪切位形的可能性。     

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.     

On the Nonlinear Processes During Generation of Current Drive

The manifestations of the induced scattering effects in the generation process of current driven by lower-hybrid (LH) waves are studied taking into account the radiative-resonant interactions. The influence extent of the LH wave modulational instability on current drive is estimated. It is shown that the induced scattering of LH waves on plasma particles leads to a change of the LH waves spectrum and through this leads to an essential influence on fast electrons generation rate and the steady-state current drive. The modulational instability of LH waves can provide a “spectral gap” filling in the case of sufficiently strong LH wave pumping.     

Optimized calculation of the synergy conditions between electron cyclotron current drive and lower hybrid current drive on EAST

The optimized synergy conditions between electron cyclotron current drive(ECCD) and lower hybrid current drive(LHCD) with normal parameters of the EAST tokamak are studied by using the C3PO/LUKE code based on the understanding of the synergy mechanisms so as to obtain a higher synergistic current and provide theoretical reference for the synergistic effect in the EAST experiment. The dependences of the synergistic effect on the parameters of two waves(lower hybrid wave(LHW) and electron cyclotron wave(ECW)), including the radial position of the power deposition, the power value of the LH and EC waves, and the parallel refractive indices of the LHW(N) are presented and discussed.     

HT－6M装置上离子回旋波的传播和吸收

本文从波与粒子相互作用的线性理论出发，结合ＨＴ－６Ｍ托卡马克少数离子为氢，基本离子为氘［Ｈ（Ｄ）］的等离子体离子回旋共振加热（ＩＣＲＨ）为例，讨论了离子回旋波在这特定的等离子体中传播、吸收与少数离子氢的浓度ＲＨ（定义为ｎＨ／ｎｅ，ｎＨ为氢离子密度，ｎｅ是等离子体总密度）和平行波数ｋ‖的关系。文中最后还给出了ＨＴ－６Ｍ托卡马克离子回旋共振加热的优化实验方案。     

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.