HT-7托卡马克等离子体逃逸电子螺旋角散射研究

在托卡马克等离子体中,相同的等离子体电流条件下,若在较低的等离子体密度条件下发生反常多普勒共振,将会导致逃逸电子快螺旋角散射（FPAS）的发生;若在较高的等离子体密度条件下发生反常多普勒共振,则会导致逃逸电子正常螺旋角散射（NPAS）的发生。通过研究FPAS和NPAS条件下的逃逸电子行为,发现FPAS和NPAS均可一定程度增加逃逸电子的螺旋角,增加逃逸电子的同步辐射损失,减小逃逸电子的能量;且NPAS和FPAS对逃逸电子的影响主要集中在高能部分,对低能逃逸电子的影响较小。     

HT-7托卡马克中逃逸电子和磁场波纹的共振作用

为抑制托卡马克等离子体中逃逸电子的能量,在2009年秋HT-7托卡马克物理实验中,分析了逃逸电子在不同放电条件下的能量演化信息,发现逃逸电子和磁场波纹的共振现象.尽管在等离子体的芯部,逃逸电子的能量可高达数十MeV,但在逃逸电子输运到边界的过程中,通过和磁场波纹不同阶的谐波共振,逃逸电子的能量被限制在一个范围内,而不会...     

全超导托卡马克装置欧姆放电逃逸电子行为研究

电子发生逃逸在托卡马克等离子体中是较常见的现象,特别是在等离子体破裂阶段,会产生大量的逃逸电子。本工作利用硬X射线监测系统,并结合其它相关诊断系统研究世界上第1个运行的全超导托卡马克（EAST）装置在欧姆放电的不同阶段逃逸电子的行为。研究结果表明：在欧姆放电起始阶段,逃逸电子的初级产生过程占主导地位。随着放电的进行,逃逸电子的次级雪崩过程逐渐增长,在放电后期一直到等离子体破裂阶段,雪崩过程将占据主导地位。等离子体破裂后,因存在较高的环电压而产生了高能逃逸电子拖尾。     

托卡马克逃逸电子输运系数的研究

1 对托卡马克逃逸电子的一般介绍 近期,人们对托卡马克中逃逸电子输运的研究十分重视与活跃。从欧姆加热与辅助加热的等离子体中,逃逸约束时间具有反常行为,这与内部的磁场涨落相关;我们利用逃逸电子作为一种试验粒子来诊断托卡马克内部的磁涨落。从约束的环向等离子体中观察到粒子与能量的损失率远比由新纪典输运理论所预言的要大得多,此状态取决于平均等离子体参数与库仑碰撞。若干类型的等离子体湍流提供了附加的等离子体输运。等离子体参数的涨落将通过静电涨落或磁涨落引起输运。该涨落所驱动的径向粒子通量为(1)其中,是扰动角向电场,是扰动电子密度。是     

HT-7托卡马克上电子回旋辐射计及前端研究

介绍了安装在HT-7托卡马克装置上的电子回旋辐射外差诊断系统的原理,设计了-套测量系统,测量了石英玻璃和TPX材料在微波波段的插人损耗,为系统设计提供了必要的数据;研究了等离子体物理实验过程中在石英玻璃上沉积的膜的徼波传输特性;测量了诊断系统的天线方向角,并分析了天线方向角给电子温度测量带来的影响.     

HT-7超导托卡马克装置上中子通量分布的实验研究

本文介绍了HT-7超导托卡马克装置上中子通量分布的测量实验.在实验中,使用了两种有较强抗伽马能力的中子探测系统:BF3和3He正比计数管及其相应的电子学与数据采集.在2005年春季实验中,在相同实验条件下,细致测量并比较研究了真空室外不同水平位置、垂直位置的中子通量.实验研究了真空室窗口和变压器铁芯的存在对测量结果的影响,验证了测量结果与三维数值计算的一致性.本项工作为更深入的物理研究奠定了基础.     

JT—60U上用LHRF系统进行电子回旋共振放电清洗

本文研究了在第一壁完全被石墨瓦覆盖的JT-60U上电子回旋共振放电清洗（ECR-DC）。由低混杂频率范围（LHRF）系统产生的2GHz带射频（RF）波被用于约0.06T的环向磁场中的ECR-DC。经LH电流驱动发射器已重复注入了高达～125kW脉宽～60s的RF功率。ECR-DC增大了石墨第一壁上的粒子再循环率,并在氘气中进行ECR,观察到了明显的水蒸气解吸（质量数m/e=20）。而且,还发现在D2中进行ECR有效地解吸了氘放电的高功率加热期间注入到石墨第一壁上的氘。这表明ECR-DC是降低未来托卡马克聚变堆中氚投料量的有效工具之一。     

用电子回旋加热和电流驱动长脉冲改善TCV托卡马克的中心电子约束

通过用电子回旋加热（ECH）和电流驱动（ECCD）调整电流分布来改善TCV托卡马克的中心电子能量约束。单靠轴上反向ECCD仅以瞬变方式可实现上述目标。用致稳磁流体动力学模的离轴ECH两步步骤和产生平的或反转的电流分布的轴上反向ECCD来获得稳定工况。这种中心温度高达9keV(归一化βN-0.6时）的高约束状态已持续了整个加热脉冲持续时间，或200倍于电子能量约束时间和5倍于电流再分布时间。     

HT-6M托卡马克上的超低密度实验

通过一些特殊方法,HT-6M托卡马克可以稳定运行在只带少量过热电子的超低密度(SLD)区域。其主要参数为:N_e=(0.2～0.6)×10~(13)cm~(-3);I_p=60～80kA;V_o=0.7～2.0V;B_t=0.7～1.0T;a=18cm;R=63cm。在这类放电中,等离子体的密度由限制器和壁的出气量决定,而和初始充的氢气压强完全无关。等离子体是安静的,几乎没有“锯齿振荡”。m=2,3的磁流体力学(MHD)不稳定性只出现在电流下降段。径向温度分布T_o(r)峰化,而密度分布N_e(r)是平坦的。能量约束时间τ_e为1～2ms,大约是Alcator定标律的2～4倍。     

Novillo托卡马克辉光放电等离子体化学中的电子能量研究

本文给出了Novillo托卡马克辉光清洗放电氢等离子体中电子湿度，密度及等离子体电位的评估，目的是研究能从真空容器除去杂质，且避免仍能附着于其内壁上的其它化学化合物形成的等离子体条件。放电是在功能密度在100－900W.m^-2范围内，压强在0．07－0．2mbar范围内的情况下通过2个阳极和1个阴极完成的，等离子体参数是用朗缪尔探针得到的，结果表明：电子温度处于3－10eV范围内，电子密度约为10^8-10^9cm^-3和等离子体电位在10－18V范围内，对于在Novillo托卡马克中发现的大多数杂质，电子能量在离解能量范围内。     

Simulation of runaway electron generation and diffusion during major disruptions in the HL-2A tokamak

The generation and diffusion of runaway electrons (REs) during major disruptions in the HL-2A tokamak has been studied numerically. The diffusion caused by the magnetic perturbation is especially addressed. The simulation results show that the strong magnetic perturbation (δB/B ∼ 1.0 × 10⁻³) can cause a significant loss of REs due to the radial diffusion and restrain the RE avalanche effectively. The results also indicate that the REs are generated initially in the plasma core during disruptions, and that the toroidal electric field does not exhibit a centrally hollow phenomenon. In addition, it is found that the toroidal effects have little impact on the generation of RE and the evolution of toroidal electric field.     

Diamagnetic measurement on HT-7 superconducting tokamak

Diamagnetic measurement is a basic diagnostics on tokamak. Some important plasma parameters such as plasma energy and betap β_p can be obtained from this measurement. For most case, diamagnetic flux ΔΦ is extremely smaller than toroidal flux Φ (ΔΦ/Φ − 10⁻⁴). Therefore we have to use techniques that allow measurement to better than 1 part in 104 to get 10% accuracy in value of β_p. Using a compensation coil is a typical technique to improve the signal to noise ratio. In this paper the design of diamagnetic diagnostics system for HT-7 superconducting tokamak device is introduced and some experimental results of plasma energy and β_p are given in different plasma discharges.     

Soft landing of runaway currents by ohmic field in J-TEXT tokamak

Recently, experimental studies on the soft landing of RE current by ohmic (OH) field have been performed in J-TEXT tokamak, as a possible auxiliary method to dissipate the RE current. With optimized horizontal displacement control of the RE beam, the toroidal electric field has been scanned from 1.6 to - 0.3 V m ^-1 during the RE plateau phase. The growth rate of RE currents and the evolution of hard x-ray (HXR) emissions have been studied. It is found that when the toroidal electric field is less than 7–12 times the theoretical critical electric field, the decay of REs could be achieved. The dissipation rate by the ohmic field can reach a maximum value of 3 MA s^-1.Furthermore, the results of HXR spectra analysis indicate the different behaviors of HXR emissions under the condition of different toroidal electric fields. The analysis of the ionized argon emissions and magnetic fluctuations shows that under the condition of different toroidal electric fields, the physical process of RE generation may be different.     

The Study of Heat Pulse Propagation on HT—7 Tokamak

The propagation of heat pulses originating from sawtooth activity has been studied on the HT-7 tokamak.Two theoretical models are used for determining electron heat diffusivity from the experimental data measured by a diagnostic system of soft x-ray diode-array.The results show that one model caaled dipole model is more suitable for HT-7 tokamak.In order to improve the signal-to-noise(S/N) ratio of the original signals,over a few tens of sawteeth are averaged to generatc nicc wavcforms.The apace-time evolution is found to be diffusive in character,which is consistent with the theoretical model.The electron heat diffusivity determined from heat pulse propagation is larger than determined from background plasma power balance.The variation of Xe in different discharge phases has been also discussed.     

CO2 laser collective Thomson scattering diagnostics on the HT-7 tokamak

A CW CO2 laser collective Thomson scattering diagnostics was developed to measure plasma density fluctuations on the HT-7 tokamak. The design and construction of CO2 laser scattering apparatus is described. The laser source is a continuous-wave CO2 laser with a cavity length of 1.9 m and a power output of about 10 W at 10.6 μm. The k-resolution of the system is △k ≈ 3.2 cm^-1. The preliminary data from the diagnostic is presented.     

Upgrade of plasma density feedback control systemin HT-7 tokamak

The HT-7 is a superconducting tokamak in China used to make researches on the controlled nuclear fusion as a national project for the fusion research. The plasma density feedback control subsystem is the one of the subsystems of the distributed control system in HT-7 tokamak (HT7DCS). The main function of the subsystem is to control the plasma density on real-time. For this reason, the real-time capability and good stability are the most significant factors, which will influence the control results. Since the former plasma density feedback control system (FPDFCS) based on Windows operation system could not fulfill such requirements well, a new subsystem has to be developed. The paper describes the upgrade of the plasma density feedback control system (UPDFCS), based on the dual operation system (Windows and Linux), in detail.     

Design of flowing liquid lithium device for HT-7 tokamak

Lithium is a very attractive element due to its very low radiation power, strong H retention as well as strong O getter activity. Flowing liquid lithium (FLiLi) device, to be used as a plasma-facing limiters, has been designed and will be tested in HT-7 tokamak. It is mainly composed of distributor, guide plate, collector, and heater as well as cooling loop. The heater uses heater strip and cooling loop design, to control the temperature of lithium on the guide plate ranging from 200 °C to 400 °C. The distributor attached to feeding pipe, distributes liquid lithium (LiLi) flowing on the guide plate. The collector was designed to reclaim the superfluous LiLi and transport it out of device.The paper focuses on the design of flowing liquid lithium device. In addition to the process of design, thermal analysis has been carried out using finite element method (FEM) for optimizing the structure of heater and cooling loop and results of analysis are presented.