HT—7超导托卡马克最新实验进展

HT－7超导托卡马克在过去的一年中取得较大进展：高参数放电时间长度接近4s,总加热功率超过1MW,在低杂波全波驱动、电流爬升、离子回旋共振加热、双波协同效应,射频壁处理,低环电压启动等方面都取得可喜的结果。     

Study of Density Behavior During LHCD and IBW Heating in the HT-7 Superconducting Tokamak

A new method using special shape parameters has been introduced to study density behavior with synergy of lower hybrid current drive (LHCD) and ion Bernstein wave (IBW) heating in the HT-7 superconducting tokamak. During the synergy of the LHCD and IBW heating an improved confinement plasma was achieved, and the electron density was increased and peaked.     

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采用1.5维的放电模拟程序TSC结合蒙特卡罗程序NUBEAM对使用中性束加热的EAST放电全过程进行数值模拟研究。分析了典型实验参数条件下的中性束的加热及电流驱动效果。讨论了不同背景等离子体密度对中性束加热及电流驱动效果的影响。模拟结果表明,中性束的注入使得背景等离子体温度有了较大幅度的提升,并能驱动出一定份额的非感应电流;适当降低背景等离子体密度有助于提高中性束的加热及电流驱动效率。     

Inductance of rf-wave-heated plasmas

The inductance of rf-wave-heated plasmas is derived. This inductance represents the inductance of fast electrons located in a plateau during their acceleration due to electric field or deceleration due to collisions and electric field. This inductance has been calculated for small electric fields from the two-dimensional Fokker-Planck equation as the flux crossing the surface of critical energy mv(2)(ph)/2 in the velocity space. The new expression may be important for radio-frequency current drive ramp-up, current drive efficiency, current profile control, and so on in tokamaks. This inductance may be incorporated into transport codes that study plasma heating by rf waves.     

Long-pulse improved central electron confinement in the TCV tokamak with electron cyclotron heating and current drive

Current profile tailoring by electron cyclotron heating (ECH) and current drive (ECCD) is used to improve central electron energy confinement in the TCV tokamak. Counter-ECCD on axis alone achieves this goal in a transient manner only. A stable scenario is obtained by a two-step sequence of off-axis ECH, which stabilizes magnetohydrodynamics modes, and on-axis counter-ECCD, which generates a flat or inverted current profile. This high-confinement regime, with central temperatures up to 9 keV (at a normalized beta(N) approximately 0.6), has been sustained for the entire duration of the heating pulse, or over 200 electron energy confinement times and 5 current redistribution times.     

一种适用于PWM驱动的滤波方法北大核心CSCD

脉冲宽度调制(pulse width modulation,PWM)驱动是现有伺服控制系统的关键构成,因此在直流电机前端对脉宽信号进行差模滤波与共模滤波尤为重要。以某光电惯性稳定平台WSA38M功放模块为标的搭建滤波电路,分析PWM驱动开关频率导致电机发热和产生电磁耦合干扰的原因,运用公式计算LC滤波电路的电气参数,并进行优化仿真。测试和电磁兼容实验结果表明:优化后的电路性能优良,尤其是在22 kHz~53 kHz频段对系统干扰较小,容易满足整体指标要求,为控制系统设计提供了可靠的依据。     

Improved lower hybrid current drive efficiency with IBW heating in the HT-7 tokamak

Lower hybrid current drive (LHCD) efficiency in the HT-7 tokamak is observed to increase about 30% with ion Bernstein wave (IBW) heating. The current drive efficiency as high as has been reached in HT-7 thanks to an LHCD/IBW synergy. The IBWs are significantly coupled to the fast electrons produced by the lower hybrid waves, thus results in higher fast electron photon temperature in the combined LHCD + IBW scenario. The interaction of LHCD + IBW improved current drive efficiency.     

Control of neoclassical tearing modes by sawtooth control

The onset of a neoclassical tearing mode (NTM) depends on the existence of a large enough seed island. It is shown in the Joint European Torus that NTMs can be readily destabilized by long-period sawteeth, such as obtained by sawtooth stabilization from ion-cyclotron heating or current drive. This has important implications for burning plasma scenarios, as alpha particles strongly stabilize the sawteeth. It is also shown that, by adding heating and current drive just outside the inversion radius, sawteeth are destabilized, resulting in shorter sawtooth periods and larger beta values being obtained without NTMs.     

Spatially resolved measurements of laser filamentation in long scale length underdense plasmas with and without beam smoothing

The onset of filamentation, following the interaction of a relatively long (τ(L)?1 ns) and intense (I(L)?5×10(14) W/cm(2)) laser pulse with a neopentane filled gas bag target, has been experimentally studied via the proton radiography technique, in conditions of direct relevance to the indirect drive inertial confinement fusion scheme. The density gradients associated with filamentation onset have been spatially resolved yielding direct and unambiguous evidence of filament formation and quantitative information about the filamentation mechanism in agreement with previous theoretical modelings. Experimental data confirm that, once spatially smoothed laser beams are used, filamentation is not a relevant phenomenon during the heating laser beams propagation through typical hohlraum gas fills.     

The Design of the Microwave Exciter for Klystron

To carry out lower hybrid wave heating and current drive plasma experiment on tokamak, we need mega-watt order of microwave power generated by the parallel-running klystrons. Those klystrons must be driven by the microwave exciter. Now our microwave exciter is used for many years and its performance is decreased very much. It can not satisfy any more the hybrid wave heating and current drive plasma experiment. So we set out to design a new microwave exciter that is consist of the microwave solid components, amplitudestabilization control, modularization design with multitude-outputs, microwave phase control in order to satisfy the demand of the different work in the hybrid wave heating and current drive plasma experiment.     

Neoclassical tearing mode stabilization by electron cyclotron current drive for HL-2M tokamak

Investigation of neoclassical tearing mode and its suppression by electron cyclotron current drive(ECCD) has been carried out in HL-2 M tokamak. The current driving capability of the electron cyclotron wave is evaluated. It is found that the deposition location can be effectively controlled by changing the poloidal angle. The validation of electron cyclotron wave heating and current driving has been demonstrated for the upper launcher port. We show that 3.0 MW and2.5 MW modulated ECCD can completely stabilize(2,1) and(3,2) NTMs, respectively. The non-modulated ECCD, radial misalignment as well as current profile broadening have deleterious effect on the NTM stabilization. The time required for suppression of(3,2) mode is shorter than that required for the suppression of(2,1) mode. Moreover, the time needed for complete stabilization at different initial island width has been quantitatively presented and analyzed.     

HL-2M装置低混杂波电流驱动系统高精度数字温度测量仪的研制

为HL-2M低混杂波电流驱动系统研制了16路J型数字校准热电偶测温仪,可实现16通道温度测量,测温范围为0~250°C,测量范围内误差绝对值小于1°C,具有本地高清液晶显示温度值和电脑远程温度采集功能。该测温仪已成功用于HL-2M低混杂波加热系统的调试实验,对不同输出功率条件下高功率速调管输出腔温度进行了测量,保证了速调管运行的安全性。     

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A 16-channel J-type thermocouple instrument with digital calibration for the lower hybrid current drive (LHCD) system on HL-2M tokamak was developed to achieve 16 channel temperature measurements. The temperature measurement range is 0~250°C with the absolute error value less than 1°C. The temperature can be displayed on the liquid crystal display (LCD) and read on the computer remotely. The J-type thermocouple instrument has been successfully used in the debugging experiment of the LHCD heating system of HL-2M tokamak. The temperature of output cavity of the high power klystron has been measured under different output power conditions to ensure the safety of the klystron in operation.     

LOW POWER MEASUREMENTS ON THE NEW RF OUTPUT SYSTEM OF A 170 GHZ, 2 MW COAXIAL CAVITY GYROTRON

The design of the quasi optical (q. o.) RF output system for the first industrial prototype of the European 170 GHz, 2 MW, CW coaxial cavity gyrotron for electron cyclotron heating and current drive in ITER has been verified at a low power level. Results of measurements with a high quality TE_34,19-mode generator are in good agreement with the design calculations. This strengthens the confidence both to the employed design codes and to the manufacturing quality of the launcher and mirrors.     

Controlled optimization of mode conversion from electron Bernstein waves to extraordinary mode in magnetized plasma

In the CDX-U spherical torus, agreement between radiation temperature and Thomson scattering electron temperature profiles indicates approximately 100% conversion of thermally emitted electron Bernstein waves to the X mode. This has been achieved by controlling the electron density scale length (L(n)) in the conversion region with a local limiter outside the last closed flux surface, shortening L(n) to the theoretically required value for optimal conversion. From symmetry of the conversion process, prospects for efficient coupling in heating and current drive scenarios are strongly supported.     

EAST中性束注入角度的NUBEAM模拟研究

采用蒙特卡罗程序NUBEAM对EAST NBI上的中性束注入角度(中性束系统中心线与注入窗口轴线的夹角)进行了分析。讨论了中性束注入角度对电流驱动效率、加热效率和束的穿透功率的影响,对EAST NBI系统选取了一个最优的注入角度。模拟结果表明：对EAST NBI系统,在典型的EAST实验参数和实际工程允许的范围内,19.5°是最优的注入角度。在此注入角度下,可以通过增大等离子体密度的方法来进一步提高加热效率和电流驱动效率,并减少束的穿透功率。     

Toroidal Effect on Lower Hybrid Current Drive in Tokamak

In the review paper of N. J. Fish, the topics concerning the basic theory of lower hybrid wave heating and current drive are presented. In the consideration of radio-frequency heating and current drive of tokamak plasma near the lower hybrid frequency, the parallel wave length is imposed by the coupling device parallel to the magnetic field and is modified by gradients along the field. The important effects are found on wave penetration and damping when the toroidal aspect ratio is low. It may be possible to change the plasma current via electron Landau damping with a coupler rf power spectrum.     

Novel Applications of Millimeter and Submillimeter Wave Gyro-Devices

The possible applications of high-power millimeter (mm) and submillimeter waves from gyro-devices span a wide range of technologies. The plasma physics community has already taken advantage of recent advances in applying high-power micro- and mm-waves generated by gyrotron oscillators in the areas of RF-plasma production, heating, noninductive current drive, plasma stabilization and active plasma diagnostics for magnetic confinement thermonuclear fusion research, such as lower hybrid current drive (8 GHz), electron cyclotron resonance heating (ECRH) (28–170 GHz), electron cyclotron current drive (ECCD), collective Thomson scattering and heat-wave propagation experiments. Other important applications of gyrotrons are electron cyclotron resonance (ECR) discharges for generation of multi-charged ions and soft X-rays, as well as industrial materials processing and plasma chemistry. Submillimeter wave gyrotrons are employed in high-frequency broadband electron paramagnetic resonance (EPR) spectroscopy. Future applications which await the development of novel high-power gyro-amplifiers include high resolution radar ranging and imaging in atmospheric and planetary science as well as deep-space and specialized satellite communications and RF drivers for next-generation high-gradient linear accelerators (supercolliders). The present paper reviews the state-of-the-art and future prospects of these recent applications of gyro-devices.     

Effects of trapped electrons on off-axis lower hybrid current drive in tokamaks

The effects of trapped electrons on off-axis lower hybrid current drive （LHCD） in tokamaks are studied, A computer code for solving the Fokker-Planck equation in a toroidal geometry is developed and employed. The code is suitable for various auxiliary heating and current drive schemes in tokamak plasmas. The influence of the resonance regime on the current drive efficiency as well as the influence of trapped particle fraction on the current drive efficiency are emphasized. It is shown that, as an electrostatic force, the lower hybrid wave causes some of the trapped electrons to be untrapped and lose their energy, which can cut the LHCD efficiency by about 30%. The ITER scaling law is also used to estimate the trapped electron effects.[第一段]     

On the Choice of Electron Cyclotron Heating Frequency for T-15MD Tokamak

Physics of Atomic Nuclei - Electron cyclotron heating is one of the methods of additional plasma heating and noninductive current drive in the T-15MD tokamak. One to eight gyrotrons with a total...