等离子体电流

结果表明，计算得到的能量约束时间随等离子体电流Ip和托卡马克大半径R增大而增长，随注入功率Pt、环向场Bt以及等离子体小半径α的增大而缩短。

The results indicate that energy confinement time increases with plasma current and tokamak major radius , and decreases with heating power , toroidal field and minor radius .

自适应控制在HL-2A等离子体电流控制中的应用

Applications of an adaptive control in the HL-2A plasma current control system

在LHCD期间粒子约束明显改善，用LHCD实现了对MHD扰动的完全抑制，电流驱动效率随等离子体电流增大而增加。

During LHCD particle confinement was improved and the MHD disturbances were suppressed completely .

文中详细介绍了样条配置法的数学方法，并计算了m>1撕裂模稳定的等离子体电流剖面，拟合了HL-1托卡马克装置低q实验的电流剖面。

A stable current profile for m > 1 tearing modes is calculated . The current profile for the Low - q experiment in the HL-1 tokamak is tentatively reconstructed .

在ULQ放电时随着等离子体电流的上升，出现由于发电机效应（dynamo）所引起的环向磁通增长。

The increase of toroidal flux was generated by dynamo with plasma current rising during ULQ discharges .

本文介绍了模拟等离子体电流环电流在HL-1装置铜壳的1/4段上感应的涡流，在等离子体区产生的磁场大小、分布和时间特征的测量结果。

Using a plasma simulator , the magnitude , distribution and time behavior of the magnetic field generated by the eddy currents in a quarter segment of the HL-1 copper shell were measured .

文章分析了由等离子体电流和真空室感应电流在HT－7U装置环向场超导磁体中产生的涡流损耗。

The eddy current losses in the toroidal field superconducting magnet of the HT-7U tokamak , produced by plasma current and the eddy currents on the vacuum vessel , are analyzed .

采用3kwCO2激光器在不同激光焊接规范下，依据测量得到的等离子体电流计算得到了等效电源电压和等效内阻。

The plasma current in a 3 kW CO 2 laser welding beam was measured experimentally to calculate the equivalent power source voltage and source resistance for different laser welding parameters .

结果表明：Alfven波存在比较宽的激发区域，耦合强度随等离子体电流、纵向磁场的上升而增强。

The results show that there is a quite broad excitation region for shear Alfven waves , the wave energy coupling indicated by the antenna loadings increase as the plasma current and toroidal magnetic field increase .

在HT7超导托卡马克装置上利用低杂波电流驱动有效地控制了等离子体电流分布，并使等离子体约束性能改善。

The effectiveness of the plasma current profile control and confinement improvement with lower hybrid current drive ( LHCD ) in the HT-7 superconducting tokamak has been observed successfully .

测量结果表明，SWIP-RFP装置的等离子体电流一般大于60kA，在较好的放电条件下，等离子体电流可以驱动到100kA，等离子体电流最大值时刻的单匝线圈测量的环电压约为250V。

The experiments show that the plasma current is above 60 kA normally , with better discharge conditions , the plasma current can be driven to 100 kA . The one turn coil voltage is about 250 V with maximum plasma current during a discharge .

利用环向电场提升等离子体电流以改善约束状态

Improved confinement phase in ramping up plasma current by toroidal field

本文探索波驱动等离子体电流的一种新机制，称之为随机驱动效应。

A new mechanism of current driven by a wave is discussed .

激光焊接时等离子体电流的产生机制及其数学模型

Mechanism and Mathematical Model of the Laser-induced Plasma Current in Laser Welding

本文分析了高频电磁波驱动等离子体电流的效应，指出，波的电场力和洛仑兹力都对驱动电流有贡献；

The mechanism of rf-driven currents by high frequency electromagnetic waves is discussed .

无碰撞等离子体电流片中的低频波

Low-frequency waves in collisionless plasma current sheet

高频电磁波驱动等离子体电流

Currents driven by high frequency electromagnetic waves

随机驱动等离子体电流

Stochastic current driven by a wave

在初步的欧姆加热实验中已得到了等离子体电流为52kA的可重复放电。

Reproducible discharge with plasma current of 52 kA has been achieved in initial ohmic heating experiments .

给出了等离子体电流及其持续时间，以及与其相关因素的依赖关系。

Relationships between relevant factors and plasma current ( IP ) , plasma current duration ( rp ) are also given .

计算发现，增大等离子体电流或使电流分布趋于中心可以改善快离子的约束，提高加热效率。

Increasing plasma current or making the current distribution concentrate close to the center can improve the confinement of fast ions and raise heating efficiency .

该控制系统采用了微机和高精度的电子元器件，对等离子体电流的位移控制有了极大的改善，提高了装置放电的质量和效率。

By using the computer and the high accurate electronic component the great amelioration has been made on plasma displacement control , discharge quality and efficiency .

数值放电模拟还利用基本的位移控制和等离子体电流控制系统实现了从孔栏位形到下单零偏滤器位形的稳定演变。

This simulation achieves a stable configuration evolution from limiter to lower single-null divertor by using the vertical and horizontal displacement feedback and the current feedback .

研究了水分压强的某些特性及其同充氢气压、等离子体电流（电子温度）、电子密度的关系。

The variation of partial pressure of water vapour has been measured as a function of hydrogen filling pressure , plasma current , electron density , and temperature .

在反场箍缩条件下可允许用强等离子体电流充分加热等离子体到点火温度，而不需要辅助的中性束或射频加热系统。

The high plasma current allowed in a RFP is expected to be sufficient to heat the plasma to ignition without the need of auxiliary neutral-beam or radio-frequency heating .

在杂散场测量与软件补偿实验中，发现同心圆逆磁线圈感应的杂散信号主要来自垂直场、涡流电流、等离子体电流和纵场电流的变化。

In the experiments of measurement and software compensation of diamagnetism , it is found that stray fields mainly come from the vertical field , plasma current and eddy current .

这一变化解释了壁处理后稳态放电时，等离子体电流可以轻松放大且等离子体电流分布变宽的现象。

The results may help explain the previous experimental phenomena that the plasma current profile is broadened and the higher current can be obtained easily on the HT-7 tokamak experiment after wall conditionings .

HL2A装置反馈控制系统的主要任务是逐步实现对等离子体电流、位移、形状和密度的实时反馈控制，从而能够按照实验目的对托卡马克等离子体进行各种试验。

The feedback control system of HL-2A device is designed to control the current , displacement , configuration and density of plasma on real-time , so some plasma parameters can be achieved as expected .

与离子真空规预电离比较，等离子体电流建立得更快，幅值增大25%，维持时间增长30%；

By comparison with preionization by vacuum gauge , the plasma current build-up becomes fast in this case . The amplitude and duration of discharge current increase by 25 % and 30 % , respectively .

电感耦合RF放电等离子体的电流特性

The Characteristic of Current in an Inductive Coupled RF Plasma