是带4个内导体坏的托卡马克装置。
本文介绍了KT—5托卡马克装置质谱测量的初步结果。
A primary measurement of mass spectrum on Tokamak KT-5 is presented.
本文概述了托卡马克聚变堆堆芯参数计算的一种基本模型。
This article Outlines a model for calculating the parameters oi a tokamak fusion reactor core.
球形托卡马克为聚变能的商业应用提供了一条可能的途径。
Spherical Tokamak is showing an attractive promising route for commercial application of fusion energy.
软x射线诊断是研究托卡马克等离子体不稳定性的重要手段。
Soft X-ray diagnosis is a important method in the research of tokamak plasma instability.
模拟计算的结果对托卡马克偏滤器和第一壁的设计有重要意义。
The simulation results play an important role in the design of divertor and first wall of Tokamak.
等离子体破裂是托卡马克运行中几乎不可避免的极快失控事件。
Plasma disruption, which seems to be unavoidable in Tokamak operation, occurs very fast and uncontrolled.
冷屏是EAST超导托卡马克核聚变实验装置的重要部件之一。
The thermal shield (TS) is a main part of EAST superconducting Tokamak.
抽气偏滤器初步实现了托卡马克放电过程中边缘粒子的抽运与控制；
The pumping divertor initially realizes the pumping and control of edge particles in tokamak discharge.
托卡马克等离子体控制系统中包括了对不同控制对象的PID控制。
The plasma control system of Tokamak consists of PID control for different objects.
介绍用于HL-2A托卡马克装置先进的加料系统研制的立项依据。
The basis in the development of an Advanced Refueling System (ARS) for HL-2A tokamak has been presented.
本文叙述了HT - 6a托卡马克平衡系统及第一期平衡实验结果。
The equilibrium system of HT-6A as well as the experiments on this tokamak are described.
本文应用能量原理研究成形线圈系统托卡马克平衡的轴对称不稳定性。
The axisymmetric instability of tokamak equilibria with a shaping coil system is studied using the energy principle.
在托卡马克等离子体中，高能粒子可以激发一种称为鱼骨模的内扭曲模。
A special kind of internal kink mode, the fishbone, can be excited by the energetic particles in tokamak plasmas.
采用条件平均技术对CT-6B托卡马克等离子体湍流信号进行了分析。
The fluctuation data coming from the CT-6B Tokamark plasma turbulence is analyzed by conditional averaging technique .
本文描述了HL - 1托卡马克中，各放电阶段的电子回旋辐射谱的特点。
This paper describes in detail the features of electron cyclotron emission in different phases of the HL-1 tokamak discharge.
低环径比托卡马克装置的实验和理论结果已证实它有利于改善MHD稳定性。
The results of the experiment and theory from low-aspect ratio tokamak devices have proved that the MHD stability will be improved.
EAST托卡马克核聚变实验装置是世界上从事核聚变研究的先进科学设备。
EAST is an advanced device for the study of nuclear fusion around the world.
本文介绍了基于EAST超导托卡马克装置真空系统杂质控制系统的改进工作。
This article introduces some improving work on impurities control of vacuum system in EAST TOKAMAK device.
文中叙述了HL - 1m托卡马克硼化真空紫外光谱区杂质辐射的观测结果。
This paper, results of VUV impurity radiation measured in the boronization experiment on the HL-1M Tokamak are given.
结果表明，雷诺胁强的径向变化可以自发产生托卡马克等离子体的剪切极向流。
The results indicate that the sheared poloidal flow can be generated in tokamak plasma due to the radially varying Reynolds stress.
结果表明，由于雷诺胁强的径向变化，托卡马克等离子体可以自发地产生剪切极向流。
The results indicate that the sheared poloidal flow can be generated in the plasmas due to radial variations in Reynolds stress.
本文总结了6D超导托卡马克环形磁体系统的D_3超导磁体的设计，研制与试验工作。
The present paper summarizes the design, development and test of the D3 superconducting magnet of the toroidal magnet system of the 6D superconducting tokamak.
大、中型托卡马克在D - D和D - T运行条件下聚变中子能谱测量具有重要意义。
It is very important that spectrum measurement of D-D and D-T fusion neutron in large scale Tokamak.
用蒙特卡罗方法研究了脉冲充气时气体分子在托卡马克装置的环形真空室内的瞬态空间过程。
The transient space process of molecular in a toroidal vacuum chamber of tokamak device during pulse puffing gas has been simulated by Monte-Carlo method.
介绍了振动时效技术在HT-7U超导托卡马克核聚变大底板、真空装置等能源工程中的应用。
The technology of vibratory stress relief(VSR) used in energy engineering, such as HT-7U nuclear fusion superconducting Tokamak massive base plate and vacuum vessel was introduced.
实验中将纯钨样品放入HT - 7托卡马克的刮削层中，以研究等离子体与纯钨表面的作用。
In the experiment, samples of pure tungsten were placed in the scrape-off layer of HT-7 tokamak to study the interaction between plasma and the surface of samples.
介绍了SUNIST低环径比托卡马克的纵向场线圈、欧姆加热场线圈和平衡场线圈的电学参数。
The electric parameters of toroidal magnetic field coils, ohmic heating systems and vertical balance magnetic field coils of SUNIST low aseptic ratio tokamak were introduced.
对原有的托卡马克平衡编码SWEQU进行了改进，使之适用于小环径比球形环装置的磁流体研究。
Tokamak equilibrium code SWEQU has been modified so that it can be used for the MHD equilibrium study of low aspect ratio device.
比较结果表明，用空间傅里叶分析法识别托卡马克中的MHD扰动模式是一种可以行之有效的方法。
The simulation results indicate that the spatial Fourier analysis is a better method to determine the MHD perturbation mode in tokamak.
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