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.
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.
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.
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.
介绍了集散控制系统在世界第四大超导托卡马克装置极向场控制系统中的应用。
The application of distribute control system (DCS) in poloidal field power supply of HT-7 superconducting tokamak device is described.
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.
介绍了将应用于EAST超导托卡马克装置的极向场电源失超保护控制系统的设计方案和技术要求。
This paper introduces the design scheme and technical requirement of quench protection control system for the poloidal power supply, which will be used in the EAST Tokamak.
EAST极向场电源是国家“九五”大科学工程EAST非圆截面大型超导托卡马克装置的子系统。
The power-supply control system of poloidal field system is a sub-system in EAST (Experimental Advanced Superconducting Tokamak), which is a National Mage-project of Science Research of China.
托卡马克装置产生等离子体击穿的条件是在真空室区域中达到足够大的环电压以及尽可能大的零场区。
The condition that plasma breakdown on Tokmak is get enough high loop voltage and large null field region in the vacuum vessel area.
本文叙述了在HT - 6b托卡马克装置上，采用脉冲放电清洗去除真空室壁表面杂质的初步实验结果。
This paper describes the experiment results on removing impurities from vacuum wall by means of pulse discharge cleaning in the HT-6B Tokamak device.
对于聚变托卡马克装置来说，第一壁材料抗等离子体辐照的性能非常重要，国际上也对此进行了广泛的研究。
For the fusion tokamak, the abilities of first wall material to resist fusion plasma irradiation are very important, this subject have been studied for many years in the world.
超导托卡马克装置EAST长稳态运行的方式需要对实验有重要影响的实验数据进行在线分析和数据可视化。
To achieve long steady-state performance of the EAST tokamak requires online analysis and visualization for significant experiment data.
本文介绍了中科院等离子体所ht - 6m托卡马克装置新的控制系统的设计方法、工程实现及实验运行结果。
The design, realization and experiment result of new control system of HT-6M tokamak based PC real time control have been described.
根据HT -7托卡马克装置所处不同阶段对真空的要求不同，介绍该安全保护系统如何构建以满足不同阶段的需要。
According to the operation requirements of HT-7 superconducting tokamak, a safety system for the vacuum operation is built to cover all the experimental phases.
本文系统地分析了HT—6M托卡马克等离子体水平位移平衡控制的结构和控制方式，提出了相应的数学模型和控制模式，并在HT—6 M托卡马克装置上成功地进行了实验。
In this paper, the structure and the control mode about the plasma horizontal position equilibrium control system in the HT-6M Tokamak have been analyzed systematically in terms of theory.
给出了用于HT7超导托卡马克聚变实验装置的电子回旋共振加热(ECRH)系统大功率毫米波传输线的设计。
The design of the high power millimeter wave transmission line for Electron Cyclotron Resonance Heating (ECRH) system on the HT 7 Tokamak was given.
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.
本文对以托卡马克为聚变装置、氦气冷却板状元件包层的聚变-裂变混合堆进行了稳态、卸压和全厂断电断流的热工分析。
This paper presents the thermal analyses for steady state, depressurization and total loss of flow in the tokamak heliumcooling slab fuel element fusion-fission hybrid reactor.
文章介绍HT- 7托卡马克实验装置上的中性束诊断电源系统的组成、结构，以及基于S7 - 300PLC的逻辑控制系统。
A power supply system for diagnostic neutral beam on the HT-7 Tokamak was developed. Its logic control system based on S7-300 PLC was described.
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.
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.
HL 2A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.
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.
详细地叙述了求解真空室上感应涡流的计算方法，对HTU托卡马克实验装置真空室上涡流的大小、分布形式及衰减情况进行了分析。
The numerical method of calculating these eddy currents is presented in detail. The magnitude, distribution and decay of the eddy currents on the vessel of the HTU tokamak are analysed.
详细地叙述了求解真空室上感应涡流的计算方法，对HTU托卡马克实验装置真空室上涡流的大小、分布形式及衰减情况进行了分析。
The numerical method of calculating these eddy currents is presented in detail. The magnitude, distribution and decay of the eddy currents on the vessel of the HTU tokamak are analysed.
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