Tokamak

It is very important that spectrum measurement of D-D and D-T fusion neutron in large 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.

Optimum design of the PF coil system on the HL-2A tokamak

HL-2A极向场线圈系统的优化设计

J-TEXT Tokamak is an experimental facility designed for fusion research.

TEXT托卡马克是用来研究热核聚变的实验装置.

Study on Exact Protection against the Normal State of the Superconductivity Toroidal Field Magnet on the HT-7 Tokamak

HT-7托卡马克装置纵场超导磁体失超保护可靠性研究

Experimental study of large power lower hybrid current drive on HT-7 tokamak

HT-7托卡马克大功率低混杂波电流驱动的实验研究

The thermal shield ( TS ) is a main part of EAST superconducting Tokamak.

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 core plasma characteristics of a tokamak reactor with aspect ratio near 2 are studied.

初步研究了环径比接近2的托卡马克堆芯等离子体的基本特征.

This article outlines a model for calculating the parameters oi a tokamak fusion reactor core.

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。

Deputy Director of Tokamak Division , Institute of Plasma Physics, Chinese Academy of Sciences.

中国科学院等离子体物理研究所托卡马克研究室副主任.

Electron cyclotron current drive under different operational regimes in tokamak plasma

托卡马克等离子体不同运行模式下的电子回旋波电流驱动

On lower hybrid current drive efficiency in the HL 1 Tokamak

关于HL－1托卡马克的低杂波电流驱动效率

ITER ( International Thermonuclear Experimental Reactor) is a planning international Tokamak reactor designed to demonstrate the feasibility of the full dimensions controlled nuclear fusion technology.

ITER（国际热核聚变实验实验堆）是规划建设中的一个为验证全尺寸可控核聚变技术的可行性而设计的国际托卡马克实验堆。

Measurement of the plasma electron temperature in the HL 1M Tokamak

HL-1M装置等离子体电子温度测量

This article introduces some improving work on impurities control of vacuum system in EAST TOKAMAK device.

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.

BURNUP CALCULATION FOR A TOKAMAK COMMERCIAL HYBRID REACTOR.

商用航空电子设备用的微波管.

Using a multichannel quartz optical-fiber system calibrated with a standard tungsten strip lamp, the radial profiles of the visible bremsstrahlung radiation power in the HL-1 tokamak were measured.

采用经钨带灯标准光源标定的多道石英光纤光学系统，测量了HL-1装置等离子体可见光波段轫致辐射功率的径向分布。

Study of Control Data Publishing System on HT-7 Superconduction Tokamak

HT-7超导托卡马克总控数据发布系统研究

Ion viscosity effect on Tokamak resistive INTERNAL KINK mode

电阻性磁流体内扭曲模的离子粘滞性效应

A special testing method for EAST Tokamak insulator is introduced.

笔者介绍了EAST托卡马克绝缘子绝缘性能特殊的测试方法.

Inside the Tokamak are a series of magnets powered by the plant.

这个受控热核反应装置内部是用一系列电磁体作能源.

An application of this system has been demonstrated succeed on HT-7 tokamak in 2005.

该系统已在2005年度HT -7 托卡马克实验中得到了成功应用.

In Tokamak device, the behavior of plasma is difficult to analyze and control.

在托卡马克装置中, 等离子体的行为是很难精确预测和控制的.

The equivalent model and theory analysis of copper shell in HT 7 super conductive Tokamak

HT-7超导托卡马克铜壳在等离子体放电中的作用分析

In order to recycle Tokamak exhaust gases expelled from nuclear fusion reactors, the hydrogen isotope mixture gas which contain the impurities of oxygen and nitrogen has been purified by the means of the method of catalytic deoxygenization and cryogenic ( i.e. liquid nitrogen temperature 77.4 K) absorption.

为了回收利用核聚变反应堆排出的托卡马克废气，将含有氧、氮杂质的氢同位素混合气，通过催化剂脱氧，低温（774K）吸附的方法，进行了净化处理。

Head of tokamak experiment division, institute of plasma physics, Chinese Academy of Sciences.

中国科学院等离子体物理研究所托卡马克实验室主任.

Design of toroidal field magnet system for superconducting tokamak HT-7U

HT-7U托卡马克核聚变装置中纵场超导磁体系统的设计

Mass resolving charge exchange neutral particle measurement on HT 7 Tokamak

HT-7质能分辨电荷交换中性粒子分析

Thermal Analysis in Toroidal Field Superconducting Magnet of the Tokamak Device

大型Tokamak装置中环向场超导线圈的传热研究

Low Aspect Ratio ( LAR) Tokamak, as an excellent neutron source, was effectively applied in early stage of the fusion energy study. Using the existence theory of solution developed by J.

低环径比（LAR）聚变托卡马克可作为一种紧凑中子源，为聚变早期利用提供了有效途径。

Ignition start-up course calculation and ignition charge mass selection of impulse micro-thruster Start up processes of D T burning in a tokamak reactor for different heating scenarios are studied.

微型脉冲推力器点火启动过程计算与点火药量选择研究了不同的加热功率沉积剖面对托卡马克反应堆点火启动过程的影响。