Tokamak的例句大全

Suppressing tearing mode instability effectively and avoiding major disruption were observed by modulation of plasma toroidal current ( oscillating fluxes current driven) on the HT& 7 superconducting Tokamak experiment. The interaction between plasma and wall was weakened.

HT&7超导托卡马克上的实验观察到，通过对等离子体环向电流的交流调制（即振荡通量电流驱动）的方法，可有效抑制撕裂模不稳定性，从而抑制大破裂。

Stable current profile for the tearing mode in a tokamak

环流器等离子体撕裂模稳定电流剖面

The time-space structure evolution of tokamak plasma under the mutual interactions of tearing mode with transport process

输运与撕裂模相互作用下等离子体的时空结构

Test particle diffusion across a single island in a tokamak

试探粒子横越单一磁岛的扩散

In this paper, the phenomena of a test particle diffusion near a single magnetic island in a Tokamak is investigated by the method of Monte Carlo and an effective diffusion time is used to describe the effect of diffusion by the island quantitatively.

本文用试探粒子的蒙特-卡罗法计算了带电粒子横越单一磁岛的扩散，并用碰撞度和有效扩散时间来定量描述磁岛对扩散的影响。

Tokamak fusion test reactor

托卡马克聚变试验反应堆

MHD Pressure Drop Analysis for a Lithium Cooled Blanket of Tokamak Engineering Test Breeder Step forced Dynamic Speed Drop Analysis Digital Control, Dual Ring, Direct Current and Reversible Speed Governing System

托卡马克工程试验增殖堆Li冷包层的磁流体动力学压降分析数控双环直流可逆调速系统阶跃扰动动态速降分析

Using VUV lines in ion temperature measurements and observation of instability on the HL-1 TOKAMAK

用真空紫外谱线测量HL-1装置离子温度和观测等离子体不稳定性

Study on the measurement and analysis of Z_ ( eff) in the core of tokamak discharges

托卡马克芯区Z（eff）测量和分析方法的研究

Particle Simulation Study for the Electron Temperature Gradient Instability in Tokamak Toroidal Plasmas

托卡马克等离子体中电子温度梯度不稳定性的粒子模拟研究

An eigenmode equation of ion temperature gradient driven instability in a tokamak plasma with negative magnetic shear is solved numerically by the shooting method.

采用打靶法，数值求解了在负磁剪切托卡马克等离子体中离子温度梯度驱动的复本征模方程。

The effect of temperature gradient on electromagnetic two-stream instability in Tokamak

托卡马克装置中温度梯度对电磁双流不稳定性的影响

Superconduction Tokamak, especially full superconduction Tokamak, thus has become the research area for constructing the future advanced thermonuclear reactor project, and physics frontiers;

超导、特别是全超导托卡马克因此成为建造未来先进聚变堆工程、物理前沿研究领域；

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。

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

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

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。

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

Eddy Current Analysis of the Internal Thermal Shield of HT-7U Tokamak

HT-7U装置内冷屏感应电流分析

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。