tokamak
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英
词形变化
复数：tokamaks
英汉解释
英英解释
例句
Basic principle ofthe controlled nuclear fusion and the Tokamak device used for nuclear fusion reaction are presented in brief.
简要地叙述了受控核聚变反应的基本原理和实现受控核聚变反应的托卡马克装置。
Industrial hygiene concerns during the decontamination and decommissioning of the Tokamak fusion test reactor.
托卡马克聚变试验堆去污和退役期间工业保健学相关性…[中国核科技信息与经济研究院]。
Theoretical and experimental investigations on advanced Tokamak are the major concerns in present controlled fusion research.
对先进托卡马克理论和实验研究是当前受控核聚变研究的中心问题。
Progress towards internal transport barriers at high plasma density sustained by pure electron heating and current drive in the FTU tokamak.
FTU托卡马克中由纯电子加热和电流驱动维持的高等离子体密度条件下内输运壁的发展方向…[中国核科技信息与经济研究院]。
Potentials and currents in the edge tokamak plasma: simplified approach and comparison with two-dimensional modelling.
边缘托卡马克等离子体中电位和电流：简化方法和与二维模型的比较…[中国核科技信息与经济研究院]。
For safe reason, an overall check and analysis of cryogenic mechanics property for EAST Tokamak composite insulators is needed.
从整个装置的使用安全考虑，有必要对绝缘子低温力学性能作全面分析。
Spherical Tokamak is showing an attractive promising route for commercial application of fusion energy.
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。
One is the tokamak design, trapping the charged atoms within a doughnut-shape magnetic field.
一种是把带电原子收束在一个圆环状的磁场内的托卡马克热核反应装置。
The diagnostic systems for plasma current and loop voltage measurement on the HL-2A tokamak have been described in detail.
详细描述了HL-2A托卡马克装置上等离子体环电流、环电压诊断系统，其中包括测量原理、诊断安排、实验等方面的内容。
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。
The design and implementation of the protection for LHCD antenna transmission line on EAST tokamak are described in detail.
介绍了EAST低杂波系统天馈线保护的设计及其实现。
Microscopic damage of metals exposed to the helium discharges in TRIAM-1M Tokamak and its impact on hydrogen recycling process.
1M托卡马克中暴露于氦放电中的金属微观损伤和其对氢再循环过程影响…[中国核科技信息与经济研究院]。
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。
ITER is what is known as a tokamak, a doughnut-shaped device invented in Russia at about the same time Zeta was active.
国际热核反应堆就是我们所熟知的托克马克装置。当Zeta反应堆开始工作的时候，俄国人就发明这个形状像甜甜圈的家伙。
Calibration and analysis of the vacuum system of HT-7 superconductor Tokamak were discussed.
主要介绍HT-7超导托卡马克装置真空系统参数的标定和分析。
As non-circle and divertor Tokamak device like EAST, confirming the poloidal current is very important both in design and future operation.
在EAST核聚变托卡马克实验装置中，无论是在设计阶段还是未来运行过程中，确定极向场线圈电流都是非常重要的。
The design and realization of control system of Neutral Beam Injection (NBI) for HT-7 tokamak are introduced.
介绍了中科院等离子体所HT-7托卡马克装置上中性束注入（NBI）控制系统设计方案和实现方法。
Measurement of Spectral Profiles in Tokamak Plasma with an Optical Scanner Spectrometer
振镜扫描光谱仪用于托卡马克等离子体谱线轮廓测量
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
Design and implementation of a common data analysis software for EAST Tokamak
EAST装置通用数据分析软件的设计与实现
Development of a visualized software for tokamak experiment data processing
托卡马克实验数据的可视化时序处理软件开发
Numerical Simulation and Parallel Efficiency of Internal Transport with Barrier Trigger in Tokamak Plasmas
托卡马克等离子体内部输运垒触发机制的数值模拟和并行效率
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
Establishment of the Survey Control Networks for EAST Tokamak Device Assembly
托卡马克核聚变装置主机安装测量控制基准建立
Plasma Density Remote Control System of Experimental Advanced Superconductive Tokamak
先进超导托卡马克实验装置等离子体密度远程控制系统
Electromagnetic ITG modes in internal transport barrier of Tokamak plasmas
托卡马克等离子体内部输运壁垒中电磁ITG模
Development of a data analysis and visualization software for the HT-7 tokamak experiment
HT-7装置实验数据分析与可视化集成软件开发
The application of wavelet in processing the control signal of fast control power supply in EAST tokamak
小波在EAST快控电源控制信号处理中的应用研究
Reactor Core Design of Spherical Tokamak Transmutation of Nuclear Wastes
小球形托卡马克嬗变堆堆芯参数分析
Overvoltage Protection for Plasma Disruption in Tokamak
托卡马克中等离子体破裂时的过电压研究
H-Mode Behavior and Radial Electric Field Induced by Modulated Plasma Current in Tokamak
调制托卡马克等离子体电流对H模式行为和径向电场的影响
Physical analysis of electron injection by electrical drift in Tokamak
托卡马克电场漂移电子注入的物理分析研究
The Glass-Fiber Tape in Cryogenic Superconducting Magnets of TOKAMAK
托卡马克超导磁体绝缘用玻璃纤维带
Determination of ohmically driven tokamak equilibrium
欧姆驱动托卡马克平衡位形的确定
The Propagation of Electron Cyclotron Waves in Tokamak Plasmas
电子回旋波在托卡马克等离子体中的传播
Influence of Tokamak Poloidal Magnetic Field on Electron Cyclotron Wave Absorption
托卡马克极向磁场对电子回旋波吸收的影响
Electron cyclotron current drive in tokamak plasmas
托卡马克等离子体中的电子回旋波电流驱动
Relationship Between Electron Thermal Diffusivity and Plasma Parameters on the HT-7 Tokamak
HT-7托卡马克等离子体电子热扩散系数与等离子体参数的关系
Measurement of Fusion Neutron Energy Spectrum in Tokamak
托卡马克中聚变中子的能谱测量
Time-resolved Neutron Flux Density Measurement on HT-7 Superconducting Tokamak
HT-7超导托卡马克上时间分辨中子注量率测量
