tokamak
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英 
詞形變化
復數:tokamaks
英漢解釋
英英解釋
例句
Basic principle ofthe controlled nuclear fusion and the Tokamak device used for nuclear fusion reaction are presented in brief.
簡要地敘述了受控核聚變反應的基本原理和實現受控核聚變反應的托卡馬克裝置。
Industrial hygiene concerns during the decontamination and decommissioning of the Tokamak fusion test reactor.
托卡馬克聚變試驗堆去污和退役期間工業保健學相關性…[中國核科技信息與經濟研究院]。
Theoretical and experimental investigations on advanced Tokamak are the major concerns in present controlled fusion research.
對先進托卡馬克理論和實驗研究是當前受控核聚變研究的中心問題。
Progress towards internal transport barriers at high plasma density sustained by pure electron heating and current drive in the FTU tokamak.
FTU托卡馬克中由純電子加熱和電流驅動維持的高等離子體密度條件下內輸運壁的發展方向…[中國核科技信息與經濟研究院]。
Potentials and currents in the edge tokamak plasma: simplified approach and comparison with two-dimensional modelling.
邊緣托卡馬克等離子體中電位和電流:簡化方法和與二維模型的比較…[中國核科技信息與經濟研究院]。
For safe reason, an overall check and analysis of cryogenic mechanics property for EAST Tokamak composite insulators is needed.
從整個裝置的使用安全考慮,有必要對絕緣子低溫力學性能作全面分析。
Spherical Tokamak is showing an attractive promising route for commercial application of fusion energy.
球形托卡馬克為聚變能的商業應用提供了一條可能的途徑。
One is the tokamak design, trapping the charged atoms within a doughnut-shape magnetic field.
一種是把帶電原子收束在一個圓環狀的磁場內的托卡馬克熱核反應裝置。
The diagnostic systems for plasma current and loop voltage measurement on the HL-2A tokamak have been described in detail.
詳細描述了HL-2A托卡馬克裝置上等離子體環電流、環電壓診斷系統,其中包括測量原理、診斷安排、實驗等方面的內容。
This article introduces some improving work on impurities control of vacuum system in EAST TOKAMAK device.
本文介紹了基于EAST超導托卡馬克裝置真空系統雜質控制系統的改進工作。
The design and implementation of the protection for LHCD antenna transmission line on EAST tokamak are described in detail.
介紹了EAST低雜波系統天饋線保護的設計及其實現。
Microscopic damage of metals exposed to the helium discharges in TRIAM-1M Tokamak and its impact on hydrogen recycling process.
1M托卡馬克中暴露于氦放電中的金屬微觀損傷和其對氫再循環過程影響…[中國核科技信息與經濟研究院]。
A special testing method for EAST Tokamak insulator is introduced.
筆者介紹了EAST托卡馬克絕緣子絕緣性能特殊的測試方法。
ITER is what is known as a tokamak, a doughnut-shaped device invented in Russia at about the same time Zeta was active.
國際熱核反應堆就是我們所熟知的托克馬克裝置。當Zeta反應堆開始工作的時候,俄國人就發明這個形狀像甜甜圈的家伙。
Calibration and analysis of the vacuum system of HT-7 superconductor Tokamak were discussed.
主要介紹HT-7超導托卡馬克裝置真空系統參數的標定和分析。
As non-circle and divertor Tokamak device like EAST, confirming the poloidal current is very important both in design and future operation.
在EAST核聚變托卡馬克實驗裝置中,無論是在設計階段還是未來運行過程中,確定極向場線圈電流都是非常重要的。
The design and realization of control system of Neutral Beam Injection (NBI) for HT-7 tokamak are introduced.
介紹了中科院等離子體所HT-7托卡馬克裝置上中性束注入(NBI)控制系統設計方案和實現方法。
Measurement of Spectral Profiles in Tokamak Plasma with an Optical Scanner Spectrometer
振鏡掃描光譜儀用于托卡馬克等離子體譜線輪廓測量
Particle Simulation Study for the Electron Temperature Gradient Instability in Tokamak Toroidal Plasmas
托卡馬克等離子體中電子溫度梯度不穩定性的粒子模擬研究
Design and implementation of a common data analysis software for EAST Tokamak
EAST裝置通用數據分析軟件的設計與實現
Development of a visualized software for tokamak experiment data processing
托卡馬克實驗數據的可視化時序處理軟件開發
Numerical Simulation and Parallel Efficiency of Internal Transport with Barrier Trigger in Tokamak Plasmas
托卡馬克等離子體內部輸運壘觸發機制的數值模擬和并行效率
Electron cyclotron current drive under different operational regimes in tokamak plasma
托卡馬克等離子體不同運行模式下的電子回旋波電流驅動
Establishment of the Survey Control Networks for EAST Tokamak Device Assembly
托卡馬克核聚變裝置主機安裝測量控制基準建立
Plasma Density Remote Control System of Experimental Advanced Superconductive Tokamak
先進超導托卡馬克實驗裝置等離子體密度遠程控制系統
Electromagnetic ITG modes in internal transport barrier of Tokamak plasmas
托卡馬克等離子體內部輸運壁壘中電磁ITG模
Development of a data analysis and visualization software for the HT-7 tokamak experiment
HT-7裝置實驗數據分析與可視化集成軟件開發
The application of wavelet in processing the control signal of fast control power supply in EAST tokamak
小波在EAST快控電源控制信號處理中的應用研究
Reactor Core Design of Spherical Tokamak Transmutation of Nuclear Wastes
小球形托卡馬克嬗變堆堆芯參數分析
Overvoltage Protection for Plasma Disruption in Tokamak
托卡馬克中等離子體破裂時的過電壓研究
H-Mode Behavior and Radial Electric Field Induced by Modulated Plasma Current in Tokamak
調制托卡馬克等離子體電流對H模式行為和徑向電場的影響
Physical analysis of electron injection by electrical drift in Tokamak
托卡馬克電場漂移電子注入的物理分析研究
The Glass-Fiber Tape in Cryogenic Superconducting Magnets of TOKAMAK
托卡馬克超導磁體絕緣用玻璃纖維帶
Determination of ohmically driven tokamak equilibrium
歐姆驅動托卡馬克平衡位形的確定
The Propagation of Electron Cyclotron Waves in Tokamak Plasmas
電子回旋波在托卡馬克等離子體中的傳播
Influence of Tokamak Poloidal Magnetic Field on Electron Cyclotron Wave Absorption
托卡馬克極向磁場對電子回旋波吸收的影響
Electron cyclotron current drive in tokamak plasmas
托卡馬克等離子體中的電子回旋波電流驅動
Relationship Between Electron Thermal Diffusivity and Plasma Parameters on the HT-7 Tokamak
HT-7托卡馬克等離子體電子熱擴散系數與等離子體參數的關系
Measurement of Fusion Neutron Energy Spectrum in Tokamak
托卡馬克中聚變中子的能譜測量
Time-resolved Neutron Flux Density Measurement on HT-7 Superconducting Tokamak
HT-7超導托卡馬克上時間分辨中子注量率測量