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plasma disruption
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  等离子体破裂
     The COSMOS/M code is used to investigate the FEB modules during plasma disruption.
     用COSMOS/M 程序对在等离子体破裂期间的FEB模件进行了研究。
短句来源
     In this artical, we use pulse laser beam to simulate the hent flux from plasma disruption
     报道使用脉冲激光束来模拟等离子体破裂产生的热负荷对面对等离子体壁材料石墨的热负荷影响的实验研究方法和结果。
短句来源
     One of the most diffuculties in designing ICRH antenna is how to analyse and estimate the electric forces on it when so high a plasma current disappears rapidly as the plasma disruption occurs.
     本文讨论了在设计离子迴旋共振加热天线时,如何考虑由于等离子体破裂引起的强等离子体电流瞬时变化加于天线的电动力的影响。 这种影响往往是这种天线设计过程中所遇到的最困难的问题之一。
短句来源
     Surface damage of tungsten during plasma disruption
     钨在等离子体破裂时的表面损伤
短句来源
     The thermal shock behavior of 4 kinds of impurity doped graphites was investigated under a simulated plasma disruption condition using high-energy laser and electron beam.
     用高能激光束和电子束轰击实验材料 ,模拟聚变堆面对等离子体材料在等离子体破裂时的工作状态 ,考察了 4种掺杂石墨材料在热冲击下的热腐蚀规律。
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  等离子体大破裂
     An Overview on Plasma Disruption Mitigation and Avoidance in Tokamak (In Chinese)
     托卡马克等离子体大破裂及防治综述
短句来源
  “plasma disruption”译为未确定词的双语例句
     ELECTRIC FORCES ON ICRH ANTENNA IN TOKAMAK CAUSED BY PLASMA DISRUPTION
     托卡马克中离子迴旋共振加热天线的电动力问题
短句来源
     The azimuthal mode number of this instability is one. The critical beta value for plasma disruption due to the interchange mode is about 5%. The line-tying effect of conducting wall has important stabilizing influence on the interchange mode.
     被磁镜场捕获的等离子体驱动了m=1的交换不稳定性,等离子体发生破裂的临界β值约5%,导电壁的线结效应对交换模有稳定作用。
短句来源
     It consists of a 5T-138mm bore, superconducting background magnet, a pair of pulsed superconducting solenoids which can superimpose a dB/dt up to 10T/s during their discharge to the tested samples and a supercritical helium cooling system. This facility will be used to simulate the operating condition of CICC in tokamak S.C. magnet system which are subjected to the disturbances due to the poloidal field magnet pulsed and plasma disruption.
     该装置包括一个 5T - 138mm口径的长均匀区背场超导磁体、一对可产生 10T/s磁场变化率的脉冲超导磁体 ,以及人工超临界氦系统 ,它可以将高压室温氦气通过冷却变成可以冷却超导CICC导体的超临界氦 .
短句来源
     The phenomena and processes of the precursor, thermal quench, current quench, VDE, halo current and runaway electrons generation during plasma disruption are analyzed in detail and systematically based on the data obtained from current Tokamaks such as TFTR, JET, JT-60U and ASDEX-U, etc.
     该文以当今运行的托卡马克提供的相关数据为依据,比较全面系统地分析了托卡马克大破裂的先兆、热猝灭、电流猝灭、垂直位移运动、晕电流和逃逸电子产生等现象及过程,并就预防措施进行了概括的描述。
短句来源
     In this paper, eddy current for the Toroidal field superconducting magnet in HT7U Tokamak device and the heat removal through the forced flow supercritical helium has been investigated. The thermal analysis is made for the particular status of a plasma disruption.
     分析了HT-7U超导Tokamak核聚变装置中环向场超导线圈上的涡流损耗热产生的机理和迫流式超临界氦对流换热等过程。
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  plasma disruption
The source heat fluence (variable from 0.2 to 7 MJ/m2) is adequate for simulation of the thermal quench phase of plasma disruption in future fusion tokamaks.
      
The mechanical strength of the first wall of power reactor is inadequate to withstand the thermal load expected during plasma disruption in an experimental reactor.
      
An experimental study was made on the behavior of a solid surface subjected to an extremely high heat flux similar to that expected during a plasma disruption.
      
A simulated plasma disruption experiment using an electron beam as a heat source
      
Effect of implanted helium on nickel stability in simulation of plasma disruption in a thermonuclear reactor
      
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Experimental investigation of plasma stream injection into a simple mirror device has been performed. The parameters of the plasma stream are determined The electron temperature is 4eV; the velocity of stream is about 5×10~6cm/s. The plasma density and plasma current reach 10~(14)cm(-3) and 450A, respectively. The plasma trapped in the mirror device drives an interchange instability. The azimuthal mode number of this instability is one. The critical beta value for plasma disruption due to the interchange...

Experimental investigation of plasma stream injection into a simple mirror device has been performed. The parameters of the plasma stream are determined The electron temperature is 4eV; the velocity of stream is about 5×10~6cm/s. The plasma density and plasma current reach 10~(14)cm(-3) and 450A, respectively. The plasma trapped in the mirror device drives an interchange instability. The azimuthal mode number of this instability is one. The critical beta value for plasma disruption due to the interchange mode is about 5%. The line-tying effect of conducting wall has important stabilizing influence on the interchange mode.

本文叙述简单磁镜中,等离子体流注入的实验结果。被磁镜场捕获的等离子体驱动了m=1的交换不稳定性,等离子体发生破裂的临界β值约5%,导电壁的线结效应对交换模有稳定作用。

The induced voltages and currents due to plasma disruptions in the surrounding conductors are presented.The induced eddy currents,magnetic fields and electromagnetic forces in the vacuum vessel and copper shell are calculated.Their influence on engineering of the HL-1 device is analysed.

本文描述HL-1装置放电过程中,等离子体破裂及环形导体中感应电压和电流的精细测量。给出了破裂时内真空室和铜壳的感应涡流、磁场和电动力。分析了它们对装置工程的影响。

One of the most diffuculties in designing ICRH antenna is how to analyse and estimate the electric forces on it when so high a plasma current disappears rapidly as the plasma disruption occurs. In this paper, a means to analyse and calculate these forces isgiven.

本文讨论了在设计离子迴旋共振加热天线时,如何考虑由于等离子体破裂引起的强等离子体电流瞬时变化加于天线的电动力的影响。这种影响往往是这种天线设计过程中所遇到的最困难的问题之一。本文将给出考虑这种电动力的方法以及计算公式。结合HT-6M托卡马克的天线参数,给出了计算结果。

 
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