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等离子体平衡    
相关语句
  plasma equilibrium
    INVESTIGATION OF PLASMA EQUILIBRIUM IN HL-1 TOKAMAK
    HL-1装置等离子体平衡实验研究
短句来源
    INVESTIGATION OF PLASMA EQUILIBRIUM ON HL-1 TOKAMAK
    HL-1装置等离子体平衡的实验研究
短句来源
    INVESTIGATION OF PLASMA EQUILIBRIUM IN HL-l TOKAMAK
    HL-1装置等离子体平衡实验研究
短句来源
    ANALYSIS OF PLASMA EQUILIBRIUM IN THE HT-7 TOKAMAK
    HT-7托卡马克中等离子体平衡研究
短句来源
    LOWER HYBRID WAVE CURRENT RAMP-UP AND PLASMA EQUILIBRIUM
    低混杂波电流驱升与等离子体平衡
短句来源
更多       
  plasma equilibrium
    INVESTIGATION OF PLASMA EQUILIBRIUM IN HL-1 TOKAMAK
    HL-1装置等离子体平衡实验研究
短句来源
    INVESTIGATION OF PLASMA EQUILIBRIUM ON HL-1 TOKAMAK
    HL-1装置等离子体平衡的实验研究
短句来源
    INVESTIGATION OF PLASMA EQUILIBRIUM IN HL-l TOKAMAK
    HL-1装置等离子体平衡实验研究
短句来源
    ANALYSIS OF PLASMA EQUILIBRIUM IN THE HT-7 TOKAMAK
    HT-7托卡马克中等离子体平衡研究
短句来源
    LOWER HYBRID WAVE CURRENT RAMP-UP AND PLASMA EQUILIBRIUM
    低混杂波电流驱升与等离子体平衡
短句来源
更多       
  plasma equilibrium
    INVESTIGATION OF PLASMA EQUILIBRIUM IN HL-1 TOKAMAK
    HL-1装置等离子体平衡实验研究
短句来源
    INVESTIGATION OF PLASMA EQUILIBRIUM ON HL-1 TOKAMAK
    HL-1装置等离子体平衡的实验研究
短句来源
    INVESTIGATION OF PLASMA EQUILIBRIUM IN HL-l TOKAMAK
    HL-1装置等离子体平衡实验研究
短句来源
    ANALYSIS OF PLASMA EQUILIBRIUM IN THE HT-7 TOKAMAK
    HT-7托卡马克中等离子体平衡研究
短句来源
    LOWER HYBRID WAVE CURRENT RAMP-UP AND PLASMA EQUILIBRIUM
    低混杂波电流驱升与等离子体平衡
短句来源
更多       
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  plasma equilibrium
Plasma equilibrium in axisymmetric open divertor configurations
      
The issue of how the plasma equilibrium changes as the parameter β≡8πp/B2 increases is considered for a fairly representative class of pressure profiles p(ψ) (where ψ is the flux coordinate).
      
The phenomenon of the internal transport barrier in a tokamak plasma is interpreted as a bifurcation of the plasma equilibrium.
      
An expression describing the change in the plasma pressure due to the buildup of the barrier is derived as a functional dependent on the parameters of the original plasma equilibrium and the plasma rotation velocity within the barrier.
      
This shift is calculated analytically, and this effect is exemplified by simple plasma equilibrium states.
      
更多          
  plasma equilibrium
Plasma equilibrium in axisymmetric open divertor configurations
      
The issue of how the plasma equilibrium changes as the parameter β≡8πp/B2 increases is considered for a fairly representative class of pressure profiles p(ψ) (where ψ is the flux coordinate).
      
The phenomenon of the internal transport barrier in a tokamak plasma is interpreted as a bifurcation of the plasma equilibrium.
      
An expression describing the change in the plasma pressure due to the buildup of the barrier is derived as a functional dependent on the parameters of the original plasma equilibrium and the plasma rotation velocity within the barrier.
      
This shift is calculated analytically, and this effect is exemplified by simple plasma equilibrium states.
      
更多          
  plasma equilibrium
Plasma equilibrium in axisymmetric open divertor configurations
      
The issue of how the plasma equilibrium changes as the parameter β≡8πp/B2 increases is considered for a fairly representative class of pressure profiles p(ψ) (where ψ is the flux coordinate).
      
The phenomenon of the internal transport barrier in a tokamak plasma is interpreted as a bifurcation of the plasma equilibrium.
      
An expression describing the change in the plasma pressure due to the buildup of the barrier is derived as a functional dependent on the parameters of the original plasma equilibrium and the plasma rotation velocity within the barrier.
      
This shift is calculated analytically, and this effect is exemplified by simple plasma equilibrium states.
      
更多          
  plasma equilibrium.
The phenomenon of the internal transport barrier in a tokamak plasma is interpreted as a bifurcation of the plasma equilibrium.
      
It is shown that, although the equilibrium conditions may be locally improved through a special choice of the profile of the plasma rotation velocity, toroidal rotation, on the whole, has a negative effect on the plasma equilibrium.
      
A bound for the pressure integral is studied by establishing ana priori estimate for a solution of the Grad-Shafranov equation of plasma equilibrium.
      
This means that y and I,, can be taken as independent parameters to specify plasma equilibrium.
      
The Appendix describes how the components of the C' vectors are calculated for a given external perturbation and plasma equilibrium.
      
更多          


The process of slow compression of plasma minor radius on tokamak is studied numerically in a time scale several times longer than the energy confinement time of plasma. A system of 1-D transport equations coupling with toroidal and poloidal magnetic field equations, and the MHD equilibrium equation has been developed. The results are compared with those in the ideal MHD model. It is shown that, after the compression, the energy confinement time increases distinctly and the temperature rise is comparable with...

The process of slow compression of plasma minor radius on tokamak is studied numerically in a time scale several times longer than the energy confinement time of plasma. A system of 1-D transport equations coupling with toroidal and poloidal magnetic field equations, and the MHD equilibrium equation has been developed. The results are compared with those in the ideal MHD model. It is shown that, after the compression, the energy confinement time increases distinctly and the temperature rise is comparable with that evaluated by the adiabatic compression scaling. The effect on compression heating due to magnetic diffusion seems to be insignificant.

本文应用一维输运模型,耦合了纵场与角向场的磁感应方程及等离子体平衡方程,对于压缩时间几倍于能量约束时间的托卡马克小半径方向慢压缩放电过程进行了计算,并与应用磁冻结假设下的计算进行了比较。结果表明,慢压缩时等离子体能量约束时间有成倍或数倍增大,且磁扩散效应不影响压缩效果,等离子体温度有接近于绝热压缩定标的增高。

A stable equilibrium plasma with the current of 135 kA and the plateau time of 150 ms have been obtained on HL-1 TOKAMAK which operates at the toroidal' magnetic field of 2.3 kT. The electron temperature is approximately 500 eV, electron density is 2.3x 1013cm"3, energy confinement time reaches 10 ms, effective charge number less than 3 and minimum safety factor for stable operation is 2.5. The experimental results show that the stray component of the toroidal magnetic field is only about hundred millionth,...

A stable equilibrium plasma with the current of 135 kA and the plateau time of 150 ms have been obtained on HL-1 TOKAMAK which operates at the toroidal' magnetic field of 2.3 kT. The electron temperature is approximately 500 eV, electron density is 2.3x 1013cm"3, energy confinement time reaches 10 ms, effective charge number less than 3 and minimum safety factor for stable operation is 2.5. The experimental results show that the stray component of the toroidal magnetic field is only about hundred millionth, and the equilibrium magnetic field with the copper shell can sustain the plasma equilibrium.The discharge lasts time can reach 1.04sec. On the basis of detail observation on MHD instability, the stable operation region have been determined, the critical density is consistent with Murakami scaling under present ohmic heating condition the energy confinement time obeys Alcator C scaling.A detail analysis and discussion on the experimental results is given,

HL-1装置在纵向磁场2.3T下运行,获得了135kA平衡稳定等离子体(平顶时间150ms)。电子温度500eV,电子密度2.5×10~(13)cm~(-3),能量约束时间10ms,有效电荷数小于3,最低稳定运行安全因子2.5。实验表明,纵场杂散分量仅约纵场的万分之一,导体壳和平衡场基本上能保证等离子体的平衡。放电延续时间可长达1.04s。在对MHD稳定性进行大量观测的基础上,确定了稳定运行区域;极限密度符合Murakami定标律。在现有的欧姆加热条件下,能量约束时间服从Alcator C定标律。 本文对实验结果进行了综合分析讨论。

In this paper, the plasma equilibrium in HL-1 tokamak has been discussed. The horizontal and vertical displacement of plasma is measured using a symmetical magnetic probe system, and the temporal evolution of displacements is given by a data acquisition system with micro-computer. The influence of various stray fields on plasma equilibrium has been analysed.. The direction and value of horizontal stray field induced by the toroidal field coils and primary windings are determined using vertical displacement data.By...

In this paper, the plasma equilibrium in HL-1 tokamak has been discussed. The horizontal and vertical displacement of plasma is measured using a symmetical magnetic probe system, and the temporal evolution of displacements is given by a data acquisition system with micro-computer. The influence of various stray fields on plasma equilibrium has been analysed.. The direction and value of horizontal stray field induced by the toroidal field coils and primary windings are determined using vertical displacement data.By adjusting parameters of internal and external vertical field, in the flat part of discharge current, the plasma can be kept in its equilibrium state at the place where is 3 cm outer of chamber center, i.e nearby the center of limiter.

本文讨论HL-1装置等离子体的平衡。用对称磁探针测量了等离子体的水平位移和垂直位移,并由微机数据处理系统即时给出位移随时间的变化规律。分析了装置存在的各种杂散场对等离子体平衡的影响。通过垂直位移测量鉴别了纵向场线圈和加热场绕组引起的水平杂散场的方向和大小。实验表明,选取合适的内、外垂直场参数,在电流的平顶段,能使等离子体稳定平衡于真空室小截面中心外侧3cm的位置,即在装置孔栏中心附近。

 
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