HL-1M装置边缘等离子体结构研究

描述HL-1M装置上几种典型放电中的边缘等离子体物理实验结果.利用马赫/朗缪尔6探针组、静电4探针组、20组三探针阵列研究了低杂波电流驱动、超声分子束注入、多发弹丸注入和中性束注入放电中的粒子约束性能、等离子体旋转和边缘静电雷诺胁强的变化对改善约束的影响.给出了雷诺胁强和极向相速度的关系.结果表明，雷诺胁强的径向变化可以自发产生托卡马克等离子体的剪切极向流.LHCD能使低密度放电的粒子约束增加1至2倍.弹丸注入后，粒子约束时间和极向旋转至少可增加1倍，而SMBI可使粒子约束时间增加约一个数量级并取得高性能等离子体. 关键词： 粒子约束 雷诺胁强 极向流剪切 马赫/朗缪尔6探针组     

ITER数据库和HL-1M装置等离子体约束特性

ITER数据库是全世界聚变专家通过多年的努力,建立起来的一个旨在研究各种等离子体行为的数据库,并由此得到了一系列的定标律。在介绍了ITER约束数据库的构成和相应的能量约柬定标律之后,介绍了HL-1M托卡马克的数据特点,给出了欧姆加热条件下利用回归分析方法得到的能量约束幂指数定标律,最后对结果进行了分析和讨论。     

用激光吹气注入高Z杂质使HL-1M托卡马克放电安全终止的研究

采用高Z杂质注入HL-1M等离子体中, 触发等离子体电流衰竭的实验已经施行.用激光吹气注入高Z杂质能够增加辐射冷却，等离子体在-3ms时间内迅速冷却而且在电流终止之前电子温度损失约80%.实验证明：它是一种使得大型聚变实验装置上在放电破裂之前显著减少等离子体中热能而且安全终止放电的简单、快速和有效的途径. 关键词： 高Z杂质 破裂 等离子体终止 激光吹气     

Disruption mitigation using laser ablation of high-Z impurities in HL-1M tokamak

A preliminary experiment triggering a plasma current quench by laser ablation of high-Z impurities has been performed in the HL-1M tokamak. The injection of impurities with higher electric charges into tokamak plasmas can increase the radiation cooling of the plasma. Resistive, highly radiating plasma formed prior to the thermal quench can dissipate both the thermal and magnetic energies, which is possibly a simple and potential approach to reducing significantly the plasma thermal energy and magnetic energy before a disruption thereby a safe plasma termination is obtained.     

托卡马克等离子体中内部磁扰动的测量研究

热等离子体中内部磁扰动水平可以由逃逸电子输运来确定，逃逸电子输运采用扰动实验和稳态实验等四种不同方法较容易获得某些局域的逃逸扩散系数，首先利用等离子体快速移动实验，测量孔栏上硬X射线通量的变化，获得边缘扩散系数；第二，由微波辐射强度和硬X射线通量(HXR)信号的锯齿振荡的峰值延迟时间得到径向位置某处到孔栏之间平均扩散系数；第三，软X射线(SXR)强度和HXR通量的信号的锯齿振荡的峰值延迟时间给出等离子体芯区外的径向平均扩散系数；第四，由来自孔栏上HXR韧致辐射谱求得逃逸电子平均能量，继而得到逃逸约束时间， 关键词： 逃逸电子输运 扩散系数 内部磁涨落 软X射线(SXR) 硬X射线 (HXR)     

HL-1M装置上MHD不稳定性磁扰动模的传播

对在HL-1M装置放电实验中发现的宏观MHD不稳定性磁扰动模的传播现象进行了研究。通过对实验中发现的各种极向模数m值的MHD磁扰动模特征的观察,以及在不同放电条件,特别是在偏压H模放电下传播方向不同的分析,深入研究了MHD模传播与等离子体旋转的定性关系。     

Calculation of transport parameters in KT-1 tokamak edge plasma

The radial profiles of KT-1 tokamak (major radius of 27 cm, minor radius of 4.25 cm, two poloidal stainless-steel limiters) edge plasma parameters are measured using single and triple electric probes. The particle transport parameters are calculated from the measured edge plasma parameters, and the results are analyzed by the simple fluid approximations. The cross-field particle diffusion coefficient (D) in the boundary plasma of the KT-1 is calculated from the density scrape-off length (λ_n) measured by using a triple probe. The particle density and electron temperature fall exponentially in the radial direction with the e-folding length of λ_n=0.13 cm and λ_e=0.41 cm, respectively. From the scrape-off layer (SOL) model, the experimental values of scrape-off length (λ_n) is used to calculate the cross-field diffusion coefficient (D=1.2×10³cm²/s), roughly corresponding to one third of the typical Bohm value. A simple SOL model with the contribution of recombination is introduced to evaluate the Bohm diffusion in the KT-1 tokamak edge plasma. Cross-field heat conductivity calculated from these deduced values is 5.2D in the SOL of KT-1 edge plasma. These results provide the finally certain information for edge particle transport in the KT-1 boundary plasmas.     

HL-2M等离子体对共振磁扰动线圈电流相位响应的模拟

在HL-2M托卡马克平衡位形(Ip=1.0MA,βN=1.62,q95=4.01)下,使用环形单流体程序MARS-F研究了等离子体对共振磁扰动(RMP)线圈电流相位差的响应.在最优相位差时,扰动磁场显著地改变边界层磁场的拓扑,形成明显的磁岛链,增加了等离子体在边界层的输运,降低了压强梯度,减小了对ELM的驱动.模拟结果...     

Studies of internal magnetic fluctuation in the HL-1M tokamak

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HL-1M装置逃逸电子的定标律

使用一维数值模型, 推断了逃逸能量ε_r与逃逸约束时间τ_r的关系。模拟结果给出能量ε_r 和放电参数的定标律。在HL- 1M 装置中不同实验条件下测量了硬X 射线谱, 研究了逃逸电子能量 ε_r模拟的定标律, 并推导出HL- 1M 装置放电的逃逸电子的约束时间与逃逸电子扩散系数。     

Self-organization in a tokamak plasma

Conclusions The observed tendency for certain optimal current-density and pressure profiles to be maintained can be interpreted if one assumes a relaxed state in the plasma, which corresponds to minimal total energy for a given current. With optimal power deposition, when the current-density and pressure profiles also remain optimal, ohmic scaling may be maintained up to fairly high densities, i.e., fairly high _p. If the power deposition profile deviates from optimal, the plasma resists deviation from the optimal profiles, and the more so the higher _p. The thermal-conductivity profile is modified to maintain the relaxed state. Nonoptimal profiles may lead to degradation in the global energy lifetime _E, which can be related phenomenologically to pumping of magnetic noise by the excess free energy F. Our argument provides a qualitative explanation of the self-organization physics.Translated from Izvestiya Vysshikh Uchebnykh Zavedenii, Radiofizika, Vol. 29, No. 9, pp. 1032–1040, September, 1986.     

HL-1M装置电子回旋加热过程中的超热电子测量

在HL-1M托卡马克上进行的电子圆旋共振加热实验表明,在低等离子体密度加热过程中。产生大量的超热电子。由Si(Li)和碘化汞(HgI2)半导体探测器阵列测量到的软X射线和中能(15～150keV)X射线能谱,得到超热电子的温度在30～60keV范围内。中能X射线辐射强度测量结果证实,等离子体对电子圆麓波的吸收是定域性的。在超热电子对MHD的相互作用中,主要的m／n=2/1模没有增强或抑制现象。     

HL-1M托卡马克中的中子通量和辐射剂量当量测量

用5台带有慢化剂(聚乙烯)的BF3₃正比计数管中子探测器测量中子通量和剂量当 量.4台 置于HL_1M装置的四周,分别测量了在氘等离子体条件下,因欧姆加热和波加热产生的热核聚 变中子产额、中子通量和剂量,以及氢等离子体条件下因高能x射线引起的光致核反应而产生 的光致中子. 另一台流动于其他6个观察点,主要监测中子剂量当量. 在D_D聚变条件下,实测 中子产额与计算值作比较,两者在数量级上大体一致. 中子辐射剂量当量远低于国家和部颁 标准,更低于国际防护委员会推荐的中子辐射允许剂量当量 关键词： 3正比计数管')" href="#">BF3₃正比计数管 光致中子 氘_氘聚变中子 剂量当量     

Drift-wave fluctuation in an inviscid tokamak plasma

In order to describe the characterization of resistive drift-wave fluctuation in a tokamak plasma,a coupled inviscid two-dimensional Hasegawa–Wakatani model is investigated.Two groups of new analytic solutions with and without phase shift between the fluctuant density and the fluctuant potential are obtained by using the special function transformation method.It is demonstrated that the fluctuant potential shares similar spatio–temporal variations with the density.It is found from the solutions without phase shift that the effect of the diffusion and adiabaticity on the fluctuant density is quite complex,and that the fluctuation may be controlled through the adiabaticity and diffusion.By using the typical parameters in the quasi-adiabatic regime in the solutions with phase shift,it is shown that the density gradient becomes larger as the contours become dense toward the plasma edge and the contours have irregular structures,which reveal the nonuniform distribution in the tokamak edge.     

Nonlinear evolution of q=1 triple tearing modes in a tokamak plasma

In magnetic configurations with two or three q=1 (with q being the safety factor) resonant surfaces in a tokamak plasma, resistive magnetohydrodynamic modes with poloidal mode numbers m much larger than 1 are found to be linearly unstable. It is found that these high-m double or triple tearing modes significantly enhance through nonlinear interactions the growth of the m=1 mode. This may account for the sudden onset of the internal resistive kink, i.e., the fast sawtooth trigger. Based on the subsequent reconnection dynamics that can proceed without formation of the m=1 islands, it is proposed that high-m triple tearing modes are a possible mechanism for precursor-free partial collapses during sawtooth oscillations.     

Probe measurements of the boundary plasma parameters in the TM-1-MH tokamak

Czechoslovak Journal of Physics -     

相关分析法确定HL-1M装置磁流体的扰动模式

采用相关分析法模拟分析了HL-1M装置的磁扰动模式,模拟的结果同预期的结果一致。在具有磁流体不稳定性的典型放电中,探测到独立模m=2、3、4,耦合模m=2、3,以及同时出现的耦合模m=4、5和独立模m=5,给出了用扰动幅度的极向截面图分析磁扰动模式的结果,讨论了相关分析法在实验分析中的优点和局限性。