HL—1托卡马克杂质注入实验及杂质输运特性的研究

本文给出了ＨＬ－１托卡马克在通常欧姆放电和偏压诱发Ｈ模放电条件下，脉冲注入杂质气体的实验结果以及对杂质在通常欧姆等离子体和偏压诱发Ｈ模等离子体中的输运研究结果。     

低混杂波电流驱动下注入杂质的输运

在欧姆放电和低混杂波电流驱动条件下,应用激光吹气技术注入金属杂质,用真空紫外谱仪测量了杂质线的辐射,给出了ＨＬ－１Ｍ 装置欧姆等离子体和低混杂波电流驱动等离子体杂质输运的研究结果。用杂质输运程序ＬＢＯ进行数值模拟,得出了等离子体中杂质的扩散系数Ｄ（ｒ） 和对流速度ｖ（ｒ）。在低混杂波电流驱动条件下,等离子体杂质的输运系数相对欧姆放电等离子体杂质的输运系数减小了５０％ 左右。结果表明,在ＨＬ－１Ｍ 装置上低混杂波电流驱动等离子体相对通常欧姆等离子体杂质的约束性能明显得到了改善     

HL－1托卡马克杂质注入实验及杂质输运特性的研究

本文给出了ＨＬ－１托卡马克在通常欧姆放电和偏压诱发Ｈ模放电条件下，脉冲注入杂质气体的实验结果以及对杂质在通常欧姆等离子体和偏压诱发Ｈ模等离子体中的输运研究结果。实验结果表明，在ＨＬ－１上偏压诱发Ｈ模等离子体中对杂质的约束性能明显优于在通常欧姆等离子体中对杂质的约束性能。杂质输运的数值模拟结果说明，无论在通常欧姆等离子体中，还是在偏压诱发Ｈ模等离子体中，杂质的输运系数都比新经典理论预计的要大得多，输运是反常的。在偏压诱发的Ｈ模等离子体中引入杂质输运“位阱”概念，能够对杂质离子约束时间长的实验现象进行很好的描述。合理地解释了在偏压杂质注入实验中杂质辐射上升时间长、衰减慢的现象。     

靶材料杂质影响新谱线产生的实验验证

 为了验证氢气放电源打靶产生的新谱线不是靶杂质的特征谱线,完成了5项检验实验。其中屏蔽实验和强电子辐照靶的实验证实了新谱线不是来自放电室中的杂质形成的;靶的打磨实验表明靶表面的污染杂质也不能产生新谱线,形成共振峰的实验和新谱线强度随放电电压变化规律的实验结果都证明靶的总杂质不影响新谱线的测量。     

EAST超导托卡马克装置真空室壁处理的研究

壁处理技术被广泛应用于托卡马克装置上,以降低装置本底杂质水平,改善器壁的再循环.自2008年起,EAST面向等离子体的第一壁采用全碳材料,由于特殊的石墨晶体多孔结构,具有高放气率以及对H₂O,H₂等杂质气体的高吸附性,从而使等离子体放电前期的装置真空室壁处理尤为关键.本文介绍了EAST装置真空室壁处理的实验系统,并研究了装置烘烤与不同工作气体及工作参数下的直流辉光放电清洗对杂质粒子的清除效果.实验结果表明:EAST装置真空室在经过长时问的前期壁处理后,显著地降低了真空室内壁的出气率与本底杂质浓度,这对随后进行的等离子体放电实验非常有必要.     

HL-1装置放电杂质的时间行为

HL-1装置放电期间,用SZ-001遥控四极质谱计观察到器壁的主要气体杂质是CH_4,CO,CO_2和H_2O,其时间行为呈多峰形;它们以不同暂态时间为其特征;其分压随等离子体电流的增大和孔栏半径的减小而增加,二次脉冲送气下尤其明显:其中CO主要产生在等离子体存在期,CH_4主要产生在放电熄灭期;连续送气下,送气侧与非送气侧杂质时间行为大约相差一个等离子体存在时间;连续用30000次Taylor法放电清洗后,仍观察到不锈钢活动孔栏上C,O杂质较多。     

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     

HL-1装置等离子体可见光谱实验

本文给出了HL-1装置等离子体光谱杂质分析,测量了清洗放电时电子温度随环电流的变化关系,根据积分光谱估计了放电时等离子体的离子温度,得到了放电时CV2270.91A线的马鞍形波形。     

杂质元素特征X射线对氢气放电源打靶新谱线的影响

 在氢气放电源打靶的实验中,测到了系列能量恒定不变的低能X射线新谱线,这些新谱线的能量分别为(1.70±0.10) keV, (2.25±0.07) keV,(2.56±0.08) keV,(3.25±0.10) keV和（3.62±0.11） keV,与Si,Ta,S,Cl,K和Ca等元素的特征X射线能量相近,但靶中所含的杂质或来自放电室的杂质元素可能会产生这些能量的X射线谱峰,证实新谱线是否由这些元素的特征X射线干扰所致显得尤为重要。分析了本实验系统中各种杂质的可能来源,论证了放电室端杂质对新谱线的影响,及靶材料中体杂质和面杂质对新谱线的影响;用X射线光电子能谱仪对靶做了表面分析。研究结果表明：杂质元素的特征X射线不会对氢气放电源打靶产生的新谱线有影响。这些新谱线的性质有待进一步的实验研究。     

HL—1装置电流上升段辐射与杂质特性

托卡马克等离子体中的杂质会影响托卡马克的放电品质及等离子体特性。许多理论和实验对杂质的产生和输运做了深入详细的研究。等离子体电流起始阶段,由于约束性能不好,会引起大量的杂质产生,辐射损失增大是杂质增加引起的直接后果。杂质辐射是等离子体辐射的主要组成部分之一,等离子体线辐射功率～Z_(eff)~6,复合辐射功率～Z_(eff)~4,轫致辐     

Radiative energy exhaust by sputtered and seeded impurities in fusion reactor

The combine effect of the seeded and sputtered impurities on the power load to the divertor plate and operation of fusion reactor is investigated in the paper. Since the energy balance depends strongly on coupling between core and scrape of layer (SOL) regions the modelling requires solving the transport problem in both region with the coupling took into account. The energy and particle transport is analyzed numerically with the help of COREDIV code treating self-consistently both regions. In COREDIV the radial 1D energy and particle transport of core plasma is coupled to 2D model of the SOL. The two types of transport model have been used: described by local transport coefficients proposed by Mandrekas and Stacey and transport model proposed by Tokar and determined by several types of drift instabilities. The 2D model is based on Braginskij-like equations for densities and velocity components parallel to magnetic fields and electron and ion temperatures (it was assumed that all ions has the same temperature). The steady states of ITER-FEAT reactor have been studied numerically. Several wall and plates materials and Argon as seeded impurities has been considered. The numerical results show that the effect of seeded impurity radiation is strongly mitigated by decreasing of sputtered impurity density and its radiation due to lower energy flowing to the SOL.     

HT-6M托卡马克装置杂质输运

利用多道可见光谱探测系统和近紫外转镜系统测量了HT-6M托卡马克等离子体中杂质的时空分布.建立完备的杂质输运程序，数值模拟碳、氧杂质在欧姆放电时的输运行为，得出了杂质的扩散和对流系数、不同电离态杂质离子密度、辐射功率密度和有效电荷数的空间分布. 分析低混杂波电流驱动（LHCD）期间杂质行为，结果表明等离子体粒子约束、杂质约束和能 量约束提高，辐射功率和有效电荷数减小. 关键词： 托卡马克 杂质输运 扩散系数 对流系数     

The carbon impurity ohmic discharges on particle transport in the HT-7 tokamak

The line-integrated optical measurement of impurity radiation profiles for the study of light impurity transport is performed in the HT-7 tokamak. The carbon impurity line emissivity is obtained by Abel inversion. The radial transport behaviours of carbon impurities at different central line averaged electron densities ne are investigated in ohmic discharges. The diffusion coefficient Dk（r）, the convection velocity Wk（r） and the total flux of the impurity ions Fk decrease with the increase of ne, which shows a reduction in the impurity particle transport at higher electron densities.     

Density inhomogeneity driven percolation metal-insulator transition and dimensional crossover in graphene nanoribbons

Transport in graphene nanoribbons with an energy gap in the spectrum is considered in the presence of random charged impurity centers. At low carrier density, we predict and establish that the system exhibits a density inhomogeneity driven two dimensional metal-insulator transition that is in the percolation universality class. For very narrow graphene nanoribbons (with widths smaller than the disorder induced length scale), we predict that there should be a dimensional crossover to the 1D percolation universality class with observable signatures in the transport gap. In addition, there should be a crossover to the Boltzmann transport regime at high carrier densities. The measured conductivity exponent and the critical density are consistent with this percolation transition scenario.     

Full-torus impurity transport simulation for optimizing plasma discharge operation using a multi-species impurity powder dropper in the large helical device

The transport of impurities supplied by a multi-species impurity powder dropper (IPD) in the large helical device (LHD) is investigated using a three-dimensional peripheral plasma fluid code (EMC3-EIRENE) coupled with a dust transport simulation code (DUSTT). The trajectories of impurity powder particles (Boron, Carbon, Iron, and Tungsten) dropped from the IPD and the impurity transport in the peripheral plasma are studied in a full-torus geometry. The simulation reveals an appropriate size of the impurity powder particles and an optimum operational range of the dust drop rates for investigating the impurity transport without inducing radiation collapse. The simulation also predicts a favourable plasma discharge condition for wall conditioning (boronization) using the IPD in order to deposit boron to high plasma flux and neutral particle density areas in the divertor region in the inboard side of the torus.     

Radial transport dynamics studies of SMBI with a newly developed TPSMBI code

In tokamak plasma fueling, supersonic molecule beam injection(SMBI) with a higher fueling efficiency and a deeper penetration depth than the traditional gas puffing method has been developed and widely applied to many tokamak devices.It is crucial to study the transport dynamics of SMBI to improve its fueling efficiency, especially in the high confinement regime. A new one-dimensional(1D) code of TPSMBI has also been developed recently based on a six-field SMBI model in cylindrical coordinate. It couples plasma density and heat radial transport equations together with neutral density transport equations for both molecules and atoms and momentum radial transport equations for molecules. The dominant particle collisional interactions between plasmas and neutrals, such as molecule dissociation, atom ionization and charge-exchange effects, are included in the model. The code is verified to be correct with analytical solutions and also benchmarked well with the trans-neut module of BOUT++ code. Time-dependent radial transport dynamics and mean profile evolution are studied during SMBI with the TPSMBI code in both slab and cylindrical coordinates. Along the SMBI path, plasma density increases due to particle fuelling, while plasma temperature decreases due to heat cooling. Being different from slab coordinate, the curvature effect leads to larger front densities of molecule and atom during SMBI in cylindrical coordinate simulation.     

共轭高聚物中低浓度掺杂下的杂质分布研究

基于紧束缚近似,研究了一维共轭高聚物链在链呈电中性,以及链中带有正、负电荷等不同情况下低浓度掺杂对系统稳定性的影响,并采用绝热近似下的自洽计算方法得出了系统在掺杂前后发生的总能量改变。研究发现,掺杂位置对系统稳定性的影响非常明显。根据杂质分布的特点,一条共轭高聚物链一般可分为链端区、中心区和过渡区三个明显不同的区域。系统的稳定性不仅受掺杂位置,杂质势的强度及性质影响,而且还受到高聚物链的载荷状态的影响。在链端区及过渡区,杂质分布趋向于凝聚成畴,而在中心区域,杂质趋于均匀分布。该研究表明,通过对掺杂条件的控制,可以有效控制杂质在共轭高聚物中的分布状态。     

Spectral densities from dynamic density-matrix renormalization

Dynamic density-matrix renormalization provides valuable numerical information on dynamic correlations by computing convolutions of the corresponding spectral densities. Here we discuss and illustrate how and to which extent such data can be deconvolved to retrieve the wanted spectral densities. We advocate a nonlinear deconvolution scheme which minimizes the bias in the ansatz for the spectral density. The procedure is illustrated for the line shape and width of the Kondo peak (low energy feature) and for the line shape of the Hubbard satellites (high energy feature) of the single impurity Anderson model. It is found that the Hubbard satellites are strongly asymmetric.     

1064 nm激光对中性密度滤光片的损伤机理研究

中性密度滤光片的典型结构是在K9玻璃上镀金属膜,来实现对激光的有效吸收.由于损伤阈值较低,严重限制了其在高能激光系统中的应用.实验研究了较高激光能量密度下滤光片的损伤形貌和损伤机理.损伤形貌的变化特征是:随着激光能量密度的增加,滤光片先出现损伤点,后以损伤点为中心产生裂纹,且裂纹长度逐渐变长,最终连接成线状和块状,导致大面积的薄膜脱落.建立了缺陷吸收激光能量升温致中性密度滤光片表面薄膜损伤的模型,计算了薄膜表面的温度和应力分布,讨论了薄膜表面不均匀温升造成的径向、环向和轴向热应力分布.理论分析显示:环向应力是造成薄膜沿径向产生裂纹的主要原因.当激光能量密度大于约2.2 J/cm²,杂质粒子半径大于140 nm且相邻杂质粒子之间的距离小于10 μ m时,裂纹才能大量连接起来引起薄膜的大面积脱落.     

Nichtgleichgewichtsdichten inhomogener Plasmen mit Photoabsorption

The electron and population densities in nonequilibrium plasmas are computed. For these computations rate equations dependent on geometrical dimensions were used. Such rate equations result if the unknown radiation intensity is eliminated. This is achived by using the radiative transport equation. Our density computations are valid for a quasi neutral plasma. The total pressure or the density of the heavy particles and the distribution of the electron energy have to be assumed. For homogeneous plasmas the inelastic collision processes and the radiation processes are considered. For inhomogeneous plasmas the diffusion processes of the excited atoms are considered in addition to the collision and radiation processes. Using this method of calculation the electron and population densities of a cesium plasma are computed. We assumed maxwellian distributions and a total pressure of 1 Torr.