微小等离子体反应器的导出机理研究

An extraction mechanism based on micronozzle in the bottom of the microhollow cathode and applied bias electrical field is proposed, and digitally simulated with a two dimensional fluid model. When the operating gas is SF₆ and its pressure is 2~9kPa, radius of the micronozzle is 0.25μm, maximum F atom flux density is between (1.53~5.62)×10¹⁴cm^-3·s^-1, maximum SF₅⁺ flux density is between (2.46~7.83)×10¹⁶cm^-3·s^-1. When gas pressur is  5kPa,average energy of F atom at sample surface is 3.82eV, dispersion angle is −14º~14º; average energy of SF is 25eV, dispersion angle is −13º~14º. When applied voltage across hollow cathode and sample is between 10~50V (sample as cathode), average energy of SF is between 52~58eV. The density of F and SF in the simulation result could satisfy the requirement for silicon etching, and the feasibility of scanning plasma etching validated.     

HL-2A装置ECRH系统的新天线设计

Using the principle of quasi-optic, the new antenna of the electron cyclotron resonant heating(ECRH) system on the tokamak HL-2A has been designed. After being focused by the elliptical mirror and reflected by the plane mirror, 4 68GHz/500kW/1s electron cyclotron wave beams would be injected into the tokamak from one Æ350mm port to accomplish heating to the plasma. Based on the propagating theory of the fundamental Gaussian beam, it is gotten that at the centre of the cross section of the tokamak, the power density of each beam is 158MW•m^-2, and the power density radius, which means that the power density is reduced by a factor 1/e² compared to the power density at the centre of the beam, is 31.7mm. On the mirror, due to the focusing and reflecting, the ohmic loss and diffraction loss of the microwave beams are 0.27% and 0.64%, respectively. By the finite element analysis software ANSYS, some thermal analysis of the mirror have been done. The result shows that the highest temperature increase would be only 0.47℃ under 1s pulse load, so there is no need of any cooling.     

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采用本征模式的数值打靶方法研究了离散阿尔芬本征模在DⅢ-D高性能运行条件下的物理特性,包括负磁剪切位形、高性能加热、正反中性束注入、内部输运垒以及高自举电流和甚高约束运行状态对这种阿尔芬模式的影响。在DⅢ-D托卡马克装置负磁剪切位形及先进运行状态实验参数下这些离散阿尔芬本征模存在于宽的径向区域,且具有广泛的本征频谱;高性能加热、同向中性束注入以及内部输运垒的存在有利于产生多个较深的气球模驱动势阱,由之得以很好地形成这种阿尔芬束缚态本征模;在高自举电流和甚高约束运行条件下这些离散阿尔芬本征模束缚态能够在更广的径向区域存在,且可具有较高的本征频率。另外,参照DⅢ-D装置放电实验数据的时间演变情况,这些离散阿尔芬本征模能在很宽的运行参数范围内出现,使之成为该类大型托卡马克实验中可能广泛存在的潜在不稳定性。     

HL-2A装置SDD软X射线能谱测量结果

Measurements of soft X-ray spectra during Electron Cyclotron Resonance Heating (ECRH) has been achieved on HL-2A tokamak using two independent silicon drift detector (SDD) systems. Electron temperatures are derived from the measured soft X-ray energy spectra. A comparison indicates that the results measured by SDD are consistent with ECE measurements. Experimental results of soft X-ray spectra measure- ment using SDD show that the increment of electron temperature is larger at z=0 than that at z = 16.4cm chord, so, we can conclude that the energy of ECW is deposited dominantly in the core of plasma and electron temperature profile become peaked during on-axis ECRH (B_T=2.4T). The statistic survey of ECRH discharges (2.41T ≤B_T≤2.43T,1.5×10¹⁹m^-3≤n_e≤2.5≤10¹⁹m^-3,300kW≤ECRH power≤600kW) shows that plasma electron temperature rises obviously during on-axis ECRH, especially, in the core of plasma (z=0). It has been observed that the on-axis ECRH can make electron temperature increase up to 30%～80% at z=0 chord and 15%～55% at z=-16.4cm chord.     

EAST中快离子Dα诊断光电检测系统的设计

设计了具有高时间和空间分辨率EAST 快离子D_α 的光电检测系统,它由16 路光电倍增管(PMT)和电流放大器(采用蓝宝石材料代替传统印刷板电路)构成。为了使快离子D_α (FIDA)信号在中性束注入时能从其他光源的在同一光谱范围内的谱线中检测出来,系统参数设计为整体光子-电压增益5.0×10⁹、电流放大器增益10⁶V/A、-3dB 带宽500kHz。实验结果表明,该光电检测系统可以很好的检测到快离子D_α (FIDA)信号,并有助于从D_α 光的多普勒偏移光谱推断快离子特性。     

HL-2A装置高βN双输运垒实验的集成分析

HL-2A托卡马克装置在中性束加热条件下获得了稳定的归一化环向比压(β_N)大于2.5的等离子体,并且实现了瞬态β_N=3.05、归一化密度(n_e,1/n_e,G)～0.6、储能(W_E)～46 kJ和高约束因子(H₉₈)～1.65的高约束性能.本文使用集成模拟平台OMFIT对βN=2.83和βN=3.05时刻的等离子体进行了集成模拟,计算得到的W_E,n_e,1/n_e,G,H₉₈和β_N等与实验参数基本一致,并通过计算发现两种情况下自举电流份额(f_BS)分别约达到45%和46%.此外,还进一步分析了HL-2A装置形成离子温度内部输运垒(ITB)的原因:快离子和E×B剪切流使得芯部湍流输运被抑制,改善了约束,从而形成了离子温度ITB.离子温度的ITB与H模边缘输运垒相互协同形成了高β_N的等离子体.     

激光核聚变

从五十年代以来世界各国一直按传统法进行聚变研究,设计建造了若干装置,总体上来看,进展是缓慢的,其原因是:要在远低于热核温度的情况下,使等离子体通过强大电流进行电阻加热达到点火温度是十分困难的,因为随着温度的增高,电阻将随之下降,影响温度进一步提高;另外还有约束、稳定等问题.尽管后来又发展了有效的绝热压缩和中性束注入等加热技术。但迄今仍离点火的劳森条件(离子密度和约束时间的乘积。n～1014/厘米3·秒)有两个数量级之差. 一九六八年以来国外相继报导了激光引起氘化物聚变反应放出中子的实验,一九七二年提出了激光向心爆炸理…     

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应用准光学原理设计了HL-2A装置电子回旋共振加热(ECRH)系统新的集束天线,该天线能使4束68GHz/500kW/1s电子回旋波通过椭球镜聚焦和平面镜的反射,从一个直径350mm装置窗口同时注入托卡马克,对等离子体实现加热。根据基模高斯束的传播原理得出,在装置环向横截面中心处单条波束的功率密度为158MW•m-2,功率密度降为中心密度的1/e2的半径为31.7mm,微波束经过镜面聚焦和反射产生的欧姆损失和衍射损失分别为0.27%和0.64%。利用有限元分析软件Ansys对镜面进行热分析得到,在1s脉冲载荷下最大镜面温升仅为0.47℃,镜面可以自然冷却。     

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应用半解析方法,研究了直圆柱位形下等离子体压强P0分别为P0=0、P0=常数和P0=f(r)时Line-tied扭曲不稳定性的增长率和二维径向本征函数的演化规律。结果表明,P0=0和P0=常数时的轴向波数k的范围相同,但P0=常数时的增长率比P0=0时的小。P0=f(r)时的轴向波数k的范围和增长率则都比P0=0时的大,同时磁流体的速度变化也较大。因此,P0=f(r)更接近实际的物理模型(例如日冕的喷射问题)。     

Pioneering experiments on atomic-beam-assisted generation of drag currents in the Globus-M spherical tokamak

Research data for drag currents in the Globus-M spherical tokamak are presented. The currents are generated by injecting atomic beams of hydrogen and deuterium. Experiments were carried out in the hydrogen and deuterium plasma of the tokamak. It has a divertor configuration with a lower X-point, a displacement along the larger radius from–1.0 to–2.5 cm, and a toroidal field of 0.4 T at a plasma current of 0.17–0.23 MA. The beam is injected into the tokamak in the equatorial plane tangentially to the magnetic axis of the plasma filament with an impact diameter of 32 cm. To provide a 28-keV 0.5-MW atomic beam with geometrical sizes of 4 × 20 cm (at a power level of 1/e), an IPM-2 ion source is used. The generation of noninductive currents is detected from a rise in the loop current and a simultaneous dip of the loop voltage. The injection of the hydrogen and deuterium atomic beams into the deuterium plasma results in a noticeable and reproducible dip of the loop voltage (up to 0.5 V). Using the ASTRA transport code, a model is constructed that allows rapid calculation of noninductive currents. Calculations performed for a specific discharge confirm that the model adequately describes the effect of drag current generation.     

Quasisteady high-confinement reversed shear plasma with large bootstrap current fraction under full noninductive current drive condition in JT-60U

A quasisteady reversed shear plasma with a large bootstrap current fraction ( approximately 80%) has been obtained for the first time in the JT-60U tokamak. The shrinkage of reversed shear region was suppressed by the bootstrap current peaked at the internal transport barrier (ITB) layer and the ITBs at a large radius were sustained, which, by combination with an H-mode edge pedestal, resulted in a high confinement or 2.2 times the H-mode scaling for 6 times energy confinement time or 2.7 s. Furthermore, a full noninductive current drive was obtained by the bootstrap current and the beam driven current.     

Calculation of the Electron Efficiency for a Two-Cavity Gyroklystron Amplifier by Using a Self-Consistent Code

The beam-wave interaction in a Ka-band, two-cavity fundamental gyroklystron amplifier is studied by using a self-consistent nonlinear simulation code. The electron efficiency for this gyroklystron amplifier is calculated, and the effect of various parameters, such as beam voltage, beam current, electron guiding center radius, velocity pitch ratio and drift tube length on the electron efficiency is discussed in detail.     

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.     

Modeling of beam ions loss and slowing down with Coulomb collisions in EAST

This paper uses the implicit Monte-Carlo full-orbit-following parallel program ISSDE to calculate the prompt loss and slowing down process of neutral beam injection (NBI)-generated fast ions due to Coulomb collisions in the equilibrium configuration of Experimental Advanced Superconducting Tokamak (EAST). This program is based on the weak equivalence of the Fokker-Planck equation under Rosenbluth MacDonald Judd (RMJ) potential and Stratonovich stochastic differential equation (SDE). The prompt loss with the LCFS boundary and the first wall (FW) boundary of the two co-current neutral injection beams are studied. Simulation results indicate that the loss behavior of fast ions using the FW boundary is very different from that of the LCFS boundary, especially for fast ions with a large gyration radius. According to our calculations, about 5.11% of fast ions generated by perpendicular injection drift out of the LCFS and then return inside the LCFS to be captured by the magnetic field. The prompt loss ratio of fast ions and the ratio of orbital types depend on the initial distribution of fast ions in the P_ζ-$\varLambda$ space. Under the effect of Coulomb collisions, the pitch-angle scattering and stochastic diffusion happens, which will cause more fast ion loss. For short time scales, among the particles lost due to collisions, the fraction of banana ions reaches 92.31% in the perpendicular beam and 58.65% in the tangential beam when the fraction of banana ions in the tangential beam is 3.4% of the total ions, which means that the effect of Coulomb collisions on banana fast ions is more significant. For long time scales, the additional fast ion loss caused by Coulomb collisions of tangential and perpendicular beams accounted for 16.21% and 25.05% of the total particles, respectively. We have also investigated the slowing down process of NBI fast ions.     

Wobbling phonon excitations in strongly deformed triaxial nuclei

The wobbling mode is uniquely related to triaxiality and introduces a series of bands with increasing wobbling phonon number, . The pattern of -transitions between the wobbling excitations will be influenced by the presence of an aligned particle. Evidence for the wobbling mode was obtained recently, and even a two-phonon wobbling excitation has now been identified in ¹⁶³Lu. The similarity of the data in ¹⁶³Lu to new strongly deformed triaxial bands and connecting transitions in the neighbouring nuclei, ¹⁶⁵Lu and ¹⁶⁷Lu, establishes wobbling as a more general phenomenon in this region. The higher phonon wobbling excitations show some anharmonicity, but the characteristic large E2 strength is observed. The wobbling interpretation is based on the comparison of electromagnetic decay strength between bands to particle-rotor calculations in which an i_13/2 proton is coupled to a triaxial core.Received: 30 October 2002, Published online: 23 March 2004PACS: 27.70. + q - 23.20.-g Electromagnetic transitions - 21.10.Re Collective levels     

8 mm二次谐波回旋速调管放大器双阳极磁控注入电子枪的设计

 计算了8 mm二次谐波回旋速调管双阳极电子枪的设计参数，根据这些参数，采用EGUN软件进行模拟和优化，设计出了一只双阳极磁控注入电子枪，该枪的电子束纵横速度比为1.45，速度零散为5.4%，并讨论了电极形状、磁场分布、电流、控制极电压和第二阳极电压对电子注性能的影响，结果发现电子注对这些影响因子非常敏感，设计中应对它们进行充分优化。