HL-2A 装置超声分子束注入缓解偏滤器靶板上边缘局域模热通量研究

在HL-2A 装置上优化和发展了偏滤器靶板上的红外测温系统,并利用该系统分析了高约束模放电期间边缘局域模的热沉积分布特性。在高约束模式放电期间,超声分子束注入使边缘局域模所引起的偏滤器靶板上瞬间热通量峰值下降了~60%,并伴随着边缘局域模爆发频率增加了2~3 倍,而等离子体储能仅下降了~8%。分析结果表明,大幅度的丝状结构在超声分子束注入之后得到了有效抑制,沉积到偏滤器靶板上的瞬间热通量峰值也随之下降。此外,在超声分子束注入之后偏滤器室内的热辐射损失大幅度增加,从而耗散了热输运所携带的部分能量,进一步分散了沉积到偏滤器靶板上的能量,有效地保护了偏滤器靶板。     

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在HL-2A 装置上优化和发展了偏滤器靶板上的红外测温系统,并利用该系统分析了高约束模放电期间边缘局域模的热沉积分布特性。在高约束模式放电期间,超声分子束注入使边缘局域模所引起的偏滤器靶板上瞬间热通量峰值下降了~60%,并伴随着边缘局域模爆发频率增加了2~3 倍,而等离子体储能仅下降了~8%。分析结果表明,大幅度的丝状结构在超声分子束注入之后得到了有效抑制,沉积到偏滤器靶板上的瞬间热通量峰值也随之下降。此外,在超声分子束注入之后偏滤器室内的热辐射损失大幅度增加,从而耗散了热输运所携带的部分能量,进一步分散了沉积到偏滤器靶板上的能量,有效地保护了偏滤器靶板。     

Collisional gyrokinetic full-f particle-in-cell simulations on open field lines with PICLS

Applying gyrokinetic simulations in theoretical turbulence and transport studies for the plasma edge and scrape-off layer (SOL) presents significant challenges. To particularly account for steep density and temperature gradients in the SOL, the “full-f” code PICLS was developed. PICLS is a gyrokinetic particle-in-cell (PIC) code, is based on an electrostatic model with a linearized field equation, and uses kinetic electrons. In previously published results, we applied PICLS to the well-studied 1D parallel transport problem during an edge-localized mode (ELM) in the SOL without collisions. As an extension to this collision-less case and in preparation for 3D simulations, in this work, a collisional model will be introduced. The implemented Lenard–Bernstein collision operator and its Langevin discretization will be shown. Conservation properties of the collision operator, as well as a comparison of the collisional and non-collisional case, will be discussed.     

改善ITER 弹丸注入芯部加料的研究

研究了五种不同组合的固态氢同位素靶丸H₂、HD、D₂、DT 和T₂ 在聚变等离子体中的消融率。结果表明, 燃料靶丸的同位素效应, 可导致更深的靶丸消融物质沉积。在同样的本底等离子体条件和弹丸初始参数下, 注入氚丸比氢丸的穿透深度增加约40%。适度减轻一些ITER 的加料困难。进一步的研究表明从中平面高场侧注入靶丸对芯部加料有显著改善。考虑托卡马克非均匀磁场的影响, 被电离的消融云内的垂直漂移电流产生极化, 引起带电消融物沿大半径方向朝外漂移。数值模拟计算表明, 只要用初始速度为每秒几百米的低速弹丸, 便能使靶丸的消融物质沉积到ITER 等离子体中心。     

The observation of field-aligned current during type-III ELM in EAST

Measurements of current-carrying filaments associated with Type-III edge localized mode (ELM) have recently been made in the Experimental Advanced Superconducting Tokamak by direct probing of the edge plasma using an advanced, fast-moving electrostatic and magnetic probe system. Contrary to expectations, no current filaments were detected near the separatrix. However, a clear signature of current filament has been observed in the far scrape-off layer (SOL) where the difference of the voltage between the divertor plates connecting a filament is sufficiently large, thus strongly suggesting that the current-carrying filaments form in the SOL, rather than being ejected from the plasma inside the separatrix. These findings provide, for the first time, information on the formation and sustainment of current filaments during type-III ELMy H-modes.     

Local 3D perturbation experiments for probing the ELM stability

Empirical estimates indicate that the transient divertor power load induced by type-I ELMs in the standard H-mode ITER scenario might result in intolerably short target life times. Significant experimental effort has been put on the exploration of recipes to avoid or at least mitigate the ELM size by external intervention. Experimental ELM mitigation studies (and related modeling) are of interest from different points of views. First, the active intervention gives access to new, externally controlled ELMy discharge scenarios and ELM diagnostic techniques. Second, the ELM response on the type and amplitude of the applied perturbation provides additional hints on the ELM stability. Third, mitigated ELMs, possibly different from spontaneous ones, and their scaling are of interest ‘per se’, in case that mitigation is to be finally applied in ITER. In this contribution we report on ELM mitigation results in ASDEX Upgrade, where we further restrict the scope to those methods involving 3D, local non-axisymmetric perturbations. Perturbations applied were cryogenic pellet injection, localized supersonic pulsed injection of D gas and laser blow of from targets carrying C or Al micro pellets. The corresponding perturbations differ strongly both in the space and time domain and provide an instrument to probe the local stability. Varying the parameters of the external perturbations by e.g. changing the amount of injected material or the injection speed we mapped out the ELM trigger threshold with high spatial and temporal resolutions. Presented at the Workshop “Electric Fields, Structures and Relaxation in Edge Plasmas”, Tarragona, Spain, July 3–4, 2005.     

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建立了计算托卡马克加料中弹丸消融的物理模型,结合1维输运模型编制了1.5维弹丸消融计算机模拟代码。使用ITER-FEAT的相关参数,对半径为6mm,初速度为2000m·s?1,从低磁场侧注入弹丸的消融速率进行了模拟计算。结果显示,弹丸消融速率先随注入深度而逐渐增大,最大消融速率约6×1026s?1,然后由于弹丸半径的减小,消融速率迅速减小,穿透深度约0.45m。这一结果与中性气体屏蔽模型(NGS)的结果一致,证明计算代码正确有效。同时,从计算结果反映出,对ITER这样的堆级托卡马克,采用常规弹丸注入方式,尽管速度高达2000m·s?1,穿透深度也远未达到等离子体中心,因此应采取其他有效措施来提高等离子体加料效率。     

弹丸消融速率的理论模型及数值计算

建立了计算托卡马克加料中弹丸消融的物理模型,结合1维输运模型编制了1.5维弹丸消融计算机模拟代码。使用ITER-FEAT的相关参数,对半径为6mm,初速度为2000m•s^-1,从低磁场侧注入弹丸的消融速率进行了模拟计算。结果显示,弹丸消融速率先随注入深度而逐渐增大,最大消融速率约6×10²⁶s^-1,然后由于弹丸半径的减小,消融速率迅速减小,穿透深度约0.45m。这一结果与中性气体屏蔽模型(NGS)的结果一致,证明计算代码正确有效。同时,从计算结果反映出,对ITER这样的堆级托卡马克,采用常规弹丸注入方式,尽管速度高达2000m•s^-1,穿透深度也远未达到等离子体中心,因此应采取其他有效措施来提高等离子体加料效率。     

High-density operation in tokamaks

Conclusion  In this paper we have examined various aspects regarding high-density operation in tokamaks and in particular the density limit, the plasma detachment, the MARFE formation and the fuelling efficiency. As regarding the density limit, both experimental findings and theoretical model indicate that the plasma current and the total input power are relevant in limiting the edge density that can be sustained in a tokamak discharge: radiation losses and SOL momentum and energy conservation are the underlying mechanisms. In the latest divertor experiments, operating in the detached regime, the influence of the input power seems to vanish or even disappear. Edge phenomena such as plasma detachment, occurring beyond a density threshold that can be lowered by means of impurity injection, can lead to the almost complete exhausting of the heating power by radiation which is greatly helpful for the design of the divertor plates. The compatibility of H-mode operation with this regime is still under investigation. The MARFE phenomenon, sometimes precursor of a major disruption, is now understood in terms of a radiation induced thermal instability. Finally, experiments performed in order to investigate the fuelling efficiency of the gas puffing technique have shown that at high density this technique becomes rather inefficient, thus indicating that pellet injection still remains an essential requirement to fuel the reactor plasma. The drop of the fuelling efficiency of gas-puffing at high density can be accounted for by collision phenomena taking place in the SOL.     

EAST中加热功率对弹丸注入加料效率的影响

介绍了 EAST 装置气动加速氘弹丸注入加料系统和不同加热功率条件下弹丸加料效率的实验结果。 当等离子体加热功率从 1MW 逐渐增加到 10MW 时,弹丸加料效率从 60%降低到 10%。加热功率的升高导致弹 丸粒子的沉积深度 λp/a 降低达 50%左右,从而导致大量的弹丸粒子沉积在等离子体边界。     

MHD plasma physics in rail accelerators for hydrogen-pelletinjection in fusion reactors

The behavior of the electromagnetic and thermal quantities in a plasma arc placed between two conducting rails is analyzed. The plasma hydrogen drives the hydrogen pellets for the refueling of magnetic fusion reactors. Considering the general equations of electromagnetism and of plasma fluid dynamics and assuming steady-state conditions in a frame which is moving at the same rate as the plasma arc armature, a one-dimensional model is deduced. The effects of an applied magnetic field on the behavior of all flow variables are investigated. Results indicate that the adverse effects of plasma arc heating can be reduced by the application of a magnetic-induction field normal to the current path in the armature. At the maximum acceleration pressure (30 bar) applicable to the hydrogen pellet in the proposed one-dimensional model, the arc temperature at the pellet backend falls from 20000 to 14000 K when a magnetic induction of about 5 T is applied     

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     

Modeling of Large ELM Suppressions for High Confinement Plasma in D Ⅲ-D

The H-mode discharges with high edge pressure gradients are expected for the economic feasibility of future fusion reactors. However, the high edge pressure gradients easily produce ELM instability , which generally can expel large, heat and particle loading to the divertor targets. These ELMs limit the core plasma performance and reduce the lifetime of divertor target plates. The transports of heat and particles outward across plasma boundary are useful to control density and impurity profiles for achieving steady state, high performance plasmas. Consequently, any technique to eliminate or mitigate large fast ELM impulses must replace the transient heat and particle transports with another slow process. Such a technique is high priority for a burning plasma device such as ITER.     

Investigations of the spatio-temporal build-up of atomic oxygen inside the micro-scaled atmospheric pressure plasma jet

The ascent of atomic oxygen densities created inside the micro-scaled atmospheric pressure plasma jet has been investigated spatially resolved under parameter variations such as applied power, gas mixture and gas velocity using two-photon absorption laser induced fluorescence spectroscopy. Along the discharge channel an increase of the atomic oxygen density within the plasma is observed. The density shows an exponentially asymptotic convergence into an equilibrium close to the effluent. In the post-discharge effluent an exponential spatial decrease can be found. Typical ascent distances of a few hundreds of μm decrease with the applied power and increase with gas velocity and oxygen admixture. The maximum atomic oxygen density increases with applied power and admixed molecular oxygen up to more than 10¹⁶ cm^-3. An increase of the maximum atomic oxygen density with increasing gas velocity has been found. Optical emission spectroscopy measurements indicate a strong increase of the nitrogen emission at low gas flow rates along the channel.     

HL-2A装置偏滤器位形超声分子束注入深度观测

用22道Hα辐射测量阵列观测了HL-2A装置偏滤器位形超声分子束的注入过程。观测结果表明：在HL-2A装置偏滤器位形下,当分子束注入气源压强大于1MPa时,Hα辐射沿径向分布存在两个峰值,其第二个Ha辐射峰值位于r/a~0.8附近,表明大部分氢粒子在等离子体边缘(SOL区域)即被离解或电离,但仍有部分氢粒子沉积在分界面内5cm。     

HL-2A充气弹丸注入初步实验结果

介绍了充气夹心弹丸的基本结构、制作工艺和充气弹丸注入器的基本构成以及在HL-2A等离子体中注入的初步实验结果。实验中采用以聚苯乙烯为主的空心微球为载体，直径~0.76mm，壳体厚度~20μm，充满~1.5MPa的氘气的充气弹丸。实验结果表明，充气弹丸注入速度~200m•s^-1，注入深度~12cm，加料效率~60%。     

偏滤器运行模式对托卡马克边缘区等离子体平行流的影响

我们使用一维流体模型,根据在不同偏滤器运行模式下静压强沿着磁力线方向的分布变化,讨论了偏滤器运行模式对托卡马克边缘区等离子体平行流的影响.低再循环模式下,静压强从X点 (X-point)附近的刮削层区域开始明显下降,变化趋势与密度变化趋势一致;等离子体平行流的马赫数在偏滤器区域逐步变大,变化从平缓到迅速.高再循环模式下,静压强在靶板附近的区域迅速下降,在其他区域变化非常小;等离子体平行流的马赫数仅在靠近靶板附近的区域迅速变大,在其他区域变化平缓.在弱脱靶模式下的静压强变化与高再循环模式下类似,不过静压强在X-point附近的刮削层区域开始出现下降的趋势,导致等离子体平行流的马赫数在X-point处的值比在高再循环模式下大.强脱靶模式下,静压强在刮削层区域开始明显下降,在远离靶板的偏滤器区域,静压强迅速下降的地方,观察到高马赫数等离子体平行流.静压强迅速下降引起动压强迅速上升来维持总的压强守恒是在强脱靶状态 下产生高马赫数平行流的一种可能驱动机理.     

Explosion model applied to an intense pulsed plasma source for thinfilm deposition

A pulsed plasma source for deposition of thin polymer films was modeled numerically with the one-dimensional (1-D) time dependent fluid transport equations describing an explosion for an ideal gas. Initial number density, explosion temperature, and velocity were made consistent with values in an experimental reactor. These quantities as well as pressure and fluence were modeled for a distance of 2 m and for a time duration of 93 μs. The trajectory for maximum pressure calculated from the model was observed to be consistent with the experimentally measured trajectory of maximum emitted light from an acetylene plasma. Measured axial profiles of areal density for the deposited polymer films were compared with modeled fluence     

HL-1M装置高气压超声分子束加料效果

超声分子束注入作为一种新的托卡马克加料方法,已成功地开发和应用于环流器新一号(HL1M)和超导托卡马克HT7.近期开展的高气压超声分子束注入实验,在束流中发现了团簇流,其注入等离子体深度超过17cm.电子密度上升率接近于小型冰弹丸加料.多脉冲超声分子束注入形成电子密度阶梯形上升,类似于多弹丸加料效果,电子温度剖面呈中空分布.描述了在HL1M装置同一次欧姆放电等离子体中超声分子束与冰弹丸加料效果的实验比较. 关键词： 超声分子束 托卡马克 团簇 加料