HL-1M多脉冲分子束注入的CCD摄像

HL-1M装置实现了一种新的气体加料改善约束的方法——分子束注入(用多脉冲高速分子束注入加料)。多脉冲分子束注入加料可以控制等离子体密度分布、改善约束性能和提高密度极限。HL-1M托卡马克的多脉冲分子束注入得到了高的加料效率、改进了能量约束并维持了较高的密度峰化截面。分子束加料τ_E的改善和     

托卡马克超声分子束注入加料的进展

超声分子束注入作为一种新的托卡马克加料方法由作者在1992年首次提出并于当年在中国环流器一号(HL-1)装置演示成功,随后相继应用于中国环流器新一号(HL-1M)和中国科学院超导托卡马克HT-7装置。超声分子束注入等离子体呈现出电子密度峰化和温度中空分布的特征;等离子体流极向旋转速度提高,边缘扰动被抑制,等离子体能量约束得到改善。加料效率较常规脉冲送气提高一倍,而滞留器壁的粒子大为减少。近期开展的高气压氢超分子束注入实验,在束流中发现团簇流,可注入等离子体中心区域。多脉冲分子束注入形成电子密度的阶跃上升,如同冰弹丸注入效果。近年来该项技术已陆续应用于国外大型托卡马克和仿星器,是核聚变装置稳态运行的一种有效的加料方法。     

脉冲分子束注入HI-1M装置等离子体行为研究(英文)

介于已有的喷气(Gas puffing)和弹丸注入(Ice pellet injection)之间,提出了一种新的托卡马克加料手段—脉冲超声分子束注入。在较高的粒子注入通量5×10~(19)脉冲~(-1)时,氢分子的速度仍可达到500m/s。一系列氦分子束脉冲注入初始密度为(?)=0.4×10~(19)m~(-3)HL-1M真空室氢等离子体,经过160ms,密度上升至(?)=5.4×10~(19)m~(-3)。根据脉冲分子束注入初期氦光谱(HeⅠ587.6nm)强度的径向分布,1/3峰高位于r=12cm附近。注入后粒子约束时间增加5倍。由于气体粒子注入深化,电子密度峰化因子Q_n=n_e(0)/     

HL-1装置分子束注入实验研究

提出一种气体加料的新方法,采用高压氘气通过拉瓦尔喷嘴经一级分离器形成分子束注入HL-1装置等离子体,氘气体分子流量为3×10~(20)/s在线平均电子密度5.2×10~(19)m~(-3)时,粒子束速度可达到100m/s,随着等离子体密度和温度持续升高,粒子束通量很快衰减。当分子束注入结束并转为常规喷气加料时,D_α辐射强度急剧下降,与此同时,粒子对流沿径向朝等离子体芯部运动速度逐渐递增,电子密度分布继续峰化、电子密度持续上升达45ms。等离子体热能、粒子约束和能量约束时间均有所增加。分子束注入加料是一种定向的高效的加料手段,加料粒子可深入等离子体8cm,进入q≈2附近约束区。加料效率约为50％,壁表面粒子再循环率系数R≈0.6,低于常规喷气加料10％。     

分子束注入HL-1M装置等离子体的行为

一种新的气体加料方法——分子束注入,在HL-1M装置上进行了实验。脉冲高速分子束是由高压气体通过拉瓦尔(Laval)喷口形成的。准直的氢分子束平均速度约为500m·s~(-1)。一个分子束脉冲通过拉瓦尔喷口进入真空室的粒子数为6×10~(19)个。一系列氦分子束脉冲注入HL-1M低密度((?)=4×10~(18)m~(-3))氢等离子体,氦粒子穿透深度可达到12cm,电子密度上升率达到3.1×10~(-20)m~(-3)·s~(-1)而始终保持稳态,密度峰值为5.6×10~(19)m~(-3)。在氦分子束脉冲注入后100ms,电子密度剖面峰化因子达到最大值Q_n=n_e(O)/〈n_e〉=1.51,其中,n_e(O)为中心密度,〈n_e〉为体平均密度。由反磁测量得出能量约束时间τ_E为28ms,较在相同运行条件下常规喷气加料高30％。分子束加料τ_E的改善和Q_n值的增加可与HL-1M装置的小弹丸注入和ASDEX装置[Kaufmann M et al,Nucl.Fusion 28(1988)827]的低速弹丸注入结果相比拟。除了氦的同位素效应之外,粒子注入的深度引起密度剖面峰化是约束改善的重要因素。因为在HL-1M装置常规喷气加料的Q_n值仅为1.4。分子束加料后的粒子约束时间比加料前高6倍。     

HL-1M装置超声分子束流注入过程中的团簇现象

在环流器等离子体中用超声分子束流注入加料,引起密度峰化和约束改善,其主要机制归结为加料粒子的注入深化和密度上升率(注入效率)的提高。本文主要介绍经过改进的超声分子束流注入HL-1M装置等离子体利用边缘H_α。线辐射、径向可伸缩的静电探针和顺着束流注入方向的CCD摄像等诊断技术,考察了粒子注入口及注入口附近区域电子温度和密度沿径向分布的变化,研究了分子束粒子注入等离子体的所谓“冷通道模型”及其效应。     

911A型中空阴极离子源的改进

对从丹麦进口的９１１Ａ型中空阴极离子源进行了重新设计，经多次出束调试及改进，离子源部件已基本国产化。气体束可达到１０＾－５Ａ；固体束最大可达到１０＾－６Ａ，一次填料可持续稳定地工作５ｈ左右。     

脉冲分子束注入HL-1M装置等离子体行为研究

介于已有的喷气(Gas puffing)和弹丸注入(Ice pellet injection)之间,提出了一种新的托卡马克加料手段——脉冲超声分子束注入。在较高的粒子注入通量5×10~(19)/脉冲时,氢分子的速度仍可达到500m/s。一系列氦分子束脉冲注入初始密度为(?)=0.4×10~(19)m~(-3)HL-1M真空室氢等离子体,经过160ms,密度上升至(?)=5.4×10~(19)m~(-3)。根据脉冲分子束注入初期氦光谱(He I 587·6nm)强度的径向分布,1/3峰高位于γ=12cm附近。注入     

HL-1M装置离子回旋波注入实验的边缘参数测量

为了提高等离子体温度和密度,在高参数下从事托卡马克等离子体物理研究,在HL-1M装置上进行低杂波加热和电子回旋波加热的基础上,我们最近开展了离子回旋波注入和中性束注入加热实验,以及弹丸注入加料和分子束注入(MBI)加料实验,特别是在后者的实验中获得了很高的粒子和能量约束时间。     

HL—1聚变装置中子发射实验研究

采用ＺｎＳ（Ａｇ）闪烁计数器，经标准中子源刻度校正后，测量ＨＬ－１（中国环流器一号）聚变装置的中子演化和中子产额；同时用活化箔法（１１５Ｉｎ）和原子核乳胶法测量中子产额。在真空室充氘和电子回旋共振加热（ＥＣＲＨ）时，３种方法同时测量，确证ＨＬ－１每放电１次发射中子数平均为（３．４１±０．５０）×１０１０。得到欧姆加热、ＥＣＲＨ、改进约束放电（ＩＯＣ）和弹丸注入等放电实验中的中子演化。在分子束注入和偏压电极（ＥＰＰ）放电实验中，产生中子较少或很少。观察部分放电方式产生的中子产额Ｎ和硬Ｘ射线产额ＨＸ间有线性关系Ｎ＝ａＨＸ－ｂ，其中，ａ和ｂ是与装置运行方式有关的常数。     

An Introduction to the Supersonic Molecular Beam injection

Magnet confinement fusion plasma physics1. IntroductionThe most commonly used system for initiating andmaintaining density in present-day tokamak is gaspuffing, but its major physics issue is whether ornot the fuel introduced at the plasma boundary canpenetrate the SOL to reach the region Of the coreplasma ti.here it is needed. The fuelling efficiency ofpresence-day tokimaks inclusive of start-up is of theorder of 10% for gas puffing. The gas fuelling efficiency is dependent on the SOL thic…     

Fuelling and Diagnostics with Pellet Injection in the HL-1M Tokamak

The pellet injection experiments for fuelling and diagnostics have been carried out on the HL-1M tokamak. The eight-pellet injector was installed on HL-1M. A reliable monitordetector and camera system was set up to take initial pellet photographs and measure the initial pellet speed and size. High fuelling efficiency of 60 % - 100 % and a density profile with a peaking factor of 1.8 - 2.0 were obtained. The maximum density close to 10^14/cm^3 in HL-1M was achieved with newly optimized combined fuelling techniques. Two typical models of pellet ablation have been utilized for simulative calculation of the ablation rates in HL-1M. In comparison with the distribution of the measured Hα emission intensity from the digital data of the CCD camera, the experimental result seems more optimistic for core fuelling than theoretical predictions by the two models. The safety factor profile q（r） has been extracted from the information provided by the CCD camera during the pellet injection. The reliability of the measured results depends mainly on the calibration of the imaging space position. Based on the calibration, the measured q-profile becomes more reasonable than those published previously for the same shot number and same photograph.     

Effect of Fuelling Depth on the Fusion Performance and Particle Confinement of a Fusion Reactor

The fusion performance and particle confinement of an international thermonuclear experimental reactor(ITER)-like fusion device have been modeled by numerically solving the energy transport equation and the particle transport equation. The effect of fuelling depth has been investigated. The plasma is primarily heated by the fusion produced alpha particles and the loss process of particles and energy in the scrape-off layer has been taken into account. To study the effect of fuelling depth on fusion performance, the ITERH-98P(y,2) scaling law has been used to evaluate the transport coefficients. It is shown that the particle confinement and fusion performance are significantly dependent on the fuelling depth. Deviation of 10% of the minor radius on fuelling depth can make the particle confinement change by ~ 61% and the fusion performance change by ~ 108%. The enhancement of fusion performance is due to the better particle confinement induced by deeper particle fuelling.     

Mechanisms of Extending Operation Regionin the HL-1M Tokamak

1. IntroductionThe HL-1 tokamak had been modified to HL-IMby replacing the vacuum chamber from 1993 to 1994[1]. Some main modifications are'1. Removing the thick copper shell.2. Increasing the minor radius from 0.20 m to 0.26m.3. Replacing two full poloidal molybdenum limiters by graphite limiters.4. Covering about 6.5 % metallic wall surface withsome graphite components, such as two sets oftoroidal belt limiter, four sets of poloidal halfring protecting bellows, one set of plates protecti…     

Analysis of Divertor Heat Flux with Infrared Thermography During Gas Fuelling in the HL-2A Tokamak

In HL-2A tokamaks, the behavior of heat flux deposited on the divertor targets has been studied during deuterium gas fuelling. The heat flux is reduced significantly after supersonic molecular beam injection （SMBI） fuelling during Ohmic and electron cyclotron resonance heating （ECRH） divertor discharges. The SMBI fuelling causes an increase in the plasma density and this change results in the experienced change of the edge properties. Most of this reduction in divertor target heat flux occurs together with a high plasma radiation region located at near the X-point. The largest reduction in heat flux profiles is observed at the outboard divertor separatrix strike point, while the heat flux far from the strike point remains almost unchanged. In particular, with SMBI multi-pulses gas fuelling, a partially detached divertor regime is observed with a highly radiating region at the X-point. With the onset of the partially detached divertor regime, a sudden drop in both heat flux and power flow on the divertor target is observed. The reduction in power load on the divertor targets is roughly equal to the increase in plasma radiation loss.     

Experimental Observation of the Pulsed High Pressure Gas Puffing on HL-2A Tokamak

The pulse propagations of both the electron temperature and the electron density have been observed during pulse-modulated molecular beam injection experiments on HL-2A. The propagation depth of the cold pulse in the low field side is much longer than that in the high field side. The cold pulses cannot propagate to the plasma center from either the low field side or the high field side. The electron temperature in the plasma center does not change during MBI, but the electron density pulse perturbations can be observed in the plasma center.     

The Principle of Plasma Boundary Identification on HL-2A Tokamak

Plasma boundary identification is a basic task for studies on equilibrium and confinement in a divertor tokamak. With the progress on the experiments after engineering experiments, the boundary identification becomes an important issue for HL-2A. In order to satisfy the requirements of preciseness, simplified measurements and quickness, the filament current method instead of solving the equilibrium equations is used to identify plasma boundary on HL-2A. The involved principle, mathematics and the progresses, which have been made with this method, are given.     

中国环流器二号A装置工程与实验进展

介绍了中国环流器二号A(简称HL-2A)装置上关键聚变工程技术取得的新进展及在磁约束聚变科学若干关键课题研究取得的重要实验成果,特别是在HL-2A装置上成功实现了偏滤器位形下具有边缘局域模的高约束模式运行,是我国磁约束聚变实验研究史上具有里程碑意义的重大进展,使我国的磁约束聚变科学和等离子体物理实验研究进入了一个崭新的阶段。     

中国环流器二号A装置工程与实验进展

介绍了中国环流器二号A(简称HL-2A)装置上关键聚变工程技术取得的新进展及在磁约束聚变科学若干关键课题研究取得的重要实验成果,特别是在HL-2A装置上成功实现了偏滤器位形下具有边缘局域模的高约束模式运行,是我国磁约束聚变实验研究史上具有里程碑意义的重大进展,使我国的磁约束聚变科学和等离子体物理实验研究进入了一个崭新的阶段。