人类能创造自己的太阳吗?

 科学家力图在地球上实现宇宙星体的能量反应并加以利用.人类能创造自己的太阳吗?答案是肯定的,而且前途乐观.世间万物无不享受着太阳的恩患.沐浴着太阳的光辉,地球才出现生命,形成繁荣的生物圈和万能的智慧圈,才进入今天的文明时代.人类自从从懂得使用火以来,开发能源的手段越来越多.本世纪三十年代,在核物理发展的早期科学家就已发现:四个氢原子核会聚合成一个较重的氦原子核,同时释放出巨大能量.不久,又发现这种轻核聚合反应是宇宙中星体能量的主要来源。     

Effects of Dual-Electrode Biasing on Er in a Toroidal Plasma

Two externally biased electrodes were inserted into the plasma on the KT-5C tokamak to test the effects on modifying the radial electric field Er, other than single biasing. Using various combinations of biasing voltage,the influences of double biasing are compared with the single biasing. It turns out that the effect of dual-biasing is also effective as a single one, but the outer electrode seems to be shielded by the inner one and show less influence. The results clearly show that the radial electric field Er changed by external biasing is intrinsically an effect localized at the edge of the plasma, which is caused by the electrode induced radial current; and dualelectrode biasing using the method similar to the single biasing seems not to be able to increase more distinctly the peaking effect on Er than the single biasing.     

High Bootstrap Current Fraction during the Synergy of LHCD and IBW on the HT-7 Tokamak

More than 70% of the total plasma current is sustained by the bootstrap current and current drive during the synergy of lower hybrid current driving (LHCD) and ion Berstein wave (IBW) heating on the HT-7 tokamak.The lower hybrid non-inductive current source is off-axis and well localized, and more than 35% bootstrap current plasma has been obtained. The IBW in controlling electron pressure profile can be integrated into the LHCD target plasma. The largest steep gradient of the electron pressure profile in the region ρ - 0.5-0.7 mostly comes from the electron temperature profile, which may induce the large fraction bootstrap current. The large off-axis bootstrap current can help to create negative magnetic shear, and the good plasma confinement is achieved.     

Investigation of Impurity Ion Transport with Laser Blow-off in HL-2A Tokamak

Non-recycling impurities are injected into ohmic HL-2A plasma for the first time. The impurities of titanium and aluminium are injected in the discharges with varying plasma density and current. The convection and diffusion process of the injected impurity ions during the inward phase are qualitatively investigated. The results show that the transport of impurities is much slower in the central region of the plasma than outside of it and that it is greatly enhanced during sawtooth crashes.     

ECRH主高压电源控制系统的设计

1引言 在托卡马克聚变研究装置中，ECRH主要被用于整体或局部的电子加热、控制电子温度和等离子体电流等重要参数的分布截面、抑制等离子体磁流体动力学不稳定性、改善等离子体约束等。ECRH高压电源的参数为：电压-55kV，电流25～30A，稳定度1％，另外，要求电源系统不仅具有快速的保护性能，并且要具有较高的稳定度。     

Transient Temperature and Stress Analysis of an Electrode on 60 kV, 55 A, 2 s Ion Source

The engineering design of 60 kV, 55 A, 2 s bucket ion source for HL-2A has been finished. The current design is based on an extraction-acceldecel extraction system that is composed of plasma electrode, acceleration electrode, deceleration electrode and grounded electrode. The primary and secondary particles due to beams ionization in each region of extraction system will hit the surface of electrode. The power loads on an electrode is estimated both theoretically and experimentally to be 1%-2% of the ion beam power, which may cause serious problems, such as thermal deformation followed by ion beam distortion and melting leading to water leaks. To ensure the mechanical reliability and no plastic deformation, it is important and necessary to analysis the temperature and stress distribution.     

Tokamak Experiment and Tokamak Engineering——Development of the Plasma Diagnostics on HL-2A Tokamak

The main mission the HL-2A tokamak is of the experiments on to explore the divertor physics and to investigate the plasma confinement, transport and instabilities with high power auxiliary heating and advanced fuelling, it is necessary to develop more new diagnostics and increase the spatial and temporal resolutions of the measurements for exist system. Up to now, about 30 diagnostic systems have been moved from HL-1M to HL-2A tokamak. Other 10 diagnostic systems are being designed and installed on the device. In developed in last 2 years, will be presented.     

Vacuum System for HL-2A Tokamak

The vacuum system of today＇s tokamak devices is designed to meet the operational requirements of the experiments. The operation can be divided into five modes, （1） pumping down and leak detecting of the vacuum vessel, （2） baking, （3） plasma-facing component （PFC） conditioning, （4）evacuating and controlling of the particles at plasma edge, （5） plasma discharge experiments.     

Development of Vacuum Monitoring System in the HL-2A tokamak

HL-2A is the first divertor tokamak in China. The vacuum system is one of the important parts of the HL-2A tokamak, which has to be work well during the physics campaign in 2004. As the tokamak machine is separated from the operation staff during discharges, to guarantee the safe and reliable operation of the vacuum system, it is necessary to watch the vacuum system outside the machine hall with an automatic monitoring system. The paper describes the design and manufacture of the monitoring system.