Runaway Electron Measurements in the EAST Tokamak

An experimental study of runaway electrons in the EAST tokamak has been performed by a recently developed multi‐channel hard x‐ray diagnostics based on NaI(TL) scintillator detectors. It is found that in the current quench phase, the inductive loop voltage plays an important role in the generation of runaway electrons. And the avalanche mechanism was the main mechanism for runaway electrons after the disruptions. The distribution and transportation of runaway electrons were also investigated by multi‐channel hard x‐ray diagnostics. It is also found that the intensity of runaway electrons emission in the core plasma was much higher than those in the downside of the cross‐section, while the emission intensity of runaway electrons in the core plasma was almost the same. Calculated shrinking coefficient of runaway electrons emission after the plasma disruption was about 26 m/s according to the experimental data (© 2010 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)     

Evolution of filament structures during edge-localized modes in the MAST Tokamak

Edge-localized modes (ELMs) are repetitive instabilities that occur in the outer region of tokamak plasmas. This Letter provides new information on and the implications of the evolution of the filament structures observed during ELMs in the MAST tokamak. The filaments exist for the time over which particles are being released into the scrape off layer. They start off at the plasma edge rotating at the velocity of the pedestal, and then decelerate toroidally and accelerate radially outwards. As the filaments propagate radially they remain aligned with the local magnetic field line.     

Transition between internal transport barriers with different temperature-profile curvatures in JT-60U Tokamak plasmas

A spontaneous transition phenomena between two states of a plasma with an internal transport barrier (ITB) is observed in the steady-state phase of the magnetic shear in the negative magnetic shear plasma in the JT-60U tokamak. These two ITB states are characterized by different profiles of the second radial derivative of the ion temperature inside the ITB region (one has a weak concave shape and the other has a strong convex shape) and by different degrees of sharpness of the interfaces between the L mode and the ITB region, which is determined by the turbulence penetration into the ITB region.     

HT-7电子加热实验的软X射线能谱诊断

介绍了HT-7装置上软X射线能谱诊断系统,用软X射线能谱对HT-7托卡马克上电子温度进行了测量。在离子伯恩斯坦波和低杂波协同实验中,观察到了对等离子体的较好的加热效果。     

J-TEXT托卡马克高速单色成像系统研制

在 J-TEXT 托卡马克上研制了一套高速单色成像系统用于研究等离子体杂质行为与磁流体力学(MHD) 不稳定性之间的关系。用 STRAH 代码模拟估算了碳杂质(CV227.09nm,CIII464.7nm)辐射强度。采用光纤耦合方 法设计了系统光路结构,光路覆盖高场侧区域 0.3a~0.95a(a 为小半径),其空间分辨率为 1.3cm。选用光电倍增管 (PMT)作为系统的探测器,结合跨阻电路与有源滤波器的电路方案,系统实现 5×10⁵VA^-1 电流增益,其电路带宽 为 100kHz,时间分辨率达到 10μs。初步实验结果表明,系统可以监测到 J-TEXT 中等离子体 MHD 不稳定性放电 中 CV 分布的变化。      

Analysis of Dα（Hα） spectrum emitted in front of the limiter in HT-7^＊

In order to understand the recycling and emission processes of hydrogen atoms in HT 7, spectral profiles of the Dα（Hα） line emitted in front of the limiter have been observed with a high-resolution spectrometer and simulated by using the neutral particle transport code DEGAS 2. The results show that four processes are necessary to interpret the Dα（Hα） line shape： 1） atom desorption, 2） molecular dissociation, 3） particle reflection, and 4） charge-exchange. The products of the first two processes are cold atoms which emit photons near the peak of Dα（Hα） line shape, and those from the last two are warm atoms contributing to the blue side of the spectrum. For a typical ohmic discharge （shot 68520 ne（0） ≈ 3× 10^19 m^-3. these components contribute 32%, 15%, 32% and 21%, respectively. Dα（Hα） line shapes under different plasma parameters are also discussed in this paper.     

磁约束聚变堆及ITER实验包层模块设计研究进展

目前国际上代表性的磁约束聚变反应堆设计包括美国的ARIES系列和APEX系列、欧洲的PPCS系列、日本的SSTR系列、中国的FDS系列设计,以及国际合作的国际热核聚变实验堆等。这些设计研究涉及到聚变能科学技术发展的各个方面,包括聚变实验堆、商用示范堆和商用动力电站等的设计研究、相关物理和技术发展以及相关的能源技术与经济策略研究等。简要介绍了上述设计研究领域的现状和发展趋势。The uhimate goal of the fusion program is to develop large scale power plants for the production of electricity. At present, there are many representative designs of magnetic confinement fusion reactors in the world,e.g. ARIES and APEX in USA, PPCS in EU, SSTR in Japan, FDS in China, and International Thermonuclear Experimental Reactor （ITER）. These studies cover many aspects on fusion experimental reactors, DEMO reactors, and commercial fusion power plants, including plasma physics, blanket technologies, material behavior, and technologies required to construct and operate such complex plants. The study status and development strategy in various countries are summarized and reviewed.