不锈钢表面Al2O3膜的微弧氧化制备

报道了在奥氏体不锈钢表面制备氧化物陶瓷膜的新方法．首先用热浸镀工艺在不锈钢表面镀铝，然后利用铝的微弧氧化形成了Al2O3陶瓷膜．对所获得的样品进行了断面形貌观察、成分和相组成分析发现，在金属间化合物上形成的陶瓷膜主要由Q．A1203和γ-Al2O3构成，γ-Al2O3的含量高于α-Al2O3．对其硬度测试发现，从基底到表面硬度呈梯度分布，氧化物陶瓷表面的硬度约为800HV．     

Temperature of the Limiter Surface Measured by IR Camera in HT-7 Tokamak

Temperature measurement by IR （infrared） camera was performed oll HT-T tokamak. particularly during long pulse discharges, during which the temperature of the hot spots on the belt limiter exceeded 1000℃. The heat load on the surface of the movable limiter could be obtained through ANSYS with the temperature measured by IR-camera. This work could be important for the temperature measurement and heat load study on the first wall of EAST device.     

Deuterium Retention in SiC-Coated Graphite Tiles of EAST

Fuel retention and recycling in plasma facing materials is a crucial issue for fusion devices, especially for the long pulse discharge devices. In this work, the deuterium retention and the surface erosion of SiC-coated graphite tiles exposed to EAST plasmas have been studied by post-mortem analyses, i.e., thermal desorption spectroscopy （TDS）, secondary ion mass spec- troscopy （SIMS） and scanning electron microscopy （SEM）. The results show that the sample cut from the high field side （HF） tile has been intensely eroded due to deuterium bombardment on plasma facing surfaces in the initial phase of discharges and trapped highest amount of deuterium. Lower deuterium retention has been found in the inner divertor sample, which is presumably due to the particular exposure history in the 2010 spring campaign.     

A Molecular Dynamics Study on the Dust-Plasma/Wall Interactions in the EAST Tokamak

The interactions between the W nano-dust and deuterium plasma at different locations of the EAST tokamak are simulated using a molecular dynamics code. It is shown that nano-dust particles, with the radius, R d , ～5 nm, can exist for at least several nano-seconds under the interactions from the ions without being ablated in some specific places of the tokamak edge plasma, while those with R d ≥25 nm may be ablated if the plasma temperature T～ 50 eV and density n～10 19 m 3 . In addition, the collisions of tungsten nano-dust grains with a tungsten wall at 100 m/s or 1000 m/s impinging speeds are simulated. It is demonstrated that the dust will stick to the wall, and the collision will not cause substantial damage to the wall, but it may be able to cause partial destruction of the dust grains themselves depending on their incident speeds.     

PIC-EDDY Simulation of Different Impurities Deposition in Gaps of Carbon Tiles

A 3D Monte Carlo （MC） code PIC- EDDY, based on EDDY （erosion and deposition dynamic simulation） code, was used to investigate the redeposition of different impurities in the gaps of C tiles. By incorporating the rate coefficients of beryllium （Be） and tungsten （W） into the code, we obtain deposition profiles of hydrocarbon, beryllium and tungsten particles in the toroidal and poloidal gaps, respectively. The redeposition rate of tungsten was found to be higher than those of other impurities in the gaps, except at the bottom, due to its easier local deposition within one gyroradius. Due to the effect of reflection coefficients of hydrocarbon fragments on graphite, fewer hydrocarbons were resided at the entrance while more were deposited on the sides of the gap. At elevated plasma temperatures （such as 30 eV）, asymmetric deposition distributions were observed between the toroidal and poloidal gaps due to the dominant ionized particles. Ions were mainly deposited within 1 mm depth inside gaps, and the bottom deposition particles were almost all neutrals.     

托卡马克装置中减缓偏滤器靶板热流的Ne杂质注入研究进展

托卡马克装置中偏滤器的能量排除一直是磁约束核聚变中最迫切需要解决的关键问题之一,而辐射偏滤器运行模式可以有效降低托卡马克装置中偏滤器靶板的热流和粒子流。本文全面介绍了氖(Ne)作为注入杂质在ASDEX-Upgrade、JET、DⅢ-D、HL-2A、EAST等装置上取得的最新的重要结果,同时总结了Ne等杂质在碳、钨材料偏滤器下的不同表现。钨作为未来聚变装置偏滤器以及第一壁等的材料,有着很大优势,但杂质注入下存在钨杂质溅射及聚芯问题,所以还需进一步探索钨偏滤器与注入杂质的兼容性以满足ITER等装置的要求。