Deposition Mitigation of the First Mirrors Exposed in EAST with Metal and Carbon Mixed Wall Materials

In order to investigate the effect of aperture geometry on deposition mitigation, stainless steel （SS） first mirrors （FMs） were fixed on the holders of protective aperture geometry with different depth-diameter ratios （DDRs） and exposed in the deposition dominated environment of EAST. A baffle was used during the wall conditioning. The surface properties and reflectivity of the FMs were characterized before and after exposure. It is shown that using aperture geometry and a baffle can effectively mitigate the impurities deposition. The degradation of the surface and specular reflectivity of the FMs is reduced with the increase of DDRs in the range of 0 to 2. The main contaminated elements in a low-Z and high-Z mixed wall materials environment were still carbon and oxygen.     

Cleaning of HT-7 Tokamak Exposed First Mirrors by Radio Frequency Magnetron Sputtering Plasma

The stainless steel （SS） first mirror pre-exposed in the deposition-dominated envi- ronment of the HT-7 tokamak was cleaned in the newly built radio frequency （RF） magnetron sputtering plasma device. The deposition layer on the FM surface formed during the exposure was successfully removed by argon plasma with a RF power of about 80 W and a gas pressure of 0.087 Pa for 30 min. The total reflectivity of the mirrors was recovered up to 90% in the wavelength range of 300-800 nm, while the diffuse reflectivity showed a little increase, which was attributed to the increase of surface roughness in sputtering, and residual contaminants. The FMs made from single crystal materials could help to achieve a desired recovery of specular reflectivity in the future.     

Thermo-Mechanical Calculation of Vacuum Plasma Spraying Tungsten Coating as the Plasma Facing Material for Tokamak Device

Thermo-mechanical simulation of the vacuum plasma spraying tungsten (VPS-W) coating on the actively cooled CuCrZr substrate under the relevant quasi-stationary heat load and transient heat flux for tokamak device,is conducted by finite element analysis (FEA).It is shown that the failure of copper softening is likely to occur at the W/Cu compliant interlayer under a typical quasi-stationary heat load and the surface failure of plastic yield damage to occur at the surface edge under a transient heat flux.In addition,the critical transient heat flux for melting is approximately 0.75MJ/m2 for about 0.5ms.All these results are useful for the design of the plasma facing components (PFCs) and the plasma operation in the future.     

Surface Cracking Behaviors of Ultra-Fine Grained Tungsten Under Edge Plasma Loading in the HT-7 Tokamak

Tests of the candidate plasma facing materials(PFMs) used in experimental fusion devices are essential due to the direct influence of in-situ plasma loading.A type of ultrafine grained(UFG) tungsten sintered by resistance sintering under ultra-high pressure(RSUHP) method has been exposed in the edge plasma of the HT-7 tokamak to investigate its performance under plasma loading.Under cychc edge plasma loading,the UFG tungsten develops both macro and micro cracks.The macro cracks are attributed to the low temperature brittleness of the tungsten material itself,while the micro cracks are generated from local intense power flux deposition.     

偏滤器第一壁W/Cu FGM的热应力模拟与优化设计

采用有限元ANSYS软件对偏滤器第一壁W/Cu FGM进行热应力模拟分析,并对其参数进行优化设计。结果表明,优化后的梯度层应力较无梯度层时得到了极大的缓和,最大等效应力值降低58%。最优化的梯度层层数为5,Cu浓度分布指数为0.4;同时在10 MW/m2的表面热流冲击下,表现出较好的抗热冲击能力     

Exposure of W-TiC/Cu Functionally Graded Materials in the Edge Plasma of HT-7 Tokamak

Six-layered W-TiC/Cu functionally graded materials were fabricated by resistance sintering under ultra-high pressure and exposed in the edge plasma of HT-7 tokamak.Microstructure morphologies show that the TiC particles distribute homogeneously in the W matrix,strengthening the grain boundary,while gradient layers provide a good compositional transition from W-TiC to Cu.After about 360 shots in the HT-7 tokamak,clear surface modification can be observed after plasma exposure,and the addition of nano TiC particles is beneficial to the improvement of plasma loads resistance of W.