ITER偏滤器W/Cu单体模块热-结构模拟与分析

采用有限元分析软件ANSYS模拟分析了W/Cu单体模块在ITER稳态热流和瞬态热流叠加下的温度分布和应力分布。结果表明,在稳态热流下,结构安全可靠;但在瞬态热流加载下,钨材料表面发生塑性应变,发生塑性应变的临界热流密度为320MW·m 2(持续0.5ms)。模拟结果对ITER偏滤器的设计和升级改造具有一定的借鉴意义。

EAST边缘等离子体中钨表面电弧诱导实验研究

在EAST装置中利用材料与等离子体测试平台MAPES对不同表面性质和结构的钨样品进行了边缘等离子体条件下的起弧诱导实验研究。结果显示只有纳米丝结构的钨表面成功产生了电弧,表明了钨表面的纳米丝结构更有利于电弧的触发,甚至在装置远离刮削层区域的地方也能诱导电弧触发。在纳米丝钨表面起弧过程中会产生两种不同的电弧,其中较强电弧能产生熔坑,并溅射出液滴,是等离子体中尘埃及杂质的重要来源。弧坑直径约为3μm,深度约为0.7μm,在电弧熔坑中心区域形成了一些小孔和纳米结构,其周围的熔化液滴也存在类似的结构。

EAST等离子体辐照对第一镜光学特性的影响研究

2010年春季对安装在EAST抽气、硼化和限制器等所在的不同窗口的不锈钢、钨、钼等三种金属第一镜样品进行辐照实验,以初步研究等离子体辐照对第一镜光学特性的影响。辐照后,样品表面出现明显杂质沉积层,沉积层导致第一镜光学特性严重恶化。因此,对第一镜安装有效的保护装置以屏蔽杂质沉积,或应用第一镜原位清洗技术是必要的。

Analysis of Residual Thermal Stress in CVD-W Coating as Plasma Facing Material

Chemical vapor deposition-tungsten （CVD-W） coating covering the surface of the plasma facing component （PFC） is an effective method to implement the tungsten material as plasma facing material （PFM） in fusion devices. Residual thermal stress in CVD-W coating due to thermal mismatch between coating and substrate was successfully simulated by using a finite element method （ANSYS 10.0 code）. The deposition parametric effects, i.e., coating thickness and deposition temperature, and interlayer were investigated to get a description of the residual thermal stress in the CVD-W coating-substrate system. And the influence of the substrate materials on the generation of residual thermal stress in the CVD-W coating was analyzed with respect to the CVD-W coating application as PFM. This analysis is beneficial for the preparation and application of CVD-W coating.

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.

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 0.75 MJ/m2 for about 0.5 ms. All these results are useful for the design of the plasma facing components （PFCs） and the plasma operation in the future.

钨材料在瞬态高热流冲击下热结构响应过程模拟和分析

采用有限元分析软件ANSYS模拟了面对等离子体钨材料在聚变瞬态高热流加载和卸载过程中的温度和应力分布以及演化过程,并结合材料力学性能对热冲击开裂行为进行了分析和讨论。结果表明,在瞬态热流下,钨的单次热冲击开裂阈值约200MW·m^(-2)(~5ms)、460MW·m^(-2)(~1ms)和660MW·m^(-2)(~0.5ms),其临界热流因子(14.14~14.75MW·m^(-2)·s^(1/2))也基本一致。

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.

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. Microstruc- ture morphologies show that the TiC particles distribute homogeneously in the W matrix, strength- ening 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.

Characterization of dust collected in EAST after 2019 campaign

Dust presented in experimental advanced superconducting tokamak(EAST)with mixed plasmafacing materials has been collected and characterized for the first time.Dust at different positions in the vessel was collected by vacuum cleaner after the first experimental campaign in 2019.The shape,composition,and size of dust particles have been analyzed using different methods.About 80%of the total number of dust particles have size between 20 and 80μm,and most of dust particles are spherical,while schistose shape,columnar and irregular shape were also found.With the help of energy-dispersive x-ray spectroscopy different elements of dust have been identified,which is generally consistent with the different plasma-facing components in EAST.Both x-ray fluorescence and inductively coupled plasma emission spectrometer are complementary methods for measuring the dust composition quantitatively.It was found that the major components of dust were lithium dust in the form of lithium carbonate and lithium hydroxide,which is due to the routine lithium wall conditioning during EAST operation.

Thermal analysis on the EAST tungsten plasma facing components with shaping structure counteracting the misalignment issues

Tungsten monoblock type tiles with ITER dimensions along with supporting cassette components were installed at EAST＇s upper diverter during 2014 and EAST＇s lower diverter will also be upgraded in the future. These cassette structures pose critical issues on the high cumulative incident heat flux due to the leading edges and misalignments （0 ～ 1.5 mm）, which may result in the destruction or even melting of the tungsten tile. The present work summarizes the thermal analysis using ANSYS multiphysics software 15.0 performed on the actively cooled W tiles to evaluate the shaping effect on surface temperature. In the current heat flux conditions （Q11 ～ 100 MW m-2）, the adopted chamfer shaping （1 ×1 mm） can only reduce the maximum temperature by about 14%, but it also has a melting risk at the maximum misalignment of 1.5 mm. The candidate shaping solutions elliptical （round） edge, dome and fish-scale are analyzed for comparison and are identified not as good as the dual chamfer structure. A relatively good dual chamfer （2 ×13 mm） shaping forming a symmetrical sloping roof structure can effectively counteract the 1.5 mm misalignment, reducing the maximum temperature by up to 50%. However, in the future heat flux conditions （Q11 ～287 MW m-2）, it may only endure about 0.5 mm misalignment. Moreover, no proper shaping solution has been found that can avoid melting at the maximum misalignment of 1.5 mm. Thus, the engineering misalignment has to be limited to an acceptable level.

Repetitive cleaning of a stainless steel first mirror using radio frequency plasma

First mirrors（FMs） are crucial components of optical diagnostic systems in present-day tokamaks and future fusion reactors. Their lifetimes should be extremely limited due to their proximity to burning plasma, greatly influencing the safe operation of corresponding diagnostics.Repetitive cleaning is expected to provide a solution to the frequent replacement of contaminated FMs, thus prolonging their lifetimes. Three repetitive cleaning cycles using radio frequency plasma were applied to stainless steel（SS） FM samples, to evaluate the change of the mirrors＇ optical properties and morphology during each cycle. Amorphous carbon films were deposited on mirror surfaces under identical conditions in three cycles. In three cycles with identical cleaning parameters, the total reflectivity was restored at up to 95%. Nevertheless, with successive cleaning cycles, the FM surfaces gradually appeared to roughen due to damage to the grain boundaries. Correspondingly, the diffuse reflectivity increased from a few percent to 20%and 27% after the second and third cycles. After optimizing the cleaning parameters of the second and third cycles, the roughness showed a significant decrease, and simultaneously the increase of diffuse reflectivity was remarkably improved.

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/CuFGM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10MW/m2的表面热流冲击下,表现出较好的抗热冲击能力。