The W (tungsten) samples were placed at Top, Equator and Bottom plasma facing walls of QUEST (Q-shu University Experiment with Steady-State-Spherical Tokamak) device and exposed to 754 shots of hydrogen plasma during 2017A/W (Autumn/Winter) campaign. Thereafter, their surface morphologies and chemical states were evaluated by TEM (Transmission Electron Microscope) and XPS (X-ray photoelectron spectroscopy). The XPS results showed that a thick carbon layer about 3–18 nm has formed throughout the wall surface. Among them, the Bottom wall had the deposition layer with the thickness of 2 nm, which was thinner than the top wall, namely erosion-dominated. On the other hand, a thick C layer about 18 nm was deposited on the Equator wall. The additional 1 keV D₂⁺ was implanted into these samples and the D (deuterium) retention enhancement was estimated. The D₂ TDS (Thermal Desorption Spectroscopy) spectra for all the samples had two major desorption stages at 400 K and 650 K, namely the desorption of D trapped by irradiation damages and deposition layer. The erosion/deposition profile would be caused by wall position and plasma condition, like a current start-up experiment. The desorption temperature of H₂ (hydrogen) was shifted toward higher temperature side compared to that exposed to previous plasma campaign (2016 A/W), suggesting that H was mainly accumulated in the deposition layer with forming C–H bonds.

将W（钨）样品放在QUEST（Q-shu大学的稳态态球形托卡马克实验）装置的顶，赤道和底面等离子体壁上，并在2017A / W（秋/冬）期间暴露于754张氢等离子体）广告系列。之后，通过TEM（透射电子显微镜）和XPS（X射线光电子能谱）评价其表面形态和化学状态。XPS结果表明，整个壁表面形成了大约3–18 nm的厚碳层。其中，底壁具有2nm的厚度的沉积层，该沉积层比顶壁薄，即侵蚀为主。另一方面，在赤道壁上沉积了约18 nm的厚C层。额外的1 keV D ₂ ⁺将其植入这些样品中，并估计D（氘）的保留增强。所有样品的D ₂ TDS（热解吸光谱）光谱在400 K和650 K有两个主要的解吸阶段，即被辐照损伤和沉积层捕获的D的解吸。腐蚀/沉积轮廓将由壁位置和等离子体条件引起，例如当前的启动实验。与以前的等离子运动（2016 A / W）相比，H ₂（氢）的解吸温度移向了较高的温度侧，这表明H主要沉积在沉积层中并形成了C–H键。