After three years of operation (2017–2019) and four experimental campaigns (C1 to C4), the first phase of operation of the WEST tokamak has now come to an end. During that period, WEST has operated with tungsten coated copper-based and carbon-based plasma facing components in order to comply with a full metallic environment. A set of components, called plasma facing units, using ITER tungsten monoblock technology was also installed onto one sector of the lower divertor to test their behaviour in a real tokamak environment. This paper gives an overview of the ageing behaviour of these components during in situ visual inspections. It is shown that tungsten coatings are in a good condition after 3 years of operation but are prone to delamination in the areas dominated by off-normal events such as runaway electrons or arcing. For this reason, the W coated carbon tiles of the outer limiter were replaced by bulk W tiles after the C3 campaign. As for the bulk tungsten ITER-like components, damage such as melting and cracking was mainly observed on the monoblock edges exposed to the parallel heat flux. The first observations show that the damage formed during C3 on the tungsten monoblocks did not evolve during C4, which leads to believe that it results from singular events rather than continuous heating due to steady state operation.

经过三年运行（2017-2019 年）和四次实验活动（C1 至 C4），西托卡马克的第一阶段运行现已结束。在此期间，WEST 使用镀钨的铜基和碳基等离子面向组件运行，以符合全金属环境。使用 ITER 钨单块技术的一组组件（称为面向等离子体单元）也安装在下偏滤器的一个扇区上，以测试它们在真实托卡马克环境中的行为。本文概述了这些组件在原位老化过程中的老化行为。目视检查。结果表明，钨涂层在运行 3 年后处于良好状态，但在由失控电子或电弧等非正常事件主导的区域容易发生分层。出于这个原因，在 C3 运动之后，外部限制器的 W 涂层碳砖被散装 W 砖取代。对于类钨 ITER 组件，主要在暴露于平行热通量的整体边缘上观察到熔化和开裂等损坏。第一个观察结果表明，在 C3 期间对钨单体形成的损坏在 C4 期间没有发生，这导致人们相信它是由奇异事件引起的，而不是由于稳态操作而导致的连续加热。