Overview of plasma-facing materials and components for EAST
Overview of plasma-facing materials and components for EAST
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DOI：
10.1088/0031-8949/2007/t128/001
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发表时间：
2007-03
期刊：
影响因子：
2.9
通讯作者：
G. Luo;X. Zhang;D. Yao;X. Gong;J. Chen;Z. Yang;Q. Li;B. Shi;J. Li
中科院分区：
文献类型：
--
作者：
G. Luo;X. Zhang;D. Yao;X. Gong;J. Chen;Z. Yang;Q. Li;B. Shi;J. Li
2006年9月底，实验先进超导托卡马克（EAST）完成了工程调试，并实现了第一个以不锈钢作为等离子体面对材料（PFM）的H2等离子体。在接下来的阶段中，随着加热功率的逐渐增加，EAST偏滤器靶必须处理高达10 MW m−2的预期热负荷。采用的PFMs包括掺杂石墨和W涂层。在第一阶段，石墨瓦覆盖整个等离子体面，在第二阶段，石墨瓦逐渐取代石墨瓦，最终形成完整的W等离子体面。石墨已经被研究了很多年，并为HT-7实现约100 s的长脉冲做出了巨大贡献。介绍了目前正在开发的W涂层的最新研究进展。
By the end of September 2006, the engineering commissioning of the Experimental Advanced Superconducting Tokamak (EAST) was completed and the first H2 plasma was achieved with stainless steel as the plasma-facing material (PFM). In the following phases, with gradual increase in the heating power, the EAST divertor targets have to handle expected heat loads up to ∼10 MW m−2. The PFMs to be employed include doped graphite and W coatings. The former will be used to cover the whole plasma-facing surface in the first phase, and then the latter applied to replace the graphite tiles gradually in the second phase, and finally a whole W plasma-facing surface will be expected. Graphite has been studied for many years and contributed greatly to the HT-7 to achieve long pulses of some 100 s. The W coatings are being developed and the latest R&D development is reported in the paper.