Overview of R&D on Plasma-Facing Materials and Components in China
Overview of R&D on Plasma-Facing Materials and Components in China
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DOI：
10.13182/fst12-a14104
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发表时间：
2012-07
影响因子：
0.9
通讯作者：
G. Luo;Q. Li;J. Chen;X. Liu;W. Liu;Z. Zhou;D. Yao
中科院分区：
文献类型：
--
作者：
G. Luo;Q. Li;J. Chen;X. Liu;W. Liu;Z. Zhou;D. Yao
摘要中国科学院等离子体物理研究所于2010年启动了一个在实验先进超导托卡马克（EAST）上用几年时间实现具有ITER类等离子体面向组件（PFC）结构的W/Cu偏滤器的项目。ITER类配置应能承受粒子和功率的快速增加对偏滤器的冲击，并证明ITER设计在实际长脉冲托卡马克等离子体下的可行性。该项目不仅可以帮助EAST实验，还可以实现ITER PFC技术验证，并为ITER全W偏滤器的核阶段提供及时的答案。西南物理研究所（SWIP）将拥有10%的增强热通量（EHF）型第一壁（FW）采购包。根据ITER级材料规范，包括真空热压（VHP）-Be，CuCrZr合金和316 L（N）-IG锻造块，已经开发和表征了材料，并且已经通过热等静压（HIP）对VHP-Be瓦连接到CuCrZr散热器进行了鉴定测试。一些中国大学已经开始探索新的W材料等级，例如，碳化物或氧化物弥散强化细晶W材料，并研究了它们在高热负荷下的行为。
Abstract A project to realize, in several years, a W/Cu divertor on Experimental Advanced Superconducting Tokamak (EAST) with ITER-like plasma-facing component (PFC) configuration was launched at Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) in 2010. The ITER-like configuration should withstand the rapid increase in particle and power impact onto the divertor and demonstrate the feasibility of the ITER design under practical long-pulse tokamak plasmas. The project could help not only EAST experiments, but also realize ITER PFC technology validation and bring answers in a timely manner for the ITER full-W divertor for the nuclear phase. Southwest Institute of Physics (SWIP) will have 10% of the first wall (FW) procurement package of the enhanced heat flux (EHF) type. The materials have been developed and characterized according to the ITER-grade material specifications, including vacuum hot pressing (VHP)-Be, CuCrZr alloy, and 316L(N)-IG forged blocks, and qualification testing of the VHP-Be tiles joining to the CuCrZr heat sink by hot isostatic pressing (HIP) has been carried out. Some Chinese universities have started to explore new grades of W materials, e.g., carbide or oxide dispersion strengthened fine grain W materials, and investigated their behavior under high heat loads.