Thermal analysis of the W/Cu flat-type component used as lower divertor target in EAST

作者：Chunyu He, Dahuan Zhu, Baoguo Wang, Changjun Li, Binfu Gao, Yang Wang, Yi Li, Chuannan Xuan, Wenxue Fu, Rong Yan, Guoliang Xu, Rui Ding, Junling Chen · 发表于：Nuclear Materials and Energy · 年份：2025 · DOI：10.1016/j.nme.2025.101954 · 被引用次数：2 · 研究领域：Fusion materials and technologies、Magnetic confinement fusion research、Nuclear Materials and Properties

The tungsten-copper (W/Cu) flat-type component is a promising candidate for plasma-facing components, praised for its flexible heat sink design and cost-effective fabrication. It is considered for the ITER divertor dome section and holds potential for divertor targets for future fusion devices. Since 2021, three types of ITER-like W/Cu flat-type components with chamfer angles of 2.40°, 3.76°, and 5.19° have been installed and tested on the outer horizontal target of the lower divertor in EAST. During plasma operations, some W/Cu flat-type components experienced cracking, melting and exfoliation of tungsten, causing plasma disruptions and even the termination of experiments. To address this, this study uses Fluent to evaluate the melting thresholds of these components based on simulations that consider actual conditions. The key findings are summarized: Firstly, only certain W plates can reach high temperatures because the in-situ heat flux is localized, explaining why damage often occurs only on some specific plates. During leading-edge events, the highest temperatures for both W and oxygen-free copper (OFC) occur near the sides, but W’s maximum temperature is at the edge, while OFC’s is near the edge. The high-temperature area for OFC is larger than that for W, resulting in a more uniform temperature distribution. Secondly, for components with chamfer angles of 3.76° and 5.19°, the heat flux required for OFC to melt is always lower than that for W, meaning OFC melts first. F...