Tungsten coated tiles for KSTAR PFC upgrade

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-09 DOI:10.1016/j.fusengdes.2025.115055

Hee-Jae Ahn , Hyun-Ki Park , Koung Moon Kim , Kwang Pyo Kim , Kaprai Park , Sungjin Kwon , Young Min Park , E. Grigore , Si-Woo Yoon

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引用次数: 0

Abstract

The KSTAR plasma facing components (PFCs) include graphite tiles and metal back-plates. Since their installation in 2010, the PFCs have effectively fulfilled their mission. KSTAR's PFCs are being upgraded to create a fully tungsten (W) environment, designed to handle the increased thermal loads associated with maximum heating power and extended pulse lengths. Tungsten's high melting temperature, its heaviness, brittleness, and costliness led to the consideration of W-coated carbon tiles as a viable compromise for the limiters and passive stabilizer. The newly designed inboard limiter tiles feature a W-coated rounded surface facing the plasma, twice the size to mitigate leading-edge effects. Standard tile types were minimized to save on manufacturing and maintenance costs. Approximately 1500 graphite tiles were newly manufactured due to surface and radiation contamination. These tiles were coated with 13 μm W and 2 μm Mo using Romania's NILPRP PVD CMSII, a technique also applied to JET, ASDEX-U, and WEST PFCs. The Mo layer enhances adhesion by addressing thermal expansion mismatches between graphite and W. The W coating was completed in early 2024, and the installation of W-coated tiles is scheduled before the 2026 campaign.

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用于KSTAR PFC升级的钨涂层瓷砖

KSTAR等离子体表面组件（pfc）包括石墨瓦和金属背板。自2010年成立以来，pfc有效地完成了使命。KSTAR的pfc正在进行升级，以创建一个全钨(W)环境，旨在处理与最大加热功率和延长脉冲长度相关的增加的热负荷。钨的高熔点、重、脆和昂贵导致钨涂层碳瓦作为限制剂和被动稳定剂的可行折衷方案。新设计的板内限制瓦具有面向等离子体的w涂层圆形表面，尺寸为两倍，以减轻前缘效应。标准瓷砖类型被最小化，以节省制造和维护成本。由于表面和辐射污染，新生产了大约1500块石墨瓦。这些瓷砖采用罗马尼亚的NILPRP PVD CMSII涂覆13 μm W和2 μm Mo，该技术也适用于JET， ASDEX-U和WEST pfc。Mo层通过解决石墨和W之间的热膨胀不匹配来增强附着力。W涂层于2024年初完成，W涂层瓷砖的安装计划在2026年竞选之前完成。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.