平面型 W-ZrC/Cu 高热通量模型的内部高温烧蚀现象及机理分析

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-08-17 DOI:10.1016/j.fusengdes.2024.114630
Qianqian Lin , Lei Cao , Le Han , Xianke Yang , Chongfeng Zhong , Damao Yao , Zhuoming Xie , Rui Liu
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引用次数: 0

摘要

作为一种面向等离子体的材料(PFM),W-ZrC 是未来聚变反应堆岔流器的理想候选材料。为了验证 W-ZrC 的可行性,我们在一个综合实验平台上进行了高热通量(HHF)试验。实验中观察到了罕见的内部烧蚀失效模式。根据烧蚀坑的形状和大小,通过热模拟分析确定了烧蚀的原因和机理。可以得出的结论是,热通量的突然大幅增加加上水流量的减少会导致散热器内部发生热烧蚀。此外,烧蚀坑的尺寸与施加热通量的区域有关。总之,内部烧蚀会对分流器造成严重后果。
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Inside high-temperature ablation phenomenon and analysis of mechanism of a flat-type W–ZrC/Cu high heat flux mock-up

As a plasma-facing material (PFM), W–ZrC is a promising candidate for the divertor in future fusion reactors. To verify the feasibility of W–ZrC, a high heat flux (HHF) test was conducted on a comprehensive experimental platform. A rare internal ablation failure mode was observed during the experiment. Considering the internal ablation phenomenon during the test, the measured data of the test platform were analyzed to predict an ablation time of 12 s. Based on the shape and size of the ablation pit, the cause and mechanism of ablation were determined using thermal simulation analysis. It can be concluded that a sudden and significant increase in heat flux combined with reduced water flow can cause thermal ablation to occur within the heat sink. Furthermore, dimensions of the ablation pit are related to the area in which the heat flux is imposed. In sum, internal ablation can have serious consequences for the divertor.

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来源期刊
Fusion Engineering and Design
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.
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