用于实现钨合金高强度和热稳定性的纳米级高熵氧化物分散体

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

Fusion Engineering and Design Pub Date : 2024-11-13 DOI:10.1016/j.fusengdes.2024.114712

M.L. Yu , Z.M. Xie , X.F. Xie , W.B. Jiang , X. Dang , Z.L. Huang , Y.G. Zhang , R. Liu , X.B. Wu , C.S. Liu , Q.F. Fang

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引用次数: 0

摘要

本文利用机械球磨和火花等离子烧结技术制备了纯 W、W-0.8wt % (HfNbMoZrTi)B2 和 W-1.0wt % (HfNbMoZrTi)B2（分别简称为 W-0.8HEB 和 W-1.0HEB）材料。研究了添加 HEB 对微观结构、机械性能和热导率的影响。W-0.8HEB 材料具有约 506 Hv 的高硬度和 1774 MPa 的高屈服强度，超过了纯 W 和 W-1.0HEB 材料。此外，W-0.8HEB 的再结晶温度高达 1800 °C，高于大多数报道的 W 材料。HRTEM 结果显示，(HfNbMoZrTi)B2 和 O 杂质在高温烧结过程中发生原位反应，形成了高度稳定的纳米级溪石结构 (HfNbMoZrTi)O2 颗粒。这种反应降低了 W 中的间隙 O 浓度，从而提高了机械性能和热稳定性。

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Nano-sized high-entropy oxide dispersoids for achieving high strength and thermal stability in tungsten alloys

In this paper, pure W, W-0.8wt % (HfNbMoZrTi)B₂ and W-1.0wt % (HfNbMoZrTi)B₂ (abbreviated as W-0.8HEB and W-1.0HEB, respectively) materials were fabricated using mechanical ball milling and spark plasma sintering. The effects of HEB addition on the microstructure, mechanical properties, and thermal conductivity were studied. The W-0.8HEB materials demonstrated a high hardness of approximately 506 Hv and a high yield strength of 1774 MPa, surpassing those of pure W and W-1.0HEB. Additionally, the recrystallization temperature of W-0.8HEB reached up to 1800 °C, higher than that of most reported W materials. HRTEM results revealed highly stable, nanosized, brookite-structured (HfNbMoZrTi)O₂ particles formed by an in-situ reaction between (HfNbMoZrTi)B₂ and O impurities during high-temperature sintering. This reaction diminishes the interstitial O concentration in W, resulting in enhanced mechanical properties and thermal stability.

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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.