FeCrV-based multi-component alloys with the auspicious potential as advanced nuclear energy materials: A comprehensive review

IF 6.3 2区 材料科学 Q2 CHEMISTRY, PHYSICAL
Zhi-hao Xu , Shang Xu , Fang-qian Zhao , Yong Zhang , Qian Zhan
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Abstract

Multi-component alloys (MCAs) significantly broaden the spectrum of alloy design, opening up innovative pathways for enhancing material performance. Over the past decade, extensive global research efforts have elucidated the outstanding mechanical properties and the potential for exceptional corrosion and irradiation resistance exhibited by MCAs. FeCrV-based MCAs with body-centered cubic (BCC) structures, as an emerging MCA family, are regarded as having the auspicious potential for high-temperature applications within advanced nuclear reactors. However, the stringent reactor conditions including elevated temperatures, severe irradiation damage, high mechanical stress, and complex corrosive media, necessitate a thorough assessment of the materials’ properties to ensure their reliable performance in nuclear reactors. This review synthesizes the contemporary advancements in FeCrV-based MCAs, encompassing aspects such as synthesis methodologies, mechanical properties, strengthening mechanisms, thermal stability, thermal properties, irradiation tolerance, and corrosion resistance. Despite the fact that the application of FeCrV-based MCAs in nuclear contexts remains in its incipient stage, the extant research outcomes furnish a solid foundation for comprehending and anticipating the behaviors of materials with varying compositions and microstructures. Further exploration into the relevant mechanisms and the comprehensive assessment of material microstructures and properties under conditions akin to the reactor environment are imperative for advancing our understanding. Additionally, a critical refinement of potential candidates is essential for subsequent in-depth evaluation and engineering validation.
具有先进核能材料潜力的铁钒基多组分合金综述
多组分合金(MCAs)显著拓宽了合金设计的范围,为提高材料性能开辟了创新途径。在过去的十年中,广泛的全球研究工作已经阐明了MCAs出色的机械性能以及具有特殊的耐腐蚀性和耐辐照性的潜力。具有体心立方(BCC)结构的基于fecrv的MCA作为一个新兴的MCA家族,被认为在先进核反应堆的高温应用中具有良好的潜力。然而,苛刻的反应堆条件,包括高温、严重的辐照损伤、高机械应力和复杂的腐蚀性介质,需要对材料的性能进行彻底的评估,以确保其在核反应堆中的可靠性能。本文综述了基于fecrv的MCAs的最新进展,包括合成方法、力学性能、强化机制、热稳定性、热性能、辐照耐受性和耐腐蚀性等方面。尽管基于fecrv的MCAs在核环境中的应用仍处于起步阶段,但现有的研究成果为理解和预测不同成分和微观结构的材料的行为提供了坚实的基础。进一步探索相关机制,并在类似于反应堆环境的条件下全面评估材料的微观结构和性能,对于提高我们的理解是必不可少的。此外,对潜在候选物进行关键的细化对于后续的深入评估和工程验证至关重要。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Journal of Alloys and Compounds
Journal of Alloys and Compounds 工程技术-材料科学:综合
CiteScore
11.10
自引率
14.50%
发文量
5146
审稿时长
67 days
期刊介绍: The Journal of Alloys and Compounds is intended to serve as an international medium for the publication of work on solid materials comprising compounds as well as alloys. Its great strength lies in the diversity of discipline which it encompasses, drawing together results from materials science, solid-state chemistry and physics.
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