Enhancing the strength and toughness of high-Cr high-Si F/M steel for nuclear power applications by optimizing hot rolling deformation amount

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-06-01 Epub Date: 2025-03-28 DOI:10.1016/j.nucengdes.2025.114006
Yingqi Liu , Qianfu Pan , Runkun Shi , Xiaochang Xu
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Abstract

High-Cr high-Si ferritic/martensitic (F/M) steel has emerged as a key candidate material for nuclear power equipment due to its excellent radiation resistance and corrosion resistance. However, the high Cr and Si contents lead to a greater proportion of ferrite, which can reduce the material’s strength and toughness and affect the type and distribution of second phase particles, thereby limiting its application in nuclear industry environments. This study optimizes the microstructure of High-Cr high-Si F/M steel by adjusting the hot rolling deformation amount, achieving the best match of strength and toughness. The mechanisms of strength enhancement are also investigated to clarify the relationship between microstructure and performance. The results show that a deformation amount of 40% during hot rolling yields the best overall performance, characterized by a low ferrite content, fine MX-type carbides with a high number density, and excellent strength and toughness. Rolling at the austenitization temperatures significantly improves the material’s comprehensive properties, providing strong support for the application of high-Cr high-Si F/M steel in the nuclear power sector.
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通过优化热轧变形量提高核电用高铬高硅F/M钢的强度和韧性
高铬高硅铁素体/马氏体(F/M)钢因其优异的耐辐射和耐腐蚀性能而成为核电设备的关键候选材料。然而,高Cr和Si含量导致铁素体比例较大,会降低材料的强度和韧性,影响第二相颗粒的类型和分布,从而限制了其在核工业环境中的应用。本研究通过调整热轧变形量来优化高铬高硅F/M钢的组织,实现强度和韧性的最佳匹配。研究了强度增强的机理,阐明了微观组织与性能之间的关系。结果表明:热轧变形量为40%时,合金的综合性能最佳,铁素体含量低,mx型碳化物细,数量密度高,强度和韧性优异。在奥氏体化温度下轧制可显著提高材料的综合性能,为高铬高硅F/M钢在核电领域的应用提供有力支持。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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