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

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

Nuclear Engineering and Design Pub Date : 2025-03-28 DOI:10.1016/j.nucengdes.2025.114006

Yingqi Liu , Qianfu Pan , Runkun Shi , Xiaochang Xu

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引用次数: 0

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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来源期刊

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.