核压力容器用SA508Gr.3钢的研究进展  

Research progress of SA508Gr.3 steel for nuclear pressure vessels

作　　者：李林泽 代鑫 张源 周琳君 陈连生 田亚强 LI Lin-ze;DAI Xin;ZHANG Yuan;ZHOU Lin-jun;CHEN Lian-sheng;TIAN Ya-qiang(College of Metallurgy and Energy,North China University of Science and Technology,Tangshan 063210,China;Hebei Iron and Steel Laboratory,North China University of Science and Technology,Tangshan 063210,China)

机构地区：[1]华北理工大学冶金与能源学院,河北唐山063210 [2]华北理工大学河北钢铁实验室,河北唐山063210

出　　处：《材料热处理学报》2024年第9期27-38,共12页Transactions of Materials and Heat Treatment

基　　金：河北省自然科学基金(E2022209049);唐山市科技计划项目(22130206G);河北省高等学校科学研究项目(QN2023086);冶金与能源学院青年教师发展基金(YJY20244438)。

摘　　要：核反应堆压力容器是核电站重要组件且具有在全寿命周期内不可更换的特殊性。第二代核压力容器用钢在其焊缝中发现了再热裂纹,已不能够满足使用需求。因此,在此基础上通过添加Mn元素,减少Mo和Cr元素改进设计了SA508Gr.3钢,它具有高强度、高韧性和低辐照脆化敏感性等特点,目前广泛应用于核电压力容器、蒸发器和稳压器等核心构件。本文总结了SA508Gr.3钢的研究进展,重点介绍了合金元素、热处理工艺对其显微组织和力学性能的影响,并详细介绍了SA508Gr.3钢的抗辐照性能。根据核压力容器的服役环境,详细分析了热时效对SA508Gr.3钢显微组织及力学性能的影响机理。随后,总结了显微组织演化对其疲劳性能、疲劳裂纹萌生及疲劳裂纹扩展的影响机制。最后,展望了核压力容器的发展方向和需要进一步研究的内容,为提高SA508Gr.3钢的综合性能和研发下一代核电用钢提供参考。Nuclear reactor pressure vessel is an important component of nuclear power plant and has the special characteristic of being non replaceable throughout its entire life cycle.The second generation of steel for nuclear pressure vessels cannot meet the use requirements due to reheat cracks found in the weld.Therefore,based on this,the SA508Gr.3 steel is improved and designed by adding Mn elements and reducing Mo and Cr elements.It has the characteristics of high strength,high toughness and low radiation embrittlement sensitivity,and is currently widely used in core components such as nuclear power pressure vessels,evaporators and regulators.This article summarizes the research progress of the SA508Gr.3 steel,focusing on the effects of alloying elements and heat treatment processes on its microstructure and mechanical properties,and provides a detailed introduction to the radiation resistance of the SA508Gr.3 steel.Based on the service environment of nuclear pressure vessels,the influence mechanism of thermal aging on the microstructure and mechanical properties of the SA508Gr.3 steel is analyzed in detail.Subsequently,the influence mechanism of microstructure evolution on its fatigue performance,fatigue crack initiation and fatigue crack propagation is summarized.Finally,the development direction and further research needed for nuclear pressure vessels are discussed,providing reference for improving the comprehensive performance of the SA508Gr.3 steel and developing the next generation of nuclear power steel.

关 键 词：核压力容器 SA508Gr.3钢 热处理工艺 热时效 辐照 疲劳 

分 类 号：TG142.4[一般工业技术—材料科学与工程]