李林泽,代鑫,张源,周琳君,陈连生,田亚强

• 1:华北理工大学冶金与能源学院
• 2:华北理工大学河北钢铁实验室

摘要(Abstract)：

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。

关键词(KeyWords)： 核压力容器;SA508Gr.3钢;热处理工艺;热时效;辐照;疲劳

Abstract:

Keywords:

基金项目(Foundation): 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)

作者(Author): 李林泽,代鑫,张源,周琳君,陈连生,田亚强

DOI: 10.13289/j.issn.1009-6264.2023-0550

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