新一代核压力容器候选材料SA508Gr.4N钢的研究进展  

Research Progress of New Generation Candidate Material SA508Gr.4N Steelfor Nuclear Pressure Vessel

作　　者：李林泽 谢常胜 代鑫 田亚强 陈连生 LI Linze;XIE Changsheng;DAI Xin;TIAN Yaqiang;CHEN Liansheng(College ofMetallurgy and Energy,North China University ofScience and Technology,Tangshan 063210,China;Technology Center,Zenith Steel Group(Nantong)Co.,Ltd.,Nantong 226156,China;Hebei Iron and Steel Laboratory,North China University ofScience 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]中天钢铁集团(南通)有限公司技术中心,江苏南通226156 [3]华北理工大学河北钢铁实验室,河北唐山063210

出　　处：《热加工工艺》2025年第4期1-10,15,共11页Hot Working Technology

基　　金：河北省自然科学基金项目(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)。

摘　　要：从SA508Gr.4N钢的工艺流程出发,对锻造工艺进行了总结,以便得到均匀细小的显微组织。阐述了合金元素、冷却速率及热处理参数等因素对SA508Gr.4N钢的力学性能的影响机理。结合核压力容器的服役环境,对SA508Gr.4N钢的疲劳性能进行了总结。详细分析了显微组织演化、M/A岛和碳化物等对SA508Gr.4N钢疲劳性能、疲劳裂纹萌生及疲劳裂纹扩展的影响机理。总结了SA508Gr.4N钢抗辐照硬化和脆化的影响机理,以及耐腐蚀性能。展望了核压力容器材料的发展方向和要进一步研究的内容,以期提高核压力容器服役寿命,确保在恶劣环境下安全运行。Starting from the process flow of SA508Gr.4N steel,the forging process was summarized in order to obtain SA508Gr.4N steel with uniform fine microstructure.The influence mechanisms of alloying elements,cooling rate and heat treatment parameters on the mechanical properties of SA508Gr.4N steel were described.The fatigue properties of SA508Gr.4N steel was summarized by combining the service environment of nuclear pressure vessel.The effects of microstructure evolution,M/A islands and carbides on the fatigue properties,fatigue crack initiation and fatigue crack propagation of SA508Gr.4N steel were analyzed in detail.The influence mechanisms of irradiation hardening and embrittlement and corrosion resistance of SA508Gr.4N steel were summarized.The development direction and further research contents of nuclear pressure vessel materials were prospected in order to improve the service life and ensure its safe operation in harsh environment.

关 键 词：核压力容器 SA508Gr.4N钢 力学性能 疲劳性能 辐照性能 

分 类 号：TG142.1[一般工业技术—材料科学与工程]