连续碳化硅纤维增强碳化硅陶瓷基复合材料在先进核能领域的发展研究  

Development Strategy of Continuous Silicon-Carbide-Fiber-Reinforced Silicon Carbide Ceramic Matrix Composites in the Field of Advanced Nuclear Energy

作　　者：罗瀚 陈博文 黄鹤飞[2] 王苍龙[3] 姜志忠[4] 周海山 陈向阳 王晓敏[7] 张瑞谦[7] 董绍明[1] Luo Han;Chen Bowen;Huang Hefei;Wang Canglong;Jiang Zhizhong;Zhou Haishan;Chen Xiangyang;Wang Xiaomin;Zhang Ruiqian;Dong Shaoming(Shanghai Institute of Ceramics,Chiese Academy of Sciences,Shanghai 201899,China;Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China;Institute of Modern Physics,Chinese Academy of Sciences,Lanzhou 730000,China;Institute of Nuclear Energy Safety Technology,Hefei Institutes of Physical Science,Chinese Academy of Sciences,Hefei 230031,China;Institute of Plasma Physics,Hefei Institutes of Physical Science,Chinese Academy of Sciences,Hefei 230031,China;Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.,Shanghai 200233,China;Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国科学院上海硅酸盐研究所,上海201899 [2]中国科学院上海应用物理研究所,上海201800 [3]中国科学院近代物理研究所,兰州730000 [4]中国科学院合肥物质科学研究院核能安全技术研究所,合肥230031 [5]中国科学院合肥物质科学研究院等离子体物理研究所,合肥230031 [6]上海核工程研究设计院股份有限公司,上海200233 [7]中国核动力研究设计院,成都610213

出　　处：《中国工程科学》2024年第3期53-62,共10页Strategic Study of CAE

基　　金：中国工程院咨询项目“关键材料体系自立自强战略研究”(2022-PP-02)。

摘　　要：先进核能系统的发展对核材料在多场耦合极端环境中的服役稳定性提出了更高要求。连续碳化硅纤维增强碳化硅(SiCf/SiC)陶瓷基复合材料具有低密度、高温力学性能优异、抗腐蚀、耐辐照等优点,且在外力作用下呈现“假塑性”断裂行为,被视为先进核能系统中极具应用前景的新型结构材料。本文首先从材料级、构件级、服役性能三个层面系统总结了核用SiCf/SiC复合材料的基础研究体系,分析了美国、法国、日本等传统核电强国,其他新兴核电国家和我国在核用SiCf/SiC复合材料领域的发展趋势,梳理了我国核用SiCf/SiC复合材料在原材料、数据积累和专利标准等方面存在的问题与发展面临的挑战,针对性地提出了相关措施与建议,包括加强材料制备技术研发、发展研发新范式、强化“产学研用”合作关系、在坚持以我为主的基础上加强国际交流等,以期为我国核用SiCf/SiC复合材料领域的研究方向及决策制定提供参考。The development of advanced nuclear energy systems imposes stringent requirements on the service stability of nuclear materials under extreme environments characterized by multiple stressors.Continuous silicon-carbide-fiber-reinforced silicon carbide(SiCf/SiC)ceramic matrix composites possess advantages such as low density,excellent high-temperature mechanical properties,corrosion resistance,and irradiation tolerance.Furthermore,SiCf/SiC composites demonstrate a pseudo-ductile fracture behavior under external forces,positioning them as highly promising structural materials for advanced nuclear energy systems.This study systematically summarizes the fundamental research framework on nuclear-grade SiCf/SiC composites at the material,component,and service performance levels.It also analyzes the developmental trends in this field among traditional nuclear powerhouses such as the United States,France,and Japan,as well as in other emerging nuclear energy countries and China.Furthermore,the study identifies existing issues and challenges faced by China’s nuclear-grade SiCf/SiC sector in terms of raw materials,data accumulation,and patent standards,and proposes targeted measures and suggestions:(1)strengthening the research and development of material preparation technologies,(2)developing a new paradigm of research and development,(3)reinforcing the industry-universityresearch-application cooperation,and(4)enhancing international exchanges on the basis of maintaining independence.The aim of the study is to provide guidance and reference for the research directions and policy-making in China’s nuclear-grade SiCf/SiC sector.

关 键 词：先进核能系统用材 SICF/SIC复合材料 材料设计 服役性能 

分 类 号：TB33[一般工业技术—材料科学与工程]