核电站预应力混凝土安全壳结构是核反应堆的最后一道保护屏障,随时间的增长,混凝土材料和预应力系统以及钢构件部分都会发生老化问题。由于安全壳的安全级别、结构形式与使用环境的特殊性,使其老化问题不同于普通结构,存在特殊的导致结构老化的机理。通过对美国核管会(NRC)、国际原子能协会(IAEA)等机构相关资料的调研,结合国内多个核电站安全壳的现场老化探测结果,对核电站安全壳的老化机理进行了分类归纳,分为混凝土材料部分、预应力系统部分与钢构件部分,并对老化机理进行分析,对国内外先进的老化探测手段进行介绍。 The prestressed concrete containment structure of nuclear power plant is the last protective barrier of nuclear reactors. Over time, aging problems will occur in concrete materials and prestressing systems as well as steel components. Due to the safety level of the containment, the structure and the particularity of the use environment, the aging problem is different from the ordinary structure, and there is a special mechanism leading to structural aging. Based on the investigation of relevant data from NRC and IAEA, combined with the on-site aging detection results of multiple nuclear power stations in China, the aging mechanism of containment in nuclear power stations is classified into Concrete material part, prestressing system part and steel component part, and analyzes the aging mechanism, introduces the advanced aging detection methods at home and abroad.