核电站安全壳老化机理分析与探测方法

AGEING ANALYSIS AND AGEING DETECTING OF CONCRETE CONTAINMENT BUILDINGS FOR NUCLEAR POWER PLANT

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 prestressing concrete containment buildings for nuclear power plant is the last barrier of the nuclear reactor,as time goes on,the concrete,prestressing system and the steel components ages.Because the concrete containment has the special safety property,special structure form and special environment of use,there goes special ageing mechanism.It was researched the related rules of NRC and IAEA,listed and assorted the ageing mechanisms,mainly assorted as the concrete part,prestressing system part and the steel components part.Then it was analysed the ageing mechanism,introduced the advanced detecting measures of ageings.