核电厂抗震系统的耦合性分析  

Coupling Analysis of the Seismic Systems in Nuclear Power Plants

作　　者：姚伟达[1] 廖剑晖[1] 张明[1] 姚彦贵[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核安全》2015年第2期87-94,共8页Nuclear Safety

基　　金：国家科技重大专项大型先进压水堆及高温气冷堆核电站CAP1400蒸汽发生器及其关键部件性能试验;课题编号2011ZX06002-020

摘　　要：核电厂设施是由构筑物、管系、设备和部件(SSCs)等组成的十分复杂的系统,抗震I类设施的抗震设计分析是在安全停堆地震(SSE)设计基准事故下确保核电厂安全的重要措施之一。为了将核电厂中复杂的构筑物、系统、部件的抗震分析开展得全面、可靠又深入,最有效和通用的方法是在抗震分析中将整个构筑物、系统、部件合理地分解成若干抗震主系统和子系统。本文从将主、子系统简化为二自由度的基本振动原理出发,论证主、子系统解耦的条件,证实了美国核管会安全分析报告标准审查大纲3.7.2中提出解耦条件的依据。同时又论证了耦合系统中将子系统独立解耦并进行抗震分析时所必须满足的必要条件。本文的结论可为核电厂抗震设计分析工程师以及安全评审人员提供一个重要的设计分析及评审依据。Facilities in nuclear power plants are complicated systems consisting of structures, piping systems, equipments and components （ SSCs ）. Seismic designs and analyses for Seismic Category I facilities are carried out as an important procedure to ensure the safety of nuclear power plants under SSE design basis accidents. In order to perform the seismic analyses for complex SSC systems more comprehensively, reliably and thoroughly, the most effective and consistent manner is to suitably resolve the total seismic system into several main and sub systems. Starting from the basic principles of vibrations, where the main and sub sys- tems are simplified as a two-degree-of-freedom system, this paper deduces the decoupling conditions for the main and sub systems and verifies the basis of decoupling conditions proposed in the Standard Review Plan 3.7.2. The requirements are presented for the decoupling of sub systems from the coupled system. Conclusions drawn in this paper provide the engineers of seismic design and analysis, as well as safety reviewers, with an important criterion for their designs, analyses and reviews.

关 键 词：核电厂 抗震系统 抗震分析 耦合与解耦 

分 类 号：TL35[核科学技术—核技术及应用]