大亚湾核电厂反应堆厂房地震响应分析评估

Analysis and Evaluation of Seismic Response of Reactor Building for Daya Bay Nuclear Power Plant

大亚湾核电厂核反应堆厂房的抗震分析基本沿用法国M310型机组的标准分析方法(RCC-G),对于土-结构相互作用(SSI)效应的考虑,采用简化的阻抗函数法。本文拟采用新的相对精确的基于Green函数的三维连续半空间边界子结构法考虑地基岩土的作用,进行SSI耦合系统的地震响应分析计算,并将计算的楼层反应谱(FRS)同设计值进行比较,对设计方法及其结果的趋向性(偏于安全／或不安全)进行评估。结果表明,与基于三维连续半空间边界子结构法的计算结果相比较,电厂设计偏于安全。

Daya Bay NPP has been operating safely and stably over 10 years since 1994, and its＇ seismic analysis of nuclear island was in accordance with the approaches in RCC-G standard for the model M310, in which the Simplified Impedance Matrix Method （SIMM） was employed for the consideration of SSI. Thanks to the rapid progress being made in upgrading the evaluation technology and the capability of data processing systems, methods and software tools for the SSI analysis have experienced significant development all over the world. Focused on the model of reactor building of the Daya Bay NPP, in this paper the more sophisticated 3D half-space continuum impedance method based on the Green functions is used to analyze the functions of the soil, and then the seismic responses of the coupled SSI system are calculated and compared with the corresponding design values. It demonstrates that the design method provides a set of conservatively safe results. The conclusions from the study is hopefully to provide some important references to the assessment of seismic safety margin for the operating NPPs.