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考虑SSI效应的核电站厂房楼层反应谱对比分析
FRS comparative analysis of the nuclear power plant considering SSI effect
【摘要】 在集总参数表征的场地动阻抗框架内,国内外主要核电厂抗震设计规范均推荐单一常系数弹簧-阻尼器并联体系表征均质场地动力模型。结合土-结构相互作用数值分析的最新发展,本文以CPR1000型反应堆厂房的集中质量简化模型作为研究对象,基于ASCE4-98规范、RCC-G规范、集10参数等适用于均质场地的集总参数地基模型以及适用于非均质复杂场地的粘弹性人工边界场地模型,开展了直接法和阻抗子结构法两种时程分析方法的对比研究,并将得到的楼层加速度反应谱与SASSI程序计算结果进行对比,互相验证了不同地基动力数值模型以及计算方法的有效性,对于评价核电厂地基适应性具有一定的指导与参考意义。
【Abstract】 Background: In the framework of lumped-parameter numerical models,the traditional soil dynamic impedance models,recommended by the main international seismic design codes of the nuclear power plant,are only expressed by a single parallel connection system of spring and damper.Purpose: In order to combine the recent development of soil-structure interaction analysis.Methods: Comparative study of both the direct method and substructure method history analysis is carried out based on the lumped parameter models recommended by seismic design codes of ASCE4-98,RCCG which are both applicable to the homogeneous site and also massless foundation model and viscous-spring artificial boundary model of especially fit for the numerical simulation of non-homogeneous site.Results: Finally,by taking the analysis of FRS for a certain CPR1000 reactor plant as an example,comparison analyses of homogeneous and inhomogeneous layer site conditions for various soil dynamic numerical models above-mentioned are carried out.In addition,the calculated results are compared to that of SASSI program.It can be concluded that the calculation results are similar based on different methods.Conclusions: This paper validates the applicability of different soil dynamic numerical models mentioned above and will provide some reference and guidance significance in the aspect of evaluation the seismic suitable for the site of nuclear power plant.
- 【文献出处】 核技术 ,Nuclear Techniques , 编辑部邮箱 ,2013年04期
- 【分类号】TM623.1
- 【被引频次】17
- 【下载频次】211