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某核电站厂房由于工艺需要进行设计改进,作为翻版设计的核电站需要评估此设计改进厂房的地基适宜性。基于美国ASCE 4-98《核电结构的地震安全性分析及解说》推荐的集总参数地基模型,针对一系列的均质场地,计算了设计改进厂房典型楼层的反应谱,评估此设计改进对该核电站厂房地基适宜性的影响。计算结果表明:对于剪切波速大于1 500 m/s的均质场地,此设计改进厂房是完全适宜的。
A nuclear power plant due to process design needs improvement, as a replica of the design of the nuclear power plant needs to evaluate the design of the foundation to improve the plant’s suitability. Based on the lumped parameter foundation model recommended by ASCE 4-98 “Earthquake Safety Analysis and Interpretation of Nuclear Power Structures”, the response spectrum of a typical floor of an improved plant was calculated for a series of homogeneous sites. Influence of Subgrade Suitability of Nuclear Power Plant. The calculation results show that the design of the plant is totally suitable for the homogeneous site with shear wave velocity greater than 1 500 m / s.