원전 구조물-기기 상호작용이 기기 지진응답에 미치는 영향 연구
A Study on the Effects of Nuclear Power Plant Structure-Component Interaction in Component Seismic Responses
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초록
원자력발전소 기기 내진설계 및 지진해석은 비연계모델을 대상으로 수행된다. 그러나 이러한 비연계해석은 실제 구조물-기기 간상호작용 등의 실제 현상을 모사할 수 없기 때문에 연계해석에 비하여 정확하지 못한 결과를 발생시키게 된다는 한계를 가진다. 이러한 배경 아래 이 연구는 실제 원전 격납건물 구조물 및 관련 부계통을 대상으로 질량비와 고유진동수비를 고려하여 지진 연계해석과비연계해석을 수행하고, 이를 바탕으로 부계통에서의 응답을 비교 분석하였다. 결과적으로 지진 연계해석 결과가 비연계해석 결과보다 대다수 작은 값을 주는 것을 확인하였다. 이러한 결과는 기존 연구인 단순한 연계모델에 대한 해석 결과와 유사하지만, 부계통 응답차이는 훨씬 더 두드러지게 나타나는 것을 확인하였다. 또한, 이는 지진파의 입력 주파수의 영향보다는 부계통의 설치위치에 영향을받는 것으로 확인되었다. 마지막으로 비연계 및 연계 지진해석의 차이가 부계통의 질량비가 크고, 고유진동수가 거의 일치하는 영역에서 발생하는 이유는 이 영역에서 주계통과 부계통 동적 상호작용이 크게 나타나기 때문인 것으로 보인다.
Abstract
Seismic design and analysis of nuclear power plant components are performed based on an decoupled model. However, this decoupledanalysis has a limitation in that it generates inaccurate results compared to the coupled analysis because it cannot simulate actual phenomenasuch as the interaction between structures and components. Thus, this study performed seismic coupled and decoupled analysis on an existingnuclear containment structure and related components, considering the mass and natural frequency ratios. And based on these results,comparative analyses of responses of components were conducted. Consequently, the seismic coupled analysis result generally gave a smallervalue than the decoupled analysis result. These results were similar to the analysis results for the simple coupled model, which was an existingstudy, but the difference in component responses was much more pronounced. Also, this was influenced by the installation location of thecomponent rather than the influence of the input frequency of the input seismic motions. Finally, the difference between the decoupled andcoupled seismic analysis occurred in the region where the mass ratio of the components was large, and the natural frequencies were almostsimilar due to the considerable dynamic interaction between the structure and the component in this realm.
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