scholarly journals Seismic Response Analysis of Isolated Nuclear Power Plants with Friction Damper Isolation System

2014 ◽  
Vol 7 ◽  
pp. 26-31 ◽  
Author(s):  
Chuan Qin ◽  
Wenguang Liu ◽  
Wenfu He
Keyword(s):  
Seismic Response ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Response Analysis ◽  
Friction Damper ◽  
Seismic Response Analysis ◽  
Isolation System

scholarly journals Seismic Performance of Piping Systems of Isolated Nuclear Power Plants Determined by Numerical Considerations

Energies ◽  
2021 ◽  
Vol 14 (13) ◽  
pp. 4028
Author(s):  
Sungjin Chang ◽  
Bubgyu Jeon ◽  
Shinyoung Kwag ◽  
Daegi Hahm ◽  
Seunghyun Eem
Keyword(s):  
Seismic Response ◽  
Nuclear Power ◽  
Seismic Isolation ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Mesh Size ◽  
Seismic Fragility ◽  
Response Analysis ◽  
Seismic Safety ◽  
Seismic Isolation Systems

The interest in the seismic performance of nuclear power plants has increased worldwide since the Fukushima Daiichi Nuclear Power Plant incident. In Korea, interest in the seismic safety of nuclear power plants has increased since the earthquake events in Gyeongju (2016) and Pohang (2017). In Korea, studies have been conducted to apply seismic isolation systems to ensure seismic safety while minimizing the design changes to nuclear power plants. Nuclear power plants with seismic isolation systems may have a higher seismic risk due to the failure of the piping system in the structure after a relatively large displacement. Therefore, it is essential to secure the seismic safety of pipes for the safe operation of nuclear power plants. The seismic safety of pipes is determined by seismic fragility analysis. Seismic fragility analysis requires many seismic response analyses because it is a statistical approach to various random variables. Typical numerical conditions affecting the seismic response analysis of pipes are the convergence conditions and mesh size in numerical analysis. This study examined the change in the seismic safety of piping according to the numerical conditions. The difference in the seismic response analysis results of the piping according to the mesh size was analyzed comparatively. In addition, the change in the seismic fragility curve of the piping according to the convergence conditions was investigated.

Seismic Response Analysis of Containment with Hemisphere Dome for Advanced Nuclear Power Station

2012 ◽  
Vol 256-259 ◽  
pp. 2091-2095 ◽  
Author(s):  
Fang Liu
Keyword(s):  
Seismic Response ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Plants ◽  
Element Model ◽  
Response Analysis ◽  
Seismic Response Analysis ◽  
Power Station ◽  
Response Characteristics ◽  
Distribution Parameters

Nuclear Power Station is the last bulwark of the nuclear reactors, and the seriousness of the consequences due to the damage and the enormous impact of human psychology, the seismic response analysis of nuclear power plants is essential. MIDAS/Gen finite element model of the structure of the space, for example, a nuclear power plant, the power of the research containment structure under horizontal seismic response characteristics and undermine the law, the natural frequency of the structure, shapes characteristics, structure the displacement distribution parameters, provides a basis for the design of the structure and to provide a reference for similar studies.

Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 3 — Seismic Response of Crossover Piping for Seismic Isolation System

2014 ◽  
Author(s):  
Akihito Otani ◽  
Teruyoshi Otoyo ◽  
Hideo Hirai ◽  
Hirohide Iiizumi ◽  
Hiroshi Shimizu ◽  
...  
Keyword(s):  
Seismic Response ◽  
Nuclear Power ◽  
Seismic Isolation ◽  
Evaluation Method ◽  
Response Spectrum ◽  
Time History ◽  
Response Analysis ◽  
Isolation System ◽  
Isolation Systems ◽  
Seismic Isolation Systems

This paper, which is part of the series entitled “Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities”, shows the linear seismic response of crossover piping installed in a seismically isolated plant. The crossover piping, supported by both isolated and non-isolated buildings, deforms with large relative displacement between the two buildings and the seismic response of the crossover piping is caused by two different seismic excitations from the buildings. A flexible and robust structure is needed for the high-pressure crossover piping. In this study, shaking tests on a 1/10 scale piping model and FEM analyses were performed to investigate the seismic response of the crossover piping which was excited and deformed by two different seismic motions under isolated and non-isolated conditions. Specifically, as linear response analysis of the crossover piping, modal time-history analysis and response spectrum analysis with multiple excitations were carried out and the applicability of the analyses was confirmed. Moreover, the seismic response of actual crossover piping was estimated and the feasibility was evaluated.

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