Decoupling criterion for elastic-plastic seismic analysis of large-scale complex piping systems in nuclear power plants
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DOI 10.1007/s12206-020-1015-5
Journal of Mechanical Science and Technology 34 (11) 2020 Original Article DOI 10.1007/s12206-020-1015-5 Keywords: · Decoupling criterion · Elastic-plastic seismic analysis · Piping systems · Nuclear power plants
Decoupling criterion for elastic-plastic seismic analysis of large-scale complex piping systems in nuclear power plants Soo-Bin Kim1, Yun-Jae Kim1 and Jong-Sung Kim2 1
Correspondence to: Jong-Sung Kim [email protected]
Citation: Kim, S.-B., Kim, Y.-J., Kim, J.-S. (2020). Decoupling criterion for elastic-plastic seismic analysis of large-scale complex piping systems in nuclear power plants. Journal of Mechanical Science and Technology 34 (11) (2020) 4563~4573. http://doi.org/10.1007/s12206-020-1015-5
2
Department of Mechanical Engineering, Korea University, Seoul 02841, Korea, Department of Nuclear Engineering, Sejong University, Seoul 05006, Korea
Abstract
This paper proposes an elastic-plastic-based decoupling criterion that can be applied to the seismic analysis of large-scale complex piping systems in nuclear power plants under beyond design basis earthquakes. First, the existing elastic-based decoupling criteria for seismic analyses were critically reviewed. Next, the effect of plasticity on the decoupling criteria was investigated by considering the equivalent damping and stiffness reduction. Finally, the decoupling criterion considering plasticity was developed based on the changes resulting from existing decoupling criteria. The validity of the proposed decoupling criterion was confirmed through its application to an analysis of a real piping system.
Received June 10th, 2020 Revised
July 9th, 2020
Accepted August 13th, 2020
1. Introduction
† Recommended by Editor No-cheol Park
To ensure that the structural integrity of a nuclear power plant (NPP) is maintained even under design basis earthquakes (DBEs), seismic design provisions corresponding to DBEs have been developed according to the conservative stress-based evaluation method provided by technical codes and standards such as the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessels (B&PV) Code, Sec. III [1]. However, after the Fukushima nuclear accident following the Great East Japan Earthquake, the need to assess the structural integrity of NPPs under beyond design basis earthquake (BDBEs) was raised. Accordingly, nuclear regulatory agencies, such as the International Atomic Energy Agency (IAEA) and the United States (US) Nuclear Regulatory Commission (NRC), have established and published new safety guidelines and standards [2, 3]. In addition, some studies have been performed by the Japan Society of Mechanical Engineers (JSME) to develop a seismic analysis guideline that considers plasticity [4-7]. An NPP consists of large-scale complex piping component systems in which various piping and components are interconnected. Due to the very long calculation times and high demands for ultra-high-performance calculation tools, it is impractical to perform a seismic analysis of such a
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