Yin Xunqiang , Zhao Min , Yang Weilong , Zhang Junkai , Li Jianbo
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引用次数: 0
Abstract
The pumping station providing essential cooling water circulation are critical components in nuclear power plants (NPPs) throughout China. It is of great significance to investigate the seismic behavior of the pumping station structure considering complex heterogeneity site and load conditions according to the nuclear safety design requirements. In this study, a novel viscous-spring boundary, which is a more efficient and accurate methodology, is proposed and implemented in the ANSYS finite element software to study the seismic safety of the pumping station structure of NPPs. The Viscoelastic Static-Dynamic Unified (VSDU) artificial boundary based on Newmark’s integration scheme is proposed for nonlinear analysis of structures under coupled static-dynamic excitation. The User Programmable Features (UPFs) available in ANSYS were employed to integrate the proposed analysis method. Also, a complete toolkit for general static-dynamic coupled analysis is created using scripting-based ANSYS Parametric Design Language (APDL) and Graphical User Interface (GUI). Three validation examples are presented to demonstrate the accuracy and efficiency of the proposed method. Finally, seismic safety analysis of pumping station structure of NPPs based on the actual complex site conditions in China is also presented to illustrate the analysis procedure, and the results demonstrate that the proposed technique of investigating the seismic responses and stability of pumping station structure can provide more objective indices to evaluate the seismic safety during safety shutdown earthquake.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.