核电站中 SRC 柱-RC 板连接的抗震行为实验和数值研究

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2024-08-26 DOI:10.1016/j.net.2024.08.045
Dayang Wang, Qiang Liu, Yuanqi Song, Yong Zhu, Yongshan Zhang
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引用次数: 0

摘要

本文提出了一种基于强柱弱板概念的钢筋混凝土(SRC)柱-钢筋混凝土(RC)板连接的创新设计。在本研究中,设计并制作了两个 1:2 缩尺 SRC 柱-RC 板连接试件,用于基于核电站辅助厂房侧板-柱连接的水平循环加载试验。为了确保钢筋与型钢之间连接的施工简便性和稳定性,制作并测试了一种结构(SR-2)和另一种结构(SR-1),前者将钢套筒焊接到型钢上并与连接区域的钢筋相连,后者则在 SR-2 的基础上在连接区域安装了加劲钢板(SSP),以研究连接处的结构加固问题。根据测试结果,对试件的破坏模式、滞后性能、耗能能力和刚度退化进行了研究。建立了有限元分析(FEA)模型,并与试验结果进行了验证。经过验证的有限元分析模型被用于对 SSP 的厚度、外部尺寸、RC 板的纵向配筋率和轴向压力比的影响进行参数研究。试验结果表明,试件的破坏模式为 RC 板的剪切破坏,而 SRC 柱的破坏较小,这符合强柱弱板的设计理念。参数研究表明,增加 SSP 的厚度和外部尺寸可提高接缝的承载能力和初始刚度。
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Experimental and numerical study on seismic behaviors of SRC column-RC slab joints in NPP
This paper presents an innovative design of a steel-reinforced concrete (SRC) column-reinforced concrete (RC) slab joint based on a concept of the strong column and weak slab. In this study, two 1:2 reduced scale SRC column-RC slab joint specimens are designed and fabricated for horizontal cyclic loading tests based on side slab-column joints of an auxiliary plant of a nuclear power plant. In order to ensure the ease of construction and stability of the connection between the reinforcement and the section steel, one structure (SR-2) with steel sleeves welded to the section steel and connected to the reinforcement in the joint area and the other structure (SR-1) with a stiffened steel plate (SSP) in the connection area on the basis of SR-2 were fabricated and tested in order to investigate the structural strengthening the joint. Based on the test results, the damage modes, hysteresis performance, energy dissipation capacity and stiffness degradation of the specimens were studied. A finite element analysis (FEA) model was developed and verified with the experimental results. The verified FEA model was used for parametrical study on effects of thickness, outer dimensions of SSP, a longitudinal reinforcement ratio in the RC slab and an axial pressure ratio. The test results show that the damage mode of specimens is shear failure at the RC slab and the damage of the SRC column is minor, which is in line with the design concept of the strong column and weak slab. The parametric study shows that increasing the thickness and outer size of SSP can improve the load-bearing capacity and initial stiffness of joints.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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