核电厂SSC板- rc墙节点抗震性能试验与数值研究

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Junpeng Ye , Ming Zhao , Xiaodong Du , Xing Wang , Haitao Xu , Yongshan Zhang , Dayang Wang
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引用次数: 0

摘要

为了提高核电站板墙节点的抗震性能,提出了一种新型的单钢板混凝土板-钢筋混凝土墙节点。以核电机组典型侧壁SWJ为基础,设计制作了3个1:3缩比例尺的侧壁SWJ试件:1个钢筋混凝土板墙节点(RCSWJ)试件作为参考,2个SSCSWJ试件(SSCSWJ1、SSCSWJ2)。进行了低循环荷载试验,对三个试件的抗震性能进行了评价和比较。建立了有限元模型,并与实验结果进行了对比验证。随后,对SSCSWJ1进行了参数分析,以研究关键设计参数的影响。试验结果表明,与RCSWJ相比,SSCSWJ1和SSCSWJ2的承载力、延性和耗能均有所提高,并具有提高施工效率的潜力。参数化研究进一步表明,增加配筋率可以有效提高SSCSWJ1的初始刚度和承载力。在研究参数范围内,增加钢板厚度可以提高初始刚度,对承载力的影响最小,而t型钢间距和混凝土等级对两者的影响相对有限。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental and numerical study on seismic behavior of SSC slab-RC wall joints in NPP
A new type of single steel-plate concrete slab-reinforced concrete wall joint (SSCSWJ) is proposed to enhance the seismic performance of slab-wall joints (SWJs) in nuclear power plants (NPPs). Based on a typical side SWJ in NPPs, three 1:3 reduced scale SWJ specimens were designed and fabricated: one reinforced concrete slab-wall joint (RCSWJ) specimen as a reference, and two SSCSWJ specimens (SSCSWJ1, SSCSWJ2). Low cyclic loading tests were conducted to evaluate and compare the seismic performance of the three specimens. A finite element model (FEM) was developed and validated against the experimental results. Subsequently, a parametric analysis was performed on SSCSWJ1 to investigate the influence of critical design parameters. Test results indicate that, compared with RCSWJ, both SSCSWJ1 and SSCSWJ2 exhibit enhanced bearing capacity, ductility, and energy dissipation, and also have the potential to improve construction efficiency. The parametric study further reveals that increasing the slab reinforcement ratio effectively enhances both the initial stiffness and bearing capacity of SSCSWJ1. Within the studied parameter range, increasing the steel-plate thickness improves the initial stiffness and has minimal influence on bearing capacity, whereas T-section steel spacing and concrete grade exert relatively limited effects on both.
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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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