Experimental study on the minimum limit anchorage length and mechanical properties of bent anchorage steel bars in reactor building

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Dayang Wang , Yu Zhang , Yanhu Ding , Mingxin Bai , Zhulin Nie
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Abstract

This study presents a comprehensive investigation into the anchorage performance of bent steel bars embedded in straight segments of reinforced concrete (RC) specimens with high reinforcement ratios, using a prototype nuclear reactor shear wall as the reference model. A total of 44 pull-out tests, grouped into nine series, were conducted to determine the minimum effective anchorage length. Key failure mechanisms, bond behavior, and strain development were systematically analyzed. The results indicated that with decreasing anchorage length, no pull-out failure occurred; instead, steel bar fracture became the dominant failure mode. The minimum effective anchorage length was identified as 0.25labe, below which anchorage performance was significantly compromised. At this critical length, the incorporation of structural transverse reinforcement increased the average maximum yield load by 4.96 %, whereas variations in bent bar length exhibited minimal influence. Furthermore, high reinforcement ratios enhanced the deformation capacity of the specimens, reducing the likelihood of premature yielding. Specimens without transverse reinforcement exhibited a 32.08 % reduction in average yield displacement (9.95 mm) compared to those with transverse reinforcement. An empirical regression model was developed to modify the bond strength calculation under high reinforcement conditions, exhibiting strong predictive accuracy and aligning closely with experimental observations. The findings offer practical insights for the anchorage design of RC specimens in nuclear facilities, especially under conditions of dense reinforcement where existing code provisions may be inadequate.
反应堆建筑弯曲锚固钢筋最小极限锚固长度及力学性能试验研究
本文以核反应堆原型剪力墙为参考模型,对高配筋率钢筋混凝土直段内嵌弯钢筋的锚固性能进行了全面研究。共进行了44次拔出试验,分为9个系列,以确定最小有效锚固长度。系统地分析了关键的破坏机制、粘结行为和应变发展。结果表明:随着锚固长度的减小,锚固体不发生拉拔破坏;钢筋断裂成为主要的破坏方式。最小有效锚固长度为0.25labe,低于0.25labe锚固性能明显受损。在此临界长度下,结构横向钢筋的加入使平均最大屈服荷载增加了4.96%,而弯筋长度的变化影响最小。此外,高配筋率提高了试件的变形能力,降低了过早屈服的可能性。与有横向加固的试件相比,没有横向加固的试件的平均屈服位移(9.95 mm)减少了32.08%。建立了修正高配筋条件下粘结强度计算的经验回归模型,预测精度高,与实验结果吻合较好。研究结果为核设施中钢筋混凝土试件的锚固设计提供了实际见解,特别是在现有规范规定可能不充分的密集加固条件下。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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