考虑不同支柱支撑系统的双曲线冷却塔在地震作用下的动态响应

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-10-14 DOI:10.1016/j.nucengdes.2024.113632

Adil Ziraoui , Benaissa Kissi , Hassan Aaya , Imane Ahnouz

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引用次数: 0

摘要

使用 SAP2000 对钢筋混凝土冷却塔进行地震行为分析的目的是模拟和评估结构对来自近距离和远距离运动的地震荷载的响应。分析过程首先是创建一个数值模型，将冷却塔的几何形状、建筑材料、预期地震荷载和约束条件纳入其中。冷却塔由 I 型柱和Ʌ 型柱支撑。对结构系统的动态响应进行了相关的比较，包括塔基（支柱与外壳的交接处）、喉管层和塔顶。这些分析结果加深了我们对冷却塔地震行为的理解，突出了应力过大的区域、潜在的变形以及在地震中容易损坏的部件。这些信息对于改进结构，提高冷却塔的抗震能力，确保其在地震发生时的稳定性（无论距离多近）至关重要。

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Dynamic response of hyperbolic cooling tower considering different column supporting systems subjected to seismic actions

The seismic behavior analysis of a reinforced concrete cooling tower using SAP2000 aims to simulate and evaluate the structure’s response to seismic loads, both from near and far movements. This process begins with the creation of a numerical model that incorporates the tower’s geometry, construction materials, and anticipated seismic loads and constraints. The cooling tower is supported by I-type and Ʌ-type columns. Relevant comparisons of the dynamic response of the structural system have been made at the base level (where the columns meet the shell), throat level, and at the top of the tower. The results from these analyses enhance our understanding of the cooling tower’s seismic behavior, highlighting areas of excessive stress, potential deformations, and components vulnerable to damage during an earthquake. This information is vital for informing structural improvements that enhance the seismic resistance of the cooling tower and ensure its stability during seismic events, regardless of their proximity.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

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.