Simulating the time-dependent evolution of Alkali-Silica Reaction (ASR) strains in concrete

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

Nuclear Engineering and Design Pub Date : 2024-10-30 DOI:10.1016/j.nucengdes.2024.113658

Gunay Gina Aliyeva , Yann Le Pape , Abhinav Gupta

引用次数: 0

Abstract

Alkali-Silica Reaction (ASR) affects the resiliency of concrete structures by initiation of cracking in concrete which in turn leads to deterioration. There has been an increasing demand to understand the ASR-induced expansion and degradation in concrete. Continued safe operation of concrete structures requires an assessment of ASR-induced expansion and degradation. This paper attempts to understand the time-dependent evolution of ASR-induced expansion and degradation in concrete structures. A novel approach is proposed to simulate the ASR-induced expansion and degradation in concrete that is based on coupling the ASR-induced strains with the mechanical strains using a time-dependent piecewise evolution process at each instance of time. Data from an experimental study is used to develop the proposed approach. It is shown that the proposed approach is able to simulate the ASR-induced expansion and degradation in concrete reasonably well.

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模拟混凝土中随时间变化的碱硅反应（ASR）应变

碱硅反应（ASR）会影响混凝土结构的韧性，使混凝土开裂，进而导致结构退化。人们越来越需要了解 ASR 引起的混凝土膨胀和退化。混凝土结构的持续安全运行需要对 ASR 引起的膨胀和退化进行评估。本文试图了解 ASR 引起的混凝土结构膨胀和退化随时间的变化。本文提出了一种模拟 ASR 引起的混凝土膨胀和降解的新方法，该方法基于 ASR 引起的应变与机械应变的耦合，在每个时间实例使用随时间变化的片断演化过程。实验研究的数据被用来开发所提出的方法。结果表明，所提出的方法能够很好地模拟 ASR 引起的混凝土膨胀和降解。

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 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.