Mechanical performance and self-sensing capability of an amorphous fiber-reinforced concrete for radioactive waste storage facilities

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-11-30 DOI:10.1016/j.nucengdes.2024.113727
Théophile Bouillard , Anaclet Turatsinze , Olivier Helson , Jean-Paul Balayssac , Ahmed Toumi , Carole Soula
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Abstract

This study results from a research project initiated by the French National Radioactive Waste Management Agency (Andra) as a part of the Cigéo (Industrial Center for Geological Disposal) project. This project addresses many challenges related to sustainability, and health monitoring of confinement structures planned by Andra. In order to reduce issues related to corrosion in the tunnels, fiber reinforcement can be used to reduce the amount of steel reinforcement while maintaining high mechanical performance and durability. The fibers used in this study are named Fibraflex, metallic fibers provided by Saint Gobain SEVA. Various aspect ratios (82 and 123) and volume ratios (0.27% and 0.41%) of fibers were tested. These fibers feature high specific surface area (around 70 m2/m3), corrosion resistance, and high electrical conductivity. To characterize the contribution of fibers to concrete mechanical performances, European standard EN 14651 flexural tensile tests were conducted. Results show that fibers bring better performances, especially concerning the post-peak behavior. In fact, fibers effectively transfer stresses across cracks, resulting in better residual tensile strengths. Since these fibers are electrically conductive, tests were also conducted to design self-sensing concrete based on electrical measurements. Firstly, resistivity was monitored on saturated specimens with different mix design throughout the curing time. Results show that when fibers were added, concrete resistivity was reduced due to the ability of the fibers to transmit electrons. A relationship between reinforcement index and resistivity was thus revealed. The self-sensing capacity was investigated on specimens subjected to cyclic bending loading, with electrical properties measured by using a Wheatstone bridge. Results show a good agreement between the level of cracking in concrete and its electrical response.
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放射性废物贮存设施用非晶态纤维增强混凝土的力学性能和自传感能力
这项研究是法国国家放射性废物管理署(Andra)发起的一个研究项目的结果,该项目是地质处置工业中心项目的一部分。该项目解决了许多与可持续性相关的挑战,以及Andra规划的禁闭结构的健康监测。为了减少隧道中与腐蚀有关的问题,可以使用纤维加固来减少钢筋的数量,同时保持高机械性能和耐久性。本研究中使用的纤维被命名为Fibraflex,这是圣戈班SEVA提供的金属纤维。测试了不同长宽比(82和123)和体积比(0.27%和0.41%)的纤维。这些纤维具有高比表面积(约70 m2/m3),耐腐蚀性和高导电性。为了表征纤维对混凝土力学性能的贡献,进行了欧洲标准EN 14651的弯曲拉伸试验。结果表明,光纤具有更好的性能,尤其是在峰后性能方面。事实上,纤维有效地传递应力跨越裂缝,导致更好的残余抗拉强度。由于这些纤维具有导电性,因此还进行了基于电测量的自感混凝土设计测试。首先,对不同配合比下饱和试件在整个固化时间内的电阻率进行监测。结果表明,加入纤维后,由于纤维对电子的传输能力,降低了混凝土电阻率。从而揭示了增强指数与电阻率之间的关系。研究了试件在循环弯曲荷载下的自感知能力,并使用惠斯通电桥测量了电学性能。结果表明,混凝土开裂水平与其电响应之间具有良好的一致性。
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来源期刊
Nuclear Engineering and Design
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.
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Editorial Board Risk-informed structural integrity assessment of the HTR-PM reactor pressure vessel Design of a foreign object retrieval robot for the internal lower head of a nuclear power plant pressurizer Modeling considerations for passive safety systems in Korean SMRs using system analysis codes Experimental study of decontamination factor in pool scrubbing with two-phase flow evolution
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