核废料贮存结构用常规混凝土和超高性能混凝土的热性能和结构性能比较

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Nataliia Igrashkina , Mohamed A. Moustafa , Mustafa Hadj-Nacer
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引用次数: 0

摘要

乏核燃料(SNF)目前储存在美国各地越来越多的干桶储存结构中。由于混凝土老化风险、许可证更新挑战以及永久SNF储存库的缺乏,迫切需要延长现有储存系统的使用寿命,并重新考虑使用耐用材料的新系统的设计。超高性能混凝土(UHPC)具有优异的机械性能和耐久性,为改造现有或建造新的SNF储存设施提供了一个有前途的解决方案。只有非常有限的研究可用于UHPC在干储存系统中的可能利用。因此,本研究首先重新思考了目前使用UHPC的SNF钢筋混凝土水平模块存储设施的设计,并重点比较了传统混凝土和UHPC在典型水平存储模块中的热性能和结构性能。该研究考虑计算流体动力学(CFD)分析来建立温度分布,随后用于结构有限元分析。各种荷载组合的需求与各自的混凝土和UHPC截面能力进行比较,以进行评估。结果表明:与常规混凝土相比,UHPC构件具有更大的结构储备容量和更好的热工性能,在耐久性和使用寿命显著延长的同时,还能显著提高结构性能。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparison of thermal and structural performance of conventional concrete and UHPC for spent nuclear fuel storage structures
Spent nuclear fuel (SNF) is currently stored in a growing number of dry cask storage structures across the US. With concrete aging risks, licensing renewals challenges, and the absence of a permanent SNF repository, there is a pressing need for extending the service life of the existing storage systems and rethinking the design of new systems for longevity using durable materials. Ultra-high performance concrete (UHPC) possesses superior mechanical and durability properties and presents a promising solution for retrofitting existing or building new SNF storage facilities. Only very limited research is available on the possible utilization of UHPC in dry storage systems. As such, this study takes a first look at rethinking the design of current SNF reinforced concrete horizontal modules storage facilities using UHPC, and focuses on the comparative thermal and structural performance of conventional concrete and UHPC in a typical horizontal storage module. The study considers computational fluid dynamics (CFD) analysis to establish temperature distributions that are used subsequently in structural finite element analysis. Demands from various load combinations are compared to respective concrete and UHPC section capacities for assessment. The results show that UHPC components have a bigger reserved structural capacity and better thermal performance than conventional concrete, and could provide a significantly enhanced structural performance besides the outstanding durability and extended service life.
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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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