核电站乏燃料池储水地震晃动试验研究

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Juin-Fu Chai, Fan-Ru Lin, Wei-Hung Hsu, Yi-Jun Kao
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引用次数: 0

摘要

由于2011年福岛第一核电站的事故,美国核管理委员会(NRC)要求所有美国核电站按照最新的指导和要求进行地震危险性重新评估。其中,乏燃料池(SFP)被认为是一个重要的设施。电力研究院EPRI-1025287报告中提供的相关评估指南强调了SFP可能导致“快速泄干”的失效模式。其中一个可能的原因是由于地震晃动而从水池中溅出的水量。EPRI-1025287报告提供了一种非常方便而保守的估算水飞溅体积的方法。为了获得更准确的结果,本研究采用储液罐的振动台试验,基于地震诱发的晃动高度与储液罐溅出的水总量之间的关系,开发了一种更真实的溅水体积估算方法。在该方法的发展过程中,还提出了使用单自由度系统来估计晃动时程的方法,用于后续的溅溅体积计算。此外,与晃动高度和飞溅水量有关的晃动频率也是研究的重点。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental study on seismic sloshing of storage water for spent fuel pool in NPPs
Due to the event of Fukushima Daiichi Nuclear Power Plant in 2011, the U.S. Nuclear Regulatory Commission (NRC) requested all U.S. nuclear power plants to conduct seismic hazard re-evaluation per the newest guidance and requirements. Among them, the spent fuel pool (SFP) is considered an important facility. The related evaluation guidance provided in the Electric Power Research Institute EPRI-1025287 report emphasizes failure modes of the SFP that could result in “rapid drain-down”. One of the possible causes is the volume of water splashed out of the pool due to seismic sloshing. In EPRI-1025287 report, a very convenient yet conservative approach for estimating water splash volume was provided. To obtain more accurate results, this study employed a shaking table test of liquid storage tanks to develop a more realistic water splash volume estimation method, based on the relationship between seismic-induced sloshing height and the associated total volume of water splashed out of the tanks. In the development of this method, the use of a single-degree-of-freedom (SDOF) systems to estimate the sloshing time history is also proposed for subsequent splashed volume calculation. Furthermore, the sloshing frequency, which is related to the sloshing height and the splashed water volume, is also a key focus of the study.
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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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