Gen-IV pool reactors: Validation of sloshing CFD modelling and behavior under large seismic events

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-20 DOI:10.1016/j.nucengdes.2025.113920
Vincent Moreau, Manuela Profir
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Abstract

This paper addresses one aspect of the safety of compact lead-cooled pool fast reactors. Under a seismic event, there is concern that the surface sloshing could compromise the integrity of some structures or components. We investigate this issue by means of computational modelling and simulation using the STAR-CCM + commercial software.
In the first part, we simulate a partially filled vertical cylinder under harmonic forcing and quantitatively validate the modelling by comparison with experimental data of the free-surface height at different locations. Specifically, we capture with a very high precision a behavioral transition of the amplitude-frequency map near resonance.
In the second part, the modelling is applied to a fast reactor mock-up in water. It is validated again by comparison with experimental data under harmonic forcing. The numerical mock-up is then subjected to four seismic events of increasing intensity. The free-surface height and the forces applied to the mock-up vessel are monitored.
It is found that the forces applied to the vessel are strongly dominated by the highest frequency of the seismic acceleration. By applying a high filter cut at 1 Hz, the peak force is reduced by one order of magnitude but remains strongly related to the damped acceleration signal. Even then, sloshing forcing effects are observed but remain marginal.
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Gen-IV池反应堆:大地震下晃动CFD模型和行为的验证
本文讨论了紧凑型铅冷池快堆安全性的一个方面。在地震事件中,人们担心地表晃动会损害某些结构或部件的完整性。我们利用STAR-CCM +商业软件通过计算建模和仿真来研究这个问题。在第一部分中,我们模拟了一个在调和力作用下部分填充的垂直圆柱体,并通过与不同位置自由表面高度的实验数据的比较,定量地验证了模型的正确性。具体来说,我们以非常高的精度捕获了共振附近的幅频图的行为转变。在第二部分中,将该模型应用于一个水中快堆模型。通过与实验数据的对比,验证了该方法的有效性。数值模拟再经受4次强度递增的地震事件。自由表面高度和施加在模型船上的力被监测。研究发现,地震加速度的最高频率强烈地支配着施加在船体上的力。通过在1hz处施加高滤波器切割,峰值力减少了一个数量级,但仍然与阻尼加速度信号密切相关。即使这样,晃动强迫效应也被观察到,但仍然是微不足道的。
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
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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