核电厂流固相互作用:一些主要现象的回顾和相关安全方面的分析

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Daniele Vivaldi , Angel Papukchiev , Clément Viron , Stéphanie Graff , Mikael Kountchou
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引用次数: 0

摘要

流固相互作用,如流体引起的振动,是核电站磨损和损坏的一个来源。与流体-结构相互作用现象有关的几个问题已被广泛报道的植物成分。为了理解流体结构相关问题的重要性,对潜在机制的分析应该与相关安全问题的讨论结合起来。这就是本文的目的所在。介绍了一些与流体结构相关的主要现象,从涉及反应堆压力容器内部(如燃料棒/组件和热套管)的问题到蒸汽发生器管的退化。对于每一种现象,首先对记录的事件进行回顾,然后分析潜在的物理机制,最后分析相关的安全问题,这代表了本文的主要原创性。此外,提出了新的数值研究,旨在预测热套的磨损:他们依赖于CFD模拟的核心上静压室。对圣奥诺弗雷核电站蒸汽发生器管磨损进行了专门分析。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Fluid–structure interactions in nuclear power plants: Review of some main phenomena and analysis of the related safety aspects
Fluid–structure interactions such as fluid-induced vibrations are a source of wear and damage in nuclear power plants. Several issues linked with fluid–structure interaction phenomena have been constantly reported for a wide range of plant components. In order to understand the importance of fluid–structure related problems, the analysis of the underlying mechanisms should be combined to a discussion of the associated safety issues. This is what this article is intended to present. Some main fluid–structure related phenomena are presented, ranging from issues concerning reactor pressure vessel internals such as fuel rods/assemblies and thermal sleeves, to steam generator tube degradation. For each phenomenon, a review of the documented events is first presented, followed by the analysis of the underlying physical mechanisms and, finally, by the analysis of the associated safety concerns, that represents the main originality of this article. Beside, new numerical studies aimed at predicting the wear of thermal sleeves are presented: they rely on the CFD simulation of the core upper plenum. A dedicated analysis of the steam generator tube wear at the San Onofre nuclear power plant is proposed.
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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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