分析间隔网格下游的速度和压力波动:结构与传输

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
N. Turankok , T. Lohez , V. Biscay , L. Rossi
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引用次数: 0

摘要

在压水堆(PWR)中,流体与结构的相互作用会引起燃料棒的振动,从而导致栅与栅之间的摩擦。为了探索燃料棒受流动影响而产生局部振动的原因,我们在一个由间隔网格维持的 5 × 5 燃料棒束内进行了分析实验。实验使用了两套网格,即带混合叶片和不带混合叶片的网格,雷诺数范围很广,从大约 10,000 到 120,000 不等。在中心仪器杆附近进行的粒子图像速度测量显示了两种配置下不同的速度场结构及其波动。不带混合叶片的平均场呈倒 U 形,带混合叶片的平均场呈 λ 形。速度波动场为不带混合叶片的蝶形和带混合叶片的 Y(低 Re)和 K(高 Re)形。在网格附近,当 ReDh 在 10,000 到 120,000 之间变化时,u′rms/Uflow 增加了约 30%。速度波动场的可视化突出显示了涡的存在。这些涡流的间距及其大小与周期性长度尺度(从频率峰值获得)和测量的积分长度尺度一致。观测到的频率峰的频率对速度和压力波动都是相同的。因此,在雷诺数介于 10,000 和 120,000 之间以及两种网格配置的所有现有数据基础上,建立了新的 Strouhal 与雷诺图。结果发现,网格附近的速度和压力波动的积分长度尺度大致相同。结果表明,压力波动事件是持续存在的,其传输速度接近平均流速。此外,这种传输与速度事件的位移相关。测量到的湍流统计数据、观测到的漩涡以及压力和速度波动的交叉相关性之间的一致性支持这样的结论,即大尺度漩涡(约 0.2 Dh)是主要压力波动及其传输的起源。据作者所知,这是有关压水堆燃料组件不同几何形状的分析网格下游压力波动的起源和传输的第一个实验证据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport

Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport
In Pressurized Water Reactors (PWR), fluid–structure interaction provokes vibrations of the fuel rods leading to grid-to-rod fretting. To explore the origins of the local excitations of the rods by the flow, analytical experiments are performed within a 5 × 5 rod bundle maintained by spacer grids. Experiments are performed using two sets of grids, i.e. configurations with and without mixing vanes, over a wide range of Reynolds number, i.e. from about 10,000 to 120,000. Particle Image Velocity measurements near the central instrumented rod reveal different structures of velocity fields and their fluctuations for the two configurations. Mean fields are in U inverted shape without mixing vanes and in λ shape with mixing vanes. Fields of velocity fluctuations are in butterfly shape without mixing vanes and in Y (low Re) and K (high Re) shapes with mixing vanes. Near the grid, urms/Uflow increases by about 30% for ReDh varying from 10,000 to 120,000. The presence of eddies is highlighted by visualisations of the fields of the velocity fluctuations. The spacing of these eddies and their sizes are found to be in agreement with the periodic length scales (obtained from frequency peaks) and the integral length-scales measured. Frequencies of the observed frequency peaks are found to be the same for both velocity and pressure fluctuations. Consequently, a new Strouhal versus Reynolds map is built over all existing data for Reynolds numbers between 10,000 and 120,000 and for the two grids configurations. The integral length-scales are found to be about the same for velocity and pressure fluctuations near the grid. It is shown that events of pressure fluctuations are persistent and transported with a speed close to the one of the mean flow. Moreover, this transport is correlated with the displacement of velocity events. The coherence between measured turbulence statistics, the observed eddies and cross-correlations of pressure and velocity fluctuations support the conclusion that the large-scale eddies (about 0.2 Dh) are at the origin of main pressure fluctuations and their transport. To the authors’ knowledge, this is the first experimental evidence of the origin and transport of pressure fluctuations downstream analytical grids with different geometries relevant to PWR fuel assemblies.
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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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