Investigation on cross flow induced tube bundle vibration and tube-support contact state

IF 3.2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-09-27 DOI:10.1016/j.pnucene.2025.106068

Zhenqin Xiong, Shuo Wang, Ruiqi Kang, Jing Liu, Linpeng Shi, Shenjie Gong

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引用次数: 0

Abstract

Wear due to non-uniform cross flow induced vibration (FIV) challenging the integrity of tubes and fuel rods in nuclear reactors depends on the vibration trajectory and the contact state between the tube and the tube support plate. To reveal the characteristics of vibration and contact state of tubes suffering non-uniform cross flow, experimental investigation on the vibration response of a three-span 7x11 tube bundle subjected to cross-flow from a one-third opening baffle and a baffle with uniform holes has been carried out. Visualization measurement techniques have been developed to obtain the vibration trajectory of the tube in the middle of the first row and the micro-meter sale gap between the tube and the support plate at the top end. Numerical simulations were also conducted to analyze the flow field characteristics within the tube bundle formed by the one-third opening inlet flow. The results indicate that the tube bundle subjected to flow from a one-third open inlet is more prone to fluid-elastic instability compared to that with a uniformly perforated inlet. However, in the high velocity ranging from 1.52 m/s to 2.77 m/s before FEI, the case with uniform-hole baffle has higher vibration transverse displacement at the top end than the corresponding case with one-third opening baffle. The gap between the tube C1 (middle tube in the first row) and 2#TSP, and the top end trajectory of tube C1 is systematically analyzed. The contact states between this tube and the 2#TSP indicate that the tube stably leaning on the TSP is prone to adhesive wear before FEI for non-uniform flow case, while the tube experiencing serious displacement at contact location is prone to sliding wear before the FEI for uniform flow.

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横流诱导管束振动及管架接触状态研究

核反应堆管与燃料棒的非均匀交叉流诱发振动磨损主要取决于管与管支承板之间的接触状态和振动轨迹。为了揭示非均匀横流作用下管束的振动特性和接触状态，对三跨7x11管束在三分之一开口挡板和均匀孔挡板的横流作用下的振动响应进行了实验研究。开发了可视化测量技术，以获得第一排中间管的振动轨迹和最上端管与支撑板之间的微米间距。通过数值模拟分析了三分之一开口进口流形成的管束内流场特征。结果表明，三分之一开口进口比均匀穿孔进口的管束更容易发生流体弹性失稳。而在FEI前1.52 ~ 2.77 m/s的高速范围内，均孔挡板的顶部振动横向位移高于三分之一开挡板的顶部振动横向位移。系统分析了C1管（第一排中间管）与2#TSP之间的间隙以及C1管的顶端轨迹。该管与2#TSP的接触状态表明，在非均匀流动情况下，稳定靠在TSP上的管在FEI前容易发生粘着磨损，而在均匀流动情况下，接触位置发生严重位移的管在FEI前容易发生滑动磨损。

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.