Analysis of the influence of bottom flow holes in control rod guide tubes on flow field and control rod displacement

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-01 Epub Date: 2024-11-04 DOI:10.1016/j.anucene.2024.111028
Hanrui Qiu, Chuanming Zhang, Mingjun Wang, Wenxi Tian, G.H. Su
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Abstract

During the operation of pressurized water reactors, flow-induced vibration issues are commonly encountered, where control rod components vibrate due to the impact of coolant flow, leading to wear, thereby posing a threat to the safe operation of the reactor. This paper conducts a detailed numerical simulation of the flow field and force distribution inside a full-scale lower control rod guide tube based on the CFD method. The fluid–structure interaction analysis is performed to reveal the influence of cross-flow under various operating conditions on the vibration and displacement of control rods. The research subject consists of 24 control rods, one continuous guide section, and six control rod guide cards. The lower part of the guide tube has two flow holes on each surface, with one assumed to be a cross-flow inlet and the others as outlets. The results indicate that when considering the cross-flow effect at the flow holes, 90 % of the coolant flows out from other flow holes at the bottom of the guide tube, resulting in increased transverse velocity at the bottom and the presence of numerous vortices. The magnitude and location of the force exerted on the control rod by coolant impact are correlated. The control rod closest to the inlet of the flow hole experiences the greatest force, approximately 5.35 times the average at other positions. At a cross-flow velocity of 0.4 m/s and a low frequency of 10 Hz, the maximum displacement of the control rod is 0.3355 mm.
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控制棒导管底流孔对流场和控制棒位移的影响分析
压水堆在运行过程中,经常遇到流动诱发振动问题,控制棒部件受冷却剂流动的冲击而产生振动,导致磨损,从而对反应堆的安全运行构成威胁。本文基于CFD方法对全尺寸下控制杆导管内的流场和力分布进行了详细的数值模拟。通过流固耦合分析,揭示了不同工况下横流对控制杆振动和位移的影响。研究课题由24根控制棒、1个连续导向段、6个控制棒导向卡组成。导管下部各表面有两个流孔,其中一个设为横流入口,其余为出口。结果表明:考虑流孔处的横流效应时,90%的冷却剂从导管底部的其他流孔流出,导致导管底部横向速度增大,出现大量涡。冷却剂冲击作用在控制棒上的力的大小和位置是相关的。靠近流孔入口的控制棒受力最大,约为其他位置平均受力的5.35倍。在横流速度为0.4 m/s、低频为10 Hz时,控制杆的最大位移为0.3355 mm。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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