压水堆燃料组件GTR滑动非线性振动的实验与理论研究

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Kefei Chen , Jinming Li , Jianhang Xu , Peng Li , Yiren Yang
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引用次数: 0

摘要

在压水堆(PWR)运行过程中,燃料组件(FA)经历轴向流引起的振动,导致燃料棒(FR)包层与栅格之间的接触界面磨损。此外,在地震事件或冷却剂丢失事故(LOCAs)期间,FA可能会发生严重变形,可能导致结构失效。因此,建立FA的动态模型来研究其在这些条件下的结构行为对于保证反应堆的安全至关重要。实验研究表明,FAs在载荷作用下表现出非线性行为,包括准静态实验中的双线性滞后和强迫振动实验中的刚度软化。以往的准静态研究表明,网格-杆(GTR)节点的相对轴向滑动和旋转相互作用主要引起网格-杆(GTR)节点的刚度软化和滞后行为。在此基础上,采用弯曲-轴向耦合的Euler-Bernoulli梁理论建立了理论非线性FA动力模型,将以往的准静态分析扩展到瞬态动力条件。为了进一步研究FA的结构特性并为建模提供见解,在两端刚性固定的缩小尺寸3 × 3 FA上进行了振动实验。该理论模型通过考虑相对轴向滑动和相对旋转滑动,成功地再现了准静态和动态试验中观察到的结构响应特征。准静态循环加载下观察到的刚度过渡阶段在模拟燃料组件的非线性动态响应中起着至关重要的作用。在此基础上,利用所建立的非线性动力学模型,对FA的微动磨损特性进行了仿真分析。模拟分析了不同GTR接头的磨损规律,高磨损率GTR接头的分布与实验观察结果一致。本研究为结构动力学建模提供了可靠的框架。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental and theoretical study on nonlinear vibration of a reduced-scale PWR fuel assembly with GTR sliding
During the operation of a pressurized water reactor (PWR), the fuel assembly (FA) experiences axial flow-induced vibrations, leading to wear at the contact interfaces between the fuel rod (FR) cladding and the grids. Additionally, during seismic events or loss-of-coolant accidents (LOCAs), the FA may undergo severe deformation, potentially resulting in structural failures. Therefore, establishing a dynamic model of the FA to investigate its structural behavior under these conditions is essential for ensuring reactor safety. Experimental studies have demonstrated that FAs display nonlinear behavior under loading, including bilinear hysteresis in quasi-static experiments and stiffness softening in forced vibration experiments. Previous quasi-static studies have revealed that the stiffness softening and hysteresis behavior of FAs are primarily induced by relative axial sliding and rotational interactions at the grid-to-rod (GTR) joints. Building upon this foundation, the Euler–Bernoulli beam theory with bending-axial deformation coupling is employed to develop a theoretical nonlinear FA dynamic model that extends the previous quasi-static analysis to transient dynamic conditions. To further investigate the structural characteristics of the FA and provide insights for modeling, vibration experiments were conducted on a reduced-scale 3 × 3 FA with both ends rigidly fixed. The theoretical model successfully reproduced the structural response characteristics observed in both quasi-static and dynamic experiments by incorporating relative axial sliding and relative rotational sliding. The stiffness transition phase observed under quasi-static cyclic loading has been demonstrated to play a critical role in simulating the nonlinear dynamic response of the fuel assembly. Furthermore, using the developed nonlinear dynamic model, the GTR fretting (GTRF) wear characteristics of the FA are simulated and analyzed. The simulations identified wear patterns at different GTR joints, with the distribution of high-wear-rate GTR joints aligning with experimental observations. This study provides a reliable structural dynamic modeling framework for FA.
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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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