Kefei Chen , Jinming Li , Jianhang Xu , Peng Li , Yiren Yang
{"title":"压水堆燃料组件GTR滑动非线性振动的实验与理论研究","authors":"Kefei Chen , Jinming Li , Jianhang Xu , Peng Li , Yiren Yang","doi":"10.1016/j.nucengdes.2025.114443","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114443"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Experimental and theoretical study on nonlinear vibration of a reduced-scale PWR fuel assembly with GTR sliding\",\"authors\":\"Kefei Chen , Jinming Li , Jianhang Xu , Peng Li , Yiren Yang\",\"doi\":\"10.1016/j.nucengdes.2025.114443\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114443\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-09-15\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S002954932500620X\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002954932500620X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
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.
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.