Sipeng Wang , Jingbo Hui , Zhuoyao Li , Hang Zhang , Bao-Wen Yang , Kun Zhuang
{"title":"Numerical investigation on flow-induced vibration of LBE-cooled wire-wrapped rod and rod bundle","authors":"Sipeng Wang , Jingbo Hui , Zhuoyao Li , Hang Zhang , Bao-Wen Yang , Kun Zhuang","doi":"10.1016/j.pnucene.2025.105664","DOIUrl":null,"url":null,"abstract":"<div><div>Among the Generation-IV nuclear reactors, LBE-cooled reactors stand out as particularly promising due to their high neutron economy, high thermal conductivity, and high boiling point. However, the high density of lead-bismuth coolants and the mixing effect of helical structures lead to flow-induced vibrations, which can cause fuel rod vibrations leading to the leakage of radioactive materials and posing a significant threat to the safe operation of nuclear reactors. Consequently, this study employs CFD method to conduct an in-depth analysis of the flow-induced vibration characteristics of LBE-cooled wire-wrapped rod and rod bundles under various flow velocities to elucidate the intrinsic link between fluid excitation and structural vibration characteristics. Through multi-scenario analysis, this study not only clarifies the direct relationship between fluid excitation frequencies and fuel rod vibration responses but also integrates micro-scale fluid dynamic characteristics with macro-scale structural vibration characteristics, offering a novel perspective for understanding the physical mechanisms behind flow-induced vibrations. The results indicate that the main low-frequency components in the fluid excitation have induced low-frequency forced vibrations in the fuel rods that correspond to their response frequencies, which is consistent with numerous studies related to vibration. There is a significant difference in vibration behavior between single rod and rod bundle. As for rod bundle, due to the distinct pressure distribution characteristics of center channel and corner channel, the edge rods vibrate in diagonal directions and away from the center with a large amplitude, and the amplitude increase as flow velocity increases. However, flow velocity is not the definitive factor for vibration intensity. The vibration intensity and amplitude of the central rod increase as flow velocity increases, and fuel rods resonate in the studied flow velocities. In this study, not only the relationship between fluid excitation and structural vibration was revealed, but also the vibration characteristics of fuel rods are obtained. This provides a reference for further research and engineering applications in nuclear field.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"182 ","pages":"Article 105664"},"PeriodicalIF":3.3000,"publicationDate":"2025-02-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025000629","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}
引用次数: 0
Abstract
Among the Generation-IV nuclear reactors, LBE-cooled reactors stand out as particularly promising due to their high neutron economy, high thermal conductivity, and high boiling point. However, the high density of lead-bismuth coolants and the mixing effect of helical structures lead to flow-induced vibrations, which can cause fuel rod vibrations leading to the leakage of radioactive materials and posing a significant threat to the safe operation of nuclear reactors. Consequently, this study employs CFD method to conduct an in-depth analysis of the flow-induced vibration characteristics of LBE-cooled wire-wrapped rod and rod bundles under various flow velocities to elucidate the intrinsic link between fluid excitation and structural vibration characteristics. Through multi-scenario analysis, this study not only clarifies the direct relationship between fluid excitation frequencies and fuel rod vibration responses but also integrates micro-scale fluid dynamic characteristics with macro-scale structural vibration characteristics, offering a novel perspective for understanding the physical mechanisms behind flow-induced vibrations. The results indicate that the main low-frequency components in the fluid excitation have induced low-frequency forced vibrations in the fuel rods that correspond to their response frequencies, which is consistent with numerous studies related to vibration. There is a significant difference in vibration behavior between single rod and rod bundle. As for rod bundle, due to the distinct pressure distribution characteristics of center channel and corner channel, the edge rods vibrate in diagonal directions and away from the center with a large amplitude, and the amplitude increase as flow velocity increases. However, flow velocity is not the definitive factor for vibration intensity. The vibration intensity and amplitude of the central rod increase as flow velocity increases, and fuel rods resonate in the studied flow velocities. In this study, not only the relationship between fluid excitation and structural vibration was revealed, but also the vibration characteristics of fuel rods are obtained. This provides a reference for further research and engineering applications in nuclear field.
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.