Daniele Vivaldi , Angel Papukchiev , Clément Viron , Stéphanie Graff , Mikael Kountchou
{"title":"核电厂流固相互作用:一些主要现象的回顾和相关安全方面的分析","authors":"Daniele Vivaldi , Angel Papukchiev , Clément Viron , Stéphanie Graff , Mikael Kountchou","doi":"10.1016/j.nucengdes.2025.114121","DOIUrl":null,"url":null,"abstract":"<div><div>Fluid–structure interactions such as fluid-induced vibrations are a source of wear and damage in nuclear power plants. Several issues linked with fluid–structure interaction phenomena have been constantly reported for a wide range of plant components. In order to understand the importance of fluid–structure related problems, the analysis of the underlying mechanisms should be combined to a discussion of the associated safety issues. This is what this article is intended to present. Some main fluid–structure related phenomena are presented, ranging from issues concerning reactor pressure vessel internals such as fuel rods/assemblies and thermal sleeves, to steam generator tube degradation. For each phenomenon, a review of the documented events is first presented, followed by the analysis of the underlying physical mechanisms and, finally, by the analysis of the associated safety concerns, that represents the main originality of this article. Beside, new numerical studies aimed at predicting the wear of thermal sleeves are presented: they rely on the CFD simulation of the core upper plenum. A dedicated analysis of the steam generator tube wear at the San Onofre nuclear power plant is proposed.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"441 ","pages":"Article 114121"},"PeriodicalIF":2.1000,"publicationDate":"2025-06-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Fluid–structure interactions in nuclear power plants: Review of some main phenomena and analysis of the related safety aspects\",\"authors\":\"Daniele Vivaldi , Angel Papukchiev , Clément Viron , Stéphanie Graff , Mikael Kountchou\",\"doi\":\"10.1016/j.nucengdes.2025.114121\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Fluid–structure interactions such as fluid-induced vibrations are a source of wear and damage in nuclear power plants. Several issues linked with fluid–structure interaction phenomena have been constantly reported for a wide range of plant components. In order to understand the importance of fluid–structure related problems, the analysis of the underlying mechanisms should be combined to a discussion of the associated safety issues. This is what this article is intended to present. Some main fluid–structure related phenomena are presented, ranging from issues concerning reactor pressure vessel internals such as fuel rods/assemblies and thermal sleeves, to steam generator tube degradation. For each phenomenon, a review of the documented events is first presented, followed by the analysis of the underlying physical mechanisms and, finally, by the analysis of the associated safety concerns, that represents the main originality of this article. Beside, new numerical studies aimed at predicting the wear of thermal sleeves are presented: they rely on the CFD simulation of the core upper plenum. A dedicated analysis of the steam generator tube wear at the San Onofre nuclear power plant is proposed.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"441 \",\"pages\":\"Article 114121\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-06-03\",\"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/S0029549325002985\",\"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/S0029549325002985","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}
Fluid–structure interactions in nuclear power plants: Review of some main phenomena and analysis of the related safety aspects
Fluid–structure interactions such as fluid-induced vibrations are a source of wear and damage in nuclear power plants. Several issues linked with fluid–structure interaction phenomena have been constantly reported for a wide range of plant components. In order to understand the importance of fluid–structure related problems, the analysis of the underlying mechanisms should be combined to a discussion of the associated safety issues. This is what this article is intended to present. Some main fluid–structure related phenomena are presented, ranging from issues concerning reactor pressure vessel internals such as fuel rods/assemblies and thermal sleeves, to steam generator tube degradation. For each phenomenon, a review of the documented events is first presented, followed by the analysis of the underlying physical mechanisms and, finally, by the analysis of the associated safety concerns, that represents the main originality of this article. Beside, new numerical studies aimed at predicting the wear of thermal sleeves are presented: they rely on the CFD simulation of the core upper plenum. A dedicated analysis of the steam generator tube wear at the San Onofre nuclear power plant is proposed.
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.