{"title":"蒸汽发生器管裂纹扩展的数字孪生模型生成:方法与实现","authors":"Yingying Jiang , Hong Xia , Jinming Zhang , Yihu Zhu , Kaige Zhang , Xueying Huang , Wenzhe Yin , Peiqi Jiang","doi":"10.1016/j.anucene.2025.111697","DOIUrl":null,"url":null,"abstract":"<div><div>Crack propagation in the steam generator tubes are critical factor influencing the safe operation of nuclear power plants. Accurate prediction of crack growth behavior is vital for effective equipment health monitoring and maintenance. A fundamental framework and key technologies for the implementation of digital twin technology in nuclear power plants were presented in this study. And a novel crack propagation digital twin model generation technique for steam generator tubes was introduced, which integrates experimental data with extended finite element simulation results. Particle Filter method and reinforcement learning were conducted to evaluate respective strengths and limitations in crack propagation prediction. Both experimental data and extended finite element simulation data were incorporated into the model training process. The results demonstrated that both digital twin model generation techniques have distinct applicability conditions and high accuracy. This study could provide new insights and technological approaches for the health monitoring of steam generator tubes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111697"},"PeriodicalIF":1.9000,"publicationDate":"2025-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Digital twin model generation for crack propagation in steam generator tubes: Methods and implementation\",\"authors\":\"Yingying Jiang , Hong Xia , Jinming Zhang , Yihu Zhu , Kaige Zhang , Xueying Huang , Wenzhe Yin , Peiqi Jiang\",\"doi\":\"10.1016/j.anucene.2025.111697\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Crack propagation in the steam generator tubes are critical factor influencing the safe operation of nuclear power plants. Accurate prediction of crack growth behavior is vital for effective equipment health monitoring and maintenance. A fundamental framework and key technologies for the implementation of digital twin technology in nuclear power plants were presented in this study. And a novel crack propagation digital twin model generation technique for steam generator tubes was introduced, which integrates experimental data with extended finite element simulation results. Particle Filter method and reinforcement learning were conducted to evaluate respective strengths and limitations in crack propagation prediction. Both experimental data and extended finite element simulation data were incorporated into the model training process. The results demonstrated that both digital twin model generation techniques have distinct applicability conditions and high accuracy. This study could provide new insights and technological approaches for the health monitoring of steam generator tubes.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"224 \",\"pages\":\"Article 111697\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-07-05\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454925005146\",\"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":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925005146","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}
Digital twin model generation for crack propagation in steam generator tubes: Methods and implementation
Crack propagation in the steam generator tubes are critical factor influencing the safe operation of nuclear power plants. Accurate prediction of crack growth behavior is vital for effective equipment health monitoring and maintenance. A fundamental framework and key technologies for the implementation of digital twin technology in nuclear power plants were presented in this study. And a novel crack propagation digital twin model generation technique for steam generator tubes was introduced, which integrates experimental data with extended finite element simulation results. Particle Filter method and reinforcement learning were conducted to evaluate respective strengths and limitations in crack propagation prediction. Both experimental data and extended finite element simulation data were incorporated into the model training process. The results demonstrated that both digital twin model generation techniques have distinct applicability conditions and high accuracy. This study could provide new insights and technological approaches for the health monitoring of steam generator tubes.
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.