{"title":"基于预测梯度和残差FCN的3DVar数据同化在核电厂主蒸汽系统参数反演优化中的应用","authors":"Xiaoyu Luo , Sheng Zheng , Dazhi Zhang , Xian Zhang , Shanglong Huang","doi":"10.1016/j.nucengdes.2025.114170","DOIUrl":null,"url":null,"abstract":"<div><div>The main steam system is crucial for the safety of nuclear power plants, and predicting its operating parameters is essential for monitoring system performance and improving energy efficiency. Since the damping coefficients in steam pipes cannot be directly measured, numerical simulations are typically used. However, model simplifications and uncertainties in modeling parameters lead to discrepancies between the simulations and actual. To address this issue, we propose ResFCN-3DVar, a novel data assimilation method that optimizes modeling parameters using observable quantities. The primary innovation lies in leveraging a residual-based fully connected network (ResFCN) to construct the observation operator, effectively handling the nonlinear and complex system-level model. Additionally, we incorporate a second-order finite difference matrix within the 3DVar framework to improve computational efficiency. Experiments using a dataset simulated by the full-scope simulator showed that the root-mean-square error (RMSE) of the assimilation results remained below 1%, demonstrating the effectiveness of ResFCN-3DVar in optimizing modeling parameters.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"441 ","pages":"Article 114170"},"PeriodicalIF":2.1000,"publicationDate":"2025-06-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"3DVar data assimilation for inversion optimization of main steam system parameters in nuclear power plants using forecast-gradient and residual FCN\",\"authors\":\"Xiaoyu Luo , Sheng Zheng , Dazhi Zhang , Xian Zhang , Shanglong Huang\",\"doi\":\"10.1016/j.nucengdes.2025.114170\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The main steam system is crucial for the safety of nuclear power plants, and predicting its operating parameters is essential for monitoring system performance and improving energy efficiency. Since the damping coefficients in steam pipes cannot be directly measured, numerical simulations are typically used. However, model simplifications and uncertainties in modeling parameters lead to discrepancies between the simulations and actual. To address this issue, we propose ResFCN-3DVar, a novel data assimilation method that optimizes modeling parameters using observable quantities. The primary innovation lies in leveraging a residual-based fully connected network (ResFCN) to construct the observation operator, effectively handling the nonlinear and complex system-level model. Additionally, we incorporate a second-order finite difference matrix within the 3DVar framework to improve computational efficiency. Experiments using a dataset simulated by the full-scope simulator showed that the root-mean-square error (RMSE) of the assimilation results remained below 1%, demonstrating the effectiveness of ResFCN-3DVar in optimizing modeling parameters.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"441 \",\"pages\":\"Article 114170\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-06-05\",\"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/S0029549325003474\",\"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/S0029549325003474","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}
3DVar data assimilation for inversion optimization of main steam system parameters in nuclear power plants using forecast-gradient and residual FCN
The main steam system is crucial for the safety of nuclear power plants, and predicting its operating parameters is essential for monitoring system performance and improving energy efficiency. Since the damping coefficients in steam pipes cannot be directly measured, numerical simulations are typically used. However, model simplifications and uncertainties in modeling parameters lead to discrepancies between the simulations and actual. To address this issue, we propose ResFCN-3DVar, a novel data assimilation method that optimizes modeling parameters using observable quantities. The primary innovation lies in leveraging a residual-based fully connected network (ResFCN) to construct the observation operator, effectively handling the nonlinear and complex system-level model. Additionally, we incorporate a second-order finite difference matrix within the 3DVar framework to improve computational efficiency. Experiments using a dataset simulated by the full-scope simulator showed that the root-mean-square error (RMSE) of the assimilation results remained below 1%, demonstrating the effectiveness of ResFCN-3DVar in optimizing modeling parameters.
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.