{"title":"Investigation of ensemble Kalman filter-based data assimilation for turbulent flow in a 3×3 rod bundle","authors":"Yuguan Jin , Guangliang Chen , Zhaofei Tian","doi":"10.1016/j.net.2025.103899","DOIUrl":null,"url":null,"abstract":"<div><div>Computational Fluid Dynamics (CFD) has advanced rapidly in reactor core thermal-hydraulics, serving as a vital tool for nuclear reactor safety and performance analysis. This study addresses uncertainties in complex turbulence simulations within reactor cores, proposing a novel approach to optimize Reynolds-Averaged Navier-Stokes (RANS) models using the Ensemble Kalman Filter (EnKF) data assimilation method. By simulating turbulent flow in a 3 × 3 rod bundle channel and using time-averaged velocity fields from Particle Image Velocimetry (PIV) as observational data, an observation operator maps local velocity measurements to full-field turbulence parameters, optimizing key RANS closure parameters. Results show that the EnKF-optimized RANS model significantly improves the accuracy of velocity and turbulent kinetic energy predictions, with relative errors below 1 % in most regions, outperforming the original model. This approach provides a data-driven optimization paradigm for high-fidelity reactor thermal-hydraulic simulations, supporting complex confined turbulence modeling and multi-physics coupling analysis. However, further validation is needed to explore additional factors affecting assimilation performance in nuclear reactor systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 2","pages":"Article 103899"},"PeriodicalIF":2.6000,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S173857332500467X","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
Computational Fluid Dynamics (CFD) has advanced rapidly in reactor core thermal-hydraulics, serving as a vital tool for nuclear reactor safety and performance analysis. This study addresses uncertainties in complex turbulence simulations within reactor cores, proposing a novel approach to optimize Reynolds-Averaged Navier-Stokes (RANS) models using the Ensemble Kalman Filter (EnKF) data assimilation method. By simulating turbulent flow in a 3 × 3 rod bundle channel and using time-averaged velocity fields from Particle Image Velocimetry (PIV) as observational data, an observation operator maps local velocity measurements to full-field turbulence parameters, optimizing key RANS closure parameters. Results show that the EnKF-optimized RANS model significantly improves the accuracy of velocity and turbulent kinetic energy predictions, with relative errors below 1 % in most regions, outperforming the original model. This approach provides a data-driven optimization paradigm for high-fidelity reactor thermal-hydraulic simulations, supporting complex confined turbulence modeling and multi-physics coupling analysis. However, further validation is needed to explore additional factors affecting assimilation performance in nuclear reactor systems.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development