{"title":"Optimized ensemble of neural networks for the prediction of critical heat flux","authors":"Ibrahim Ahmed , Irene Gatti , Enrico Zio","doi":"10.1016/j.nucengdes.2025.114111","DOIUrl":null,"url":null,"abstract":"<div><div>Critical Heat Flux (CHF) is a thermal limit in boiling heat transfer, beyond which there is a substantial reduction in heat transfer efficiency. This phenomenon plays a vital role in the thermal engineering design of systems involving two-phase flow. As a result, an accurate CHF prediction is essential for both safety and performance, particularly in water-cooled nuclear reactors where thermohydraulic margins are critical. In this paper, a novel optimized ensemble of neural networks (NNs) for CHF prediction is proposed to enhance the accuracy of individual models trained separately with distinct architectures and hyperparameters settings. Two systematic procedures are presented to identify potentially optimal NN models and aggregate them into an optimal ensemble model. The proposed method is validated using experimental CHF data made available by the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) Expert Group on Reactor Systems Multi-Physics (EGMUP) task force on AI and ML for Scientific Computing in Nuclear Engineering projects, promoted by the OECD/NEA. The results obtained show that the ensemble model outperforms standalone models and other state-of-the-art modelling approaches. Parametric and sensitivity analyses across various input parameters confirm the robustness of the ensemble model and its consistency with expected physical behaviors, further underlying its potential for improving CHF prediction in nuclear reactor applications.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"439 ","pages":"Article 114111"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-06","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/S0029549325002882","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
Critical Heat Flux (CHF) is a thermal limit in boiling heat transfer, beyond which there is a substantial reduction in heat transfer efficiency. This phenomenon plays a vital role in the thermal engineering design of systems involving two-phase flow. As a result, an accurate CHF prediction is essential for both safety and performance, particularly in water-cooled nuclear reactors where thermohydraulic margins are critical. In this paper, a novel optimized ensemble of neural networks (NNs) for CHF prediction is proposed to enhance the accuracy of individual models trained separately with distinct architectures and hyperparameters settings. Two systematic procedures are presented to identify potentially optimal NN models and aggregate them into an optimal ensemble model. The proposed method is validated using experimental CHF data made available by the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) Expert Group on Reactor Systems Multi-Physics (EGMUP) task force on AI and ML for Scientific Computing in Nuclear Engineering projects, promoted by the OECD/NEA. The results obtained show that the ensemble model outperforms standalone models and other state-of-the-art modelling approaches. Parametric and sensitivity analyses across various input parameters confirm the robustness of the ensemble model and its consistency with expected physical behaviors, further underlying its potential for improving CHF prediction in nuclear reactor applications.
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.