Wei Zhang , Junsen Fu , Shuo Chen , Lijun Yu , Yao Xiao , Hanyang Gu
{"title":"Investigation of a hybrid neural network framework for CHF prediction in a wire-wrapped rod bundle","authors":"Wei Zhang , Junsen Fu , Shuo Chen , Lijun Yu , Yao Xiao , Hanyang Gu","doi":"10.1016/j.anucene.2025.111804","DOIUrl":null,"url":null,"abstract":"<div><div>While predicting critical heat transfer in rod bundles is crucial for reactor safety analysis, most of the existing methods fall short in achieving a balance between accuracy and generalization. Utilizing machine learning algorithms, the hybrid neural network framework was applied to explore prediction methods for critical heat transfer in a wire-wrapped rod bundle. It is concluded that the improvement of the prior model will lead to a better estimation result. Besides, with a larger size, the neural network will certainly improve the estimation performance, but it tends to sacrifice the mean of the data to optimize the variance. The hybrid prediction method, moreover, also has a satisfactory error characteristic at different neural network sizes. Besides, the learning preference of the neural network was also analyzed to elucidate the advantages of hybrid prediction methods. This study proposes and verifies an improved scheme for critical prediction methods which has an outstanding prediction performance over traditional fitting and standalone FCNN. Work facilitates the application of machine learning algorithms in thermal–hydraulic engineering..</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111804"},"PeriodicalIF":2.3000,"publicationDate":"2025-08-16","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/S0306454925006218","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
While predicting critical heat transfer in rod bundles is crucial for reactor safety analysis, most of the existing methods fall short in achieving a balance between accuracy and generalization. Utilizing machine learning algorithms, the hybrid neural network framework was applied to explore prediction methods for critical heat transfer in a wire-wrapped rod bundle. It is concluded that the improvement of the prior model will lead to a better estimation result. Besides, with a larger size, the neural network will certainly improve the estimation performance, but it tends to sacrifice the mean of the data to optimize the variance. The hybrid prediction method, moreover, also has a satisfactory error characteristic at different neural network sizes. Besides, the learning preference of the neural network was also analyzed to elucidate the advantages of hybrid prediction methods. This study proposes and verifies an improved scheme for critical prediction methods which has an outstanding prediction performance over traditional fitting and standalone FCNN. Work facilitates the application of machine learning algorithms in thermal–hydraulic engineering..
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.