Card fault diagnosis of the pressurized water reactor off-heap nuclear measurement system based on expert experience and convolutional neural network

Peng Jin, Jian Lu, Yue Guan, Pengfei Zhu, Ye Tian, Weijian Zhu, Jinmiao Ye, Linjun Xie
{"title":"Card fault diagnosis of the pressurized water reactor off-heap nuclear measurement system based on expert experience and convolutional neural network","authors":"Peng Jin, Jian Lu, Yue Guan, Pengfei Zhu, Ye Tian, Weijian Zhu, Jinmiao Ye, Linjun Xie","doi":"10.1088/1748-0221/19/07/p07019","DOIUrl":null,"url":null,"abstract":"\n The reactor nuclear measurement system is important in a\n nuclear power plant. Its main role is to measure the reactor's core\n power distribution using detectors and calibrate and provide data on\n the core fuel consumption. This study describes the lack of fault\n data and the lack of diagnostic methodology research in the\n overhauling process and fault diagnosis of the off-heap nuclear\n measurement system core card. This core card provides the detectors\n with the necessary working conditions. It also collects signals. In\n this study, we propose a methodology for the fault diagnosis of the\n card through circuit analysis, simulation of functional module\n division, fault data generation, and training of a convolutional\n neural network diagnostic model. The proposed methodology can\n transform the drawings into convenient diagnostic processes and\n algorithms based on expert experience. These drawings are difficult\n to use in actual overhauling conditions. The corresponding\n experimental equipment was designed for practical testing. The\n experimental results show that the accuracy of the obtained\n diagnostic model for classifying preset faults can reach 99.5%,\n indicating that this model can be applied in actual working\n conditions. The accuracy of the trained diagnostic model in\n classifying 13 kinds of faults in the training set during the actual\n test was tested. Results show that the accuracy rate is close to\n 100%. Moreover, the correction of the model using the real\n maintenance data in applying the actual maintenance conditions was\n also analyzed. The intelligent diagnostic system that centers on the\n fault diagnosis method investigated in this study has been applied\n in the pressurized water reactor off-heap nuclear measurement system\n digital transformation and upgrading project of Qinshan No. 2\n Plant.","PeriodicalId":507814,"journal":{"name":"Journal of Instrumentation","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2024-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Instrumentation","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1088/1748-0221/19/07/p07019","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

The reactor nuclear measurement system is important in a nuclear power plant. Its main role is to measure the reactor's core power distribution using detectors and calibrate and provide data on the core fuel consumption. This study describes the lack of fault data and the lack of diagnostic methodology research in the overhauling process and fault diagnosis of the off-heap nuclear measurement system core card. This core card provides the detectors with the necessary working conditions. It also collects signals. In this study, we propose a methodology for the fault diagnosis of the card through circuit analysis, simulation of functional module division, fault data generation, and training of a convolutional neural network diagnostic model. The proposed methodology can transform the drawings into convenient diagnostic processes and algorithms based on expert experience. These drawings are difficult to use in actual overhauling conditions. The corresponding experimental equipment was designed for practical testing. The experimental results show that the accuracy of the obtained diagnostic model for classifying preset faults can reach 99.5%, indicating that this model can be applied in actual working conditions. The accuracy of the trained diagnostic model in classifying 13 kinds of faults in the training set during the actual test was tested. Results show that the accuracy rate is close to 100%. Moreover, the correction of the model using the real maintenance data in applying the actual maintenance conditions was also analyzed. The intelligent diagnostic system that centers on the fault diagnosis method investigated in this study has been applied in the pressurized water reactor off-heap nuclear measurement system digital transformation and upgrading project of Qinshan No. 2 Plant.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
基于专家经验和卷积神经网络的压水堆堆外核测量系统卡故障诊断
反应堆核测量系统在核电站中非常重要。其主要作用是利用探测器测量反应堆堆芯功率分布,校准并提供堆芯燃料消耗数据。本研究介绍了堆外核测量系统核心卡检修过程和故障诊断中缺乏故障数据和诊断方法研究的情况。该核心卡为探测器提供必要的工作条件。它还负责收集信号。在本研究中,我们通过电路分析、功能模块划分仿真、故障数据生成和卷积神经网络诊断模型训练,提出了一种对该卡进行故障诊断的方法。所提出的方法可将图纸转化为基于专家经验的便捷诊断流程和算法。这些图纸在实际检修条件下很难使用。为进行实际测试,设计了相应的实验设备。实验结果表明,获得的诊断模型对预设故障分类的准确率可达 99.5%,表明该模型可应用于实际工况。在实际测试中,测试了训练诊断模型对训练集中 13 种故障进行分类的准确率。结果表明,准确率接近 100%。此外,还分析了在实际维护条件下使用真实维护数据对模型进行修正的情况。以本研究的故障诊断方法为核心的智能诊断系统已在秦山二厂压水堆堆外核测量系统数字化改造升级项目中得到应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 去求助
来源期刊
自引率
0.00%
发文量
0
期刊最新文献
Identification of material by X-ray fluorescence analysis with a pyroelectric X-ray generator Quasi-continuous re-binning of measured spectra and associated uncertainties Implementation of energy reduced 90Sr/90Y radiation fields, or: Propagation of beta radiation, a case study Evaluation of the activation of the radiation shielding of the LaDiff neutron triple-axis-spectrometer at FRM-II by simulation/calculation Calculation of efficiency and resolution of a hexagonal NaI(Tl) detector as a function of source position
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1