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

Peng Jin, Jian Lu, Yue Guan, Pengfei Zhu, Ye Tian, Weijian Zhu, Jinmiao Ye, Linjun Xie
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引用次数: 0

摘要

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