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Online Stress Corrosion Crack Monitoring in Nuclear Reactor Components Using Active Ultrasonic Sensor Networks and Nonlinear System Identification - Data Fusion Based Big Data Analytics Approach

机译:基于有源超声传感器网络和非线性系统识别的核反应堆组件在线应力腐蚀裂纹监测-基于数据融合的大数据分析方法

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The current state of the art nondestructive evaluation (NDE) techniques used in nuclear reactor structural inspection are manual labor intensive, time consuming, and only used when the reactor has been shut down. Also, despite periodic inspection of plant components, a failure mode such as stress corrosion crack can initiate in between two scheduled inspections and can become critical before the next scheduled inspection. In this context, real time monitoring of nuclear reactor components is necessary for continuous and autonomous monitoring of component structural health. In this research, an active ultrasonic based on-line monitoring (OLM) framework is developed which can be used for real-time monitoring of degradation of nuclear power plant systems, structures, and components. Nonlinear system identification technique such as Bayesian Gaussian Process technique method is investigated to estimate the structural degradation in realtime. Active broadband ultrasound input is used for damage interrogation and a multi-sensor configuration is implemented to improve spatial resolution of state estimation. The damage index at any particular time is computed using nonlinear techniques such as Gaussian Process probabilistic modeling and the necessity of sensor data fusion is evaluated. The framework was demonstrated through the monitoring of an anomaly trend in a nuclear reactor steam generator tube undergoing stress corrosion cracking (SCC) testing.
机译:核反应堆结构检查中使用的最新技术无损评估(NDE)技术是费力的劳动,费时,并且仅在反应堆已经关闭时使用。另外,尽管定期检查设备组件,但诸如应力腐蚀裂纹之类的故障模式可能会在两次预定的检查之间启动,并且在下一次预定的检查之前可能变得很关键。在这种情况下,对核反应堆组件进行实时监视对于连续和自主地监视组件结构健康是必要的。在这项研究中,开发了一种基于超声波的有源在线监测(OLM)框架,该框架可用于实时监测核电站系统,结构和组件的退化。研究了诸如贝叶斯高斯过程技术方法之类的非线性系统识别技术,以实时估计结构退化。有源宽带超声输入用于损伤询问,并且实现了多传感器配置以提高状态估计的空间分辨率。使用非线性技术(例如高斯过程概率模型)计算在任何特定时间的损坏指数,并评估传感器数据融合的必要性。该框架是通过监测经受应力腐蚀开裂(SCC)测试的核反应堆蒸汽发生器管的异常趋势来证明的。

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