控制棒驱动机构滚子状态评估及剩余使用寿命预测框架

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mengqi Huang , Zhengyu Du , Ruibo Lu , Xiaoji Wang , Changhong Peng
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引用次数: 0

摘要

控制棒驱动机构(CRDM)滚轮在环境和操作应力(包括温度、湿度、摩擦和冲击)下容易退化,如磨损和疲劳。为了能够及时诊断运行状态,预测未来的退化趋势,并支持运行控制和维护决策,本研究开发了一个CRDM轧辊状态评估和剩余使用寿命(RUL)预测框架。在状态评估阶段,采用残差分布分析与自适应邻域半径聚类相结合的方法对有限输入数据下的轧辊状态进行评估。在RUL预测阶段,构建基于粒子滤波的退化模型,通过极大似然和多目标优化估计参数,并利用贝叶斯理论和后向平滑进行校正,提高预测精度。在轴承数据集上的验证获得了退化起始估计偏差小于3个时间步长的结果,RUL预测误差为8.19%。同时,将该方法应用于CRDM轧辊,误差为8.96%。这些结果证实了该框架能够利用实时监测数据进行准确的状态诊断和精确的RUL预测。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A framework for state assessment and remaining useful life prediction of control rod drive mechanism roller
The control rod drive mechanism (CRDM) roller is susceptible to degradation, such as wear and fatigue, under environmental and operational stresses, including temperature, humidity, friction, and impact. To enable timely operating state diagnosis, predict future degradation trends, and support operation control and maintenance decisions, this study develops a framework for CRDM roller state assessment and remaining useful life (RUL) prediction. In the state assessment stage, residual distribution analysis combined with adaptive neighbourhood radius clustering is employed to evaluate roller states under limited input data. In the RUL prediction stage, a particle filter-based degradation model is constructed, with parameters estimated via maximum likelihood and multi-objective optimization, and further corrected using Bayesian theory and backward smoothing to enhance prediction accuracy. Validation on bearing datasets achieved a degradation onset estimation deviation of less than three time steps and a RUL prediction error of 8.19%. At the same time, the application to the CRDM roller yielded an error of 8.96%. These results confirm the framework’s capability for accurate state diagnosis and precise RUL prediction using real-time monitoring data.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
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.
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