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Research on the Development Technology of Remaining UsefulLife Prediction Model for Reactor Coolant Pump Bearings
编号：27 访问权限：仅限参会人 更新：2025-06-15 09:08:00 浏览：12次 口头报告

报告开始：暂无开始时间（Asia/Shanghai）

报告时间：暂无持续时间

所在会场：[暂无会议] [暂无会议段]

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摘要
Aiming at the problems that the theoretical calculation model for predicting the remaining life of main pump bearings is difficult to be established accurately and that the predictive maintenance lacks practical life assessment means, this study proposes and constructs a set of data-driven life assessment model for main pump bearings, which makes use of the data from the operating status of the bearings to preliminarily determine whether the bearings are worn out or not. Then a model for calculating the wear rate of bearings operating in the boundary lubrication region is used to estimate the total wear of bearings when they are continuously working in the wear-prone region, based on the wear rate of bearings operating in the boundary lubrication region. In addition, this study also considers the wear rate of bearings during the start-up and stopping phases, and evaluates the cumulative wear over the entire range of operating durations by using a model for calculating the wear rate of bearings during the start-up and stopping phases. This study provides an important technical support for subsequent predictive maintenance of rotating equipment, which can significantly improve operational safety and efficiency.
 
关键词
reactor coolant pump; thrust bearing; remaining useful life; predictive maintenance
报告人
Renyi Xu
Engineer Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China

稿件作者
Yan Wang College of Electronics and Information Engineering Sichuan University
Renyi Xu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
Jianyong Lai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
Chengxiao Kuang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
Shu Su Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
Xin Tan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
Ning Zhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
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重要日期

  • 会议日期

    08月01日

    2025

    至

    08月04日

    2025

  • 06月23日 2025

    初稿截稿日期

主办单位
中国机械工程学会设备智能运维分会
承办单位
新疆大学
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