171 / 2025-06-11 12:43:26
Probabilistic Characterization Methodology for Nuclear Main Pump Mechanical Seals Under Constrained Sensor Deployment Conditions
nuclear main pump,mechanical seal,health monitoring,probabilistic model
全文录用
Yuan Yin / Department of Mechanical Engineering, Tsinghua University, Beijing 100084, China; State Key Laboratory of Tribology in Advanced Equipment, Tsinghua University, Beijing 100084, China
Shengjie Li / State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co. Ltd., Shenzhen, Guangdong, 518172, China
Fengming Hu / Department of Mechanical Engineering, Tsinghua University, Beijing 100084, China; State Key Laboratory of Tribology in Advanced Equipment, Tsinghua University, Beijing 100084, China
Xingjiang Chen / State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co. Ltd., Shenzhen, Guangdong, 518172, China
Weifeng Huang / State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co. Ltd., Shenzhen, Guangdong, 518172, China
Based on considerations such as structural compactness and safety, the monitoring points set for nuclear main pump mechanical seals are often insufficient to fully describe the operational condition of the seals, especially with regard to the specific status of each sealing stage. This paper utilizes a limited number of sensor points and establishes a probabilistic model to characterize the mechanical seal condition in the form of parameter distributions, which supports the rapid identification of locations with high failure probability while simultaneously displaying the degree of certainty in the results. The method is validated using real operational data from a nuclear power unit over approximately one year (including parameters such as differential pressure, flow rate, etc.). The results indicate that the fault diagnosis conclusions derived from the algorithm are highly consistent with the shutdown maintenance records and measured low-pressure leakage flow rate data. This approach not only effectively overcomes the limitations of insufficient monitoring information, but also provides reliable technical support for the health monitoring and fault tracing of nuclear main pump mechanical seals.
重要日期
  • 会议日期

    08月01日

    2025

    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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