Degradation‐based reliability analysis of magnetic jack type control rod drive mechanism
Author:
Affiliation:
1. State Key Laboratory of Power Transmission Equipment & System Security and New Technology Chongqing University Chongqing China
2. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
Publisher
Wiley
Subject
Management Science and Operations Research,Safety, Risk, Reliability and Quality
Link
https://onlinelibrary.wiley.com/doi/pdf/10.1002/qre.3148
Reference35 articles.
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3. A novel method for diagnosis and de‐noising of control rod drive mechanism within floating nuclear reactor;Zhang L;Ocean Eng,2022
4. Modelling of primary water stress corrosion cracking (PWSCC) at control rod drive mechanism (CRDM) nozzles of pressurized water reactors (PWR)
5. Predicting the impact of CRDM thermal sleeve flange wear in Westinghouse pressurized water reactors;Rudland DL;J Pressure Vessel Technol,2021
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