{"status":"ok","message-type":"work","message-version":"1.0.0","message":{"indexed":{"date-parts":[[2026,7,21]],"date-time":"2026-07-21T04:46:15Z","timestamp":1784609175354,"version":"3.55.0"},"reference-count":34,"publisher":"MDPI AG","issue":"12","license":[{"start":{"date-parts":[[2025,6,13]],"date-time":"2025-06-13T00:00:00Z","timestamp":1749772800000},"content-version":"vor","delay-in-days":0,"URL":"https:\/\/creativecommons.org\/licenses\/by\/4.0\/"}],"funder":[{"name":"Open Fund of the Key Laboratory of Nuclear Reactor System Design","award":["HT-KFKT-02-2017101"],"award-info":[{"award-number":["HT-KFKT-02-2017101"]}]}],"content-domain":{"domain":[],"crossmark-restriction":false},"short-container-title":["Sensors"],"abstract":"<jats:p>Aiming at the difficult problem of predicting the running state of the rotor of a Control Rod Drive Mechanism (CRDM) in a floating nuclear reactor, this paper proposes a Remaining Useful Life (RUL) prediction method based on Variational Mode Decomposition and Bidirectional Long Short-Term Memory (VMD-BiLSTM). Firstly, a bench experiment of the CRDM is carried out to collect the full operational cycle (full-stroke) vibration signals of the CRDM. Secondly, the collected data are decomposed based on the VMD, and the typical vibration signals at different stages of the experiment are used to verify this method and comprehensively mine the degradation characteristics. At the same time, the time-frequency domain feature analysis is carried out on the original vibration data, and the changing trends of the extracted features are carefully analyzed. Five feature quantities closely related to the degradation trend of the rotor of the CRDM are screened out, and the corresponding health indicators are constructed in combination with the stroke. Finally, the life prediction of the rotor of the CRDM is realized through the BiLSTM method. Then, the comparison experiments with other methods are carried out, and the experimental results show that the method proposed in this paper has high accuracy and reliability and can effectively solve the RUL prediction problem of CRDM, which provides a strong support to ensure the safe and stable operation of floating nuclear reactors.<\/jats:p>","DOI":"10.3390\/s25123702","type":"journal-article","created":{"date-parts":[[2025,6,13]],"date-time":"2025-06-13T03:53:12Z","timestamp":1749786792000},"page":"3702","update-policy":"https:\/\/doi.org\/10.3390\/mdpi_crossmark_policy","source":"Crossref","is-referenced-by-count":2,"title":["Research on Remaining Useful Life Prediction of Control Rod Drive Mechanism Rotor Components in Floating Nuclear Reactor"],"prefix":"10.3390","volume":"25","author":[{"given":"Liming","family":"Zhang","sequence":"first","affiliation":[{"name":"School of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China"},{"name":"Chongqing Pump Industry Co., Ltd., Chongqing 400030, China"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Chen","family":"Wang","sequence":"additional","affiliation":[{"name":"School of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Ling","family":"Chen","sequence":"additional","affiliation":[{"name":"School of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Tian","family":"Tan","sequence":"additional","affiliation":[{"name":"School of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China"}],"role":[{"vocabulary":"crossref","role":"author"}]},{"given":"Luqi","family":"Liao","sequence":"additional","affiliation":[{"name":"School of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China"}],"role":[{"vocabulary":"crossref","role":"author"}]}],"member":"1968","published-online":{"date-parts":[[2025,6,13]]},"reference":[{"key":"ref_1","doi-asserted-by":"crossref","first-page":"110398","DOI":"10.1016\/j.oceaneng.2021.110398","article-title":"A novel method for diagnosis and de-noising of control rod drive mechanism within floating nuclear reactor","volume":"244","author":"Zhang","year":"2022","journal-title":"Ocean Eng."},{"key":"ref_2","doi-asserted-by":"crossref","first-page":"151837","DOI":"10.1016\/j.jnucmat.2019.151837","article-title":"Materials for future nuclear energy systems","volume":"527","author":"Was","year":"2019","journal-title":"J. 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