The operating performance and safety characteristics of canned motor Reactor Coolant Pump (RCP) are vital to the nuclear reactor. The annular flow, which is between the rotor and stator, makes substantial effects on the rotordynamic characteristics of RCP. In this work, the annular flow is simulated by means of 3-dimensional CFD approaches. The annular flow field and the auxiliary impeller are modeled. The results show that the pre-swirl strength at the inlet of the annular flow is evident. Another model without the auxiliary impeller is analyzed under constant pre-swirl ratio with various axial flow rates and whirl speeds. The rotordynamic coefficients of the annular flow are obtained. The results are compared with theoretical predictions. Numerical results show that the fluid in the annular region makes remarkable effects on the rotordynamic characteristics of the canned motor RCP.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4589-9
PROCEEDINGS PAPER
Numerical Analysis of Rotordynamic Coefficients of Annular Flow in Canned Motor RCP
Yaoyu Hu,
Yaoyu Hu
Shanghai Jiao Tong University, Shanghai, China
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Dezhong Wang,
Dezhong Wang
Shanghai Jiao Tong University, Shanghai, China
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Junlian Yin,
Junlian Yin
Shanghai Jiao Tong University, Shanghai, China
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Yujin Wang
Yujin Wang
Shanghai Jiao Tong University, Shanghai, China
Search for other works by this author on:
Yaoyu Hu
Shanghai Jiao Tong University, Shanghai, China
Dezhong Wang
Shanghai Jiao Tong University, Shanghai, China
Junlian Yin
Shanghai Jiao Tong University, Shanghai, China
Yujin Wang
Shanghai Jiao Tong University, Shanghai, China
Paper No:
ICONE22-30511, V001T03A018; 10 pages
Published Online:
November 17, 2014
Citation
Hu, Y, Wang, D, Yin, J, & Wang, Y. "Numerical Analysis of Rotordynamic Coefficients of Annular Flow in Canned Motor RCP." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T03A018. ASME. https://doi.org/10.1115/ICONE22-30511
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