The CPR1000 is built and operated by the China Guangdong Nuclear Power Company (CGNPC). The flow features are very complicated and asymmetrical in three dimensions. In this study, we calculated the completed model without symmetry simplification using CFD method. 3-dimensional, global and localized flow distributions of full vessel of CPR1000 PWR including top plenum, upper plenum, lower plenum and flow features under different working conditions for safety analyses have been obtained. Unsymmetrical flow field indicates the necessarily of intact vessel mode calculation and simplifications of guide tubes and core make it possible under the condition of our lab. Thermal hydraulics characteristics are obtained to give reference to safety operation under various operating conditions.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Thermal Hydraulics Characteristics Simulation of CPR1000 Using CFD Method
Yanmeng Chao
,
Yanmeng Chao
Beijing Jiaotong University, Beijing, China
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Yujia Zhai
,
Yujia Zhai
Beijing Jiaotong University, Beijing, China
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Lixin Yang
,
Lixin Yang
Beijing Jiaotong University, Beijing, China
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Mingqian Zhang
,
Mingqian Zhang
China Nuclear Power Design Company, Ltd., Shenzhen, Guangdong, China
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Yuangang Duan
Yuangang Duan
China Nuclear Power Design Company, Ltd., Shenzhen, Guangdong, China
Search for other works by this author on:
Yanmeng Chao
Beijing Jiaotong University, Beijing, China
Yujia Zhai
Beijing Jiaotong University, Beijing, China
Lixin Yang
Beijing Jiaotong University, Beijing, China
Mingqian Zhang
China Nuclear Power Design Company, Ltd., Shenzhen, Guangdong, China
Yuangang Duan
China Nuclear Power Design Company, Ltd., Shenzhen, Guangdong, China
Paper No:
ICONE21-16591, V004T09A107; 6 pages
Published Online:
February 7, 2014
Citation
Chao, Y, Zhai, Y, Yang, L, Zhang, M, & Duan, Y. "Thermal Hydraulics Characteristics Simulation of CPR1000 Using CFD Method." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A107. ASME. https://doi.org/10.1115/ICONE21-16591
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