The SMR has become great interest to researchers in recent years. The integrated nuclear heating reactor NHR200 was developed by Institute of Nuclear and New Energy Technology (INET) in Tsinghua University. On the basis of the NHR200, the NHR200-II is developed. The thermal-hydraulic parameters in the primary loop such as temperature and pressure are increased, which make it more suitable for industrial steam supply and sea water desalinization. Because the primary loop of NHR200-II operates with fully natural circulation, it is necessary to investigate the natural circulation characteristics by experiment under new thermal parameters. In order to determine the characteristics scale of the test facility, the scaling analysis is needed. The similarity groups, including Richardson number, etc. are determined from the dimensionless fluid and solid governing equations. The test facility uses the fluid with same property as the prototype to reduce the distortion. The axial length scale ratio of the test facility is set to be 1:1. The analysis results of the core surface average heat flux density ratio and the flow area ratio are 1:1 and 1:210 respectively. At the end of this paper, the results of the scaling analysis are present.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5579-9
PROCEEDINGS PAPER
Results and Discussion on Scaling Analysis for the NHR200-II Integral Test Facility Under Single Phase Natural Circulation
Qianqian Jia,
Qianqian Jia
Tsinghua University, Beijing, China
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Haijun Jia,
Haijun Jia
Tsinghua University, Beijing, China
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Lei Wu
Lei Wu
Tsinghua University, Beijing, China
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Yang Liu
Tsinghua University, Beijing, China
Qianqian Jia
Tsinghua University, Beijing, China
Haijun Jia
Tsinghua University, Beijing, China
Lei Wu
Tsinghua University, Beijing, China
Paper No:
ICONE21-15659, V002T03A029; 4 pages
Published Online:
February 7, 2014
Citation
Liu, Y, Jia, Q, Jia, H, & Wu, L. "Results and Discussion on Scaling Analysis for the NHR200-II Integral Test Facility Under Single Phase Natural Circulation." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors. Chengdu, China. July 29–August 2, 2013. V002T03A029. ASME. https://doi.org/10.1115/ICONE21-15659
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