An experimental investigation was conducted in a natural circulation (NC) loop to study the characteristics of two-phase flow instability under low pressure condition. A 3 × 3 rod bundle channel was used as the test section. The effects of heating power, inlet subcooling degree and system pressure on the two-phase NC flow instability types and stable boundaries were studied. The experimental results show that three typical flow conditions can occur in rod bundle channel under NC condition, which are single-phase NC flow, subcooled boiling NC flow oscillation and density wave oscillations (DWO). The oscillation amplitude and period of DWO can be enlarged by increasing the heat flux. Increasing the inlet subcooling degree can increase the marginal heating power of flow instability in NC system. The occurrence of DWO can be suppressed by increasing the system pressure. The flow instability boundary presented by the subcooling number and phase change number was also obtained in present work.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5148-7
PROCEEDINGS PAPER
Experimental Study on Two-Phase Natural Circulation Flow Instability in Rod Bundle Channel Under Low Pressure Condition
Kun Cheng,
Kun Cheng
Harbin Engineering University, Harbin, China
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Sichao Tan,
Sichao Tan
Harbin Engineering University, Harbin, China
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Zheng Liu,
Zheng Liu
Harbin Engineering University, Harbin, China
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Tao Meng
Tao Meng
Harbin Engineering University, Harbin, China
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Kun Cheng
Harbin Engineering University, Harbin, China
Sichao Tan
Harbin Engineering University, Harbin, China
Zheng Liu
Harbin Engineering University, Harbin, China
Tao Meng
Harbin Engineering University, Harbin, China
Paper No:
ICONE26-81225, V06AT08A017; 6 pages
Published Online:
October 24, 2018
Citation
Cheng, K, Tan, S, Liu, Z, & Meng, T. "Experimental Study on Two-Phase Natural Circulation Flow Instability in Rod Bundle Channel Under Low Pressure Condition." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A017. ASME. https://doi.org/10.1115/ICONE26-81225
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