The flow rate can fluctuate in offshore nuclear power systems which are exposed to wind and waves, as well as in loops where flow instabilities occur, resulting in different thermal-hydraulic characteristics compared with that under steady flow. Among the thermal-hydraulic characteristics, onset of nucleate boiling (ONB) model determines whether the fluid is boiling, and boiling heat transfer is crucial to equipment performance and safety, both being key issues in subcooled flow boiling. Therefore, an experimental study was conducted to investigate how an imposed periodic flow oscillation affects the boiling inception and heat transfer of subcooled flow boiling of water in a vertical tube. The experiments were conducted under atmospheric pressure with the average flow rate ranging from 96kg/m2s to 287kg/m2s and heat flux ranging from 10kW/m2 to 197kW/m2. The relative pulsatile amplitude range is 0.1–0.3 and pulsatile period range is 10s-30s. Photographic images and thermal parameters such as temperatures and flow rate were recorded. The lack of nucleation site on the heated surface of the test section results in high wall superheat at ONB. The effects of pulsatile amplitude and period on superheat at boiling onset and average heat transfer were analyzed. The results show that the superheat at boiling inception is decreased when the average heat flux is lower than the heat flux at boiling inception of the corresponding steady flow, and the superheat at boiling onset is increased when the average heat flux is higher than the heat flux at boiling onset of the corresponding steady flow. The above effect of flow rate pulsation on superheat increases with increasing amplitude and decreasing period, and the mechanism can be explained by boiling nucleation theory. The lack of large active nucleation site also affects the boiling heat transfer. By comparing the contribution of nucleate boiling to heat transfer with the widely used Cooper’s pool boiling correlation, the subcooled flow boiling was found suppressed by convection. The average heat transfer of both the intermittent flow boiling and the single phase flow is influenced by flow oscillation.
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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
Subcooled Flow Boiling Inception and Heat Transfer of Water in a Circular Tube Under Pulsatile Flow
Hongsheng Yuan,
Hongsheng Yuan
Nuclear Power Institute of China, Chengdu, China
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Sichao Tan,
Sichao Tan
Harbin Engineering University, Harbin, China
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Kun Cheng,
Kun Cheng
Harbin Engineering University, Harbin, China
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Xiaoli Wu,
Xiaoli Wu
Nuclear Power Institute of China, Chengdu, China
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Chao Guo,
Chao Guo
Nuclear Power Institute of China, Chengdu, China
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Mingjun Zhong
Mingjun Zhong
Nuclear Power Institute of China, Chengdu, China
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Hongsheng Yuan
Nuclear Power Institute of China, Chengdu, China
Sichao Tan
Harbin Engineering University, Harbin, China
Kun Cheng
Harbin Engineering University, Harbin, China
Xiaoli Wu
Nuclear Power Institute of China, Chengdu, China
Chao Guo
Nuclear Power Institute of China, Chengdu, China
Mingjun Zhong
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE26-81476, V06AT08A046; 7 pages
Published Online:
October 24, 2018
Citation
Yuan, H, Tan, S, Cheng, K, Wu, X, Guo, C, & Zhong, M. "Subcooled Flow Boiling Inception and Heat Transfer of Water in a Circular Tube Under Pulsatile Flow." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A046. ASME. https://doi.org/10.1115/ICONE26-81476
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