Coolant injection mode of molten fuel and coolant interaction (FCI) is a key issue during steam generator tube rupture accident (SGTR) in liquid metal reactors. In the present study the hydraulic breakup behavior of coolant injection mode is investigated using experimental and numerical approaches. Visual experiments are conducted using low-density gasoline as coolant jet and high-density water as denser liquid. The gasoline jet is released into a transparent water tank through a nozzle. The jet breakup behaviors are captured by a DSLR (digital single-lens relax) camera. The images of jet behaviors and the data of gasoline jet penetration depth are obtained and analyzed. By changing nozzle diameter and nozzle height, the parameter effect of jet diameter and jet inlet velocity on final penetration depth are studied. Based on FLUENT15.0, the hydraulic breakup behaviors of gasoline jet are simulated. A 3D axisymmetric model is built and Volume of Fluid (VOF) method is used. The numerical simulation results agree with the experimental results quantitatively and qualitatively. These experimental images and data are helpful to substantiate the understanding of the coolant jet breakup behavior and the pattern of jet penetration depth.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
Study on Final Depth Under Hydraulic Coolant Penetration Condition
Jingtan Chen,
Jingtan Chen
Sichuan University, Chengdu, China
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Qingyu Huang,
Qingyu Huang
Sichuan University, Chengdu, China
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Houjun Gong
Houjun Gong
Nuclear Power Institute of China, Chengdu, China
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Yuan Zhou
Sichuan University, Chengdu, China
Jingtan Chen
Sichuan University, Chengdu, China
Qingyu Huang
Sichuan University, Chengdu, China
Houjun Gong
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE25-66267, V006T08A019; 7 pages
Published Online:
October 17, 2017
Citation
Zhou, Y, Chen, J, Huang, Q, & Gong, H. "Study on Final Depth Under Hydraulic Coolant Penetration Condition." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A019. ASME. https://doi.org/10.1115/ICONE25-66267
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