In ADS reactor which choose LBE (Lead-Bismuth Eutectic) as coolant and spallation target. While SGTR (Steam Generator Tube Rupture) accident occur, water in secondary side will inject to LBE in primary coolant, and flow with LBE. The code of FLUENT will be used, steam is looked as particle, and standard k-ε model is used to predict turbulence variation of continuous phase in core. The DPM (Discrete Phase Model) will be used to track the trajectory of the particles. The distribution of steam in core will be obtained, which will verify the safety of reactor. The results show that the steam flowing across the core with LBE, might accumulate in some position and cause a surge of power. At the same time, the aggregation of steam at the channel might lead to a steam plug, and hinder the flow of the coolant in core, then core overheating might occur. Last but not least, local accumulation of water vapor may accelerate the corrosion of stainless steel material in core.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4594-3
PROCEEDINGS PAPER
Numerical Simulation of Steam Generator Tube Rupture Sequence in ADS Reactor
Xu Yang,
Xu Yang
North China Electric Power University, Beijing, China
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Tao Zhou,
Tao Zhou
North China Electric Power University, Beijing, China
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Daping Lin,
Daping Lin
North China Electric Power University, Beijing, China
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Xiaolu Fang,
Xiaolu Fang
North China Electric Power University, Beijing, China
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Baixu Chen,
Baixu Chen
North China Electric Power University, Beijing, China
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Xiaolong Ru
Xiaolong Ru
North China Electric Power University, Beijing, China
Search for other works by this author on:
Xu Yang
North China Electric Power University, Beijing, China
Tao Zhou
North China Electric Power University, Beijing, China
Daping Lin
North China Electric Power University, Beijing, China
Xiaolu Fang
North China Electric Power University, Beijing, China
Baixu Chen
North China Electric Power University, Beijing, China
Xiaolong Ru
North China Electric Power University, Beijing, China
Paper No:
ICONE22-30187, V004T10A005; 5 pages
Published Online:
November 17, 2014
Citation
Yang, X, Zhou, T, Lin, D, Fang, X, Chen, B, & Ru, X. "Numerical Simulation of Steam Generator Tube Rupture Sequence in ADS Reactor." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. Prague, Czech Republic. July 7–11, 2014. V004T10A005. ASME. https://doi.org/10.1115/ICONE22-30187
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