The blanket assemblies of China Experimental Fast Reactor (CEFR) were specially designed for the purpose of fuel breeding. There are two parts of the blanket assembly that have significant influence on its thermal-hydraulic feature: the labyrinth throttle set and the wire-wrapped fuel bundle. In this paper, the flow and temperature distribution of sodium coolant in fuel bundle, as well as the pressure drop in the labyrinth throttle set were investigated by solving the three-dimensional conservation equations of mass, momentum and energy, for a wide range of Reynolds number. Different turbulent models: k-ε, SST and Reynolds stress model (RSM) were used and compared with experimental correlations in the study of fuel bundle. The cross flow strength in three typical sub-channels and the influence of steer rods were also investigated. It has been found that the SST model fits best with the experimental correlation and although dampened the cross flow in edge channel, the steel rods installed in the hexagonal duct could enhance the heat transfer by “pushing” the sodium coolant to inner channel of the fuel bundle. Moreover, the relationship between the slot width of the labyrinth throttle set and the pressure drop under different coolant mass flow rate was analyzed, and found out the slot width that satisfied the design requirement of the blanket assembly.
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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
Thermal-Hydraulic Study of Wire-Wrapped Blanket Assembly of CEFR
Yang Liu,
Yang Liu
China Institute of Atomic Energy, Beijing, China
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Hong Yu,
Hong Yu
China Institute of Atomic Energy, Beijing, China
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Yizhe Liu
Yizhe Liu
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Yang Liu
China Institute of Atomic Energy, Beijing, China
Hong Yu
China Institute of Atomic Energy, Beijing, China
Yizhe Liu
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE21-15739, V002T05A018; 8 pages
Published Online:
February 7, 2014
Citation
Liu, Y, Yu, H, & Liu, Y. "Thermal-Hydraulic Study of Wire-Wrapped Blanket Assembly of CEFR." 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. V002T05A018. ASME. https://doi.org/10.1115/ICONE21-15739
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