When fast reactor is operation, because of scouring by high pressure liquid coolant in fuel assembly, there are a lot of products in coolant channel. Using FLUENT software simulate deposition of insoluble particle in fast reactor. Using standard k-ε model predict flow field and turbulence intensity of fluid phase. Using discrete phase model track the trajectory of insoluble particle. The following are simulation results. Fuel cladding deposits lots of insoluble particle, but the concentration of insoluble particle is lower at the central of coolant; Entrance section of the insoluble particle concentration is higher than exit section; Dot deposition of insoluble particle at outlet of fuel cladding will lead to pitting phenomenon, pitting will cause deterioration of heat transfer and destroy the integrity of cladding. In view of deposition law of insoluble particle and characteristic of fuel assembly, mitigation measures of cleaning insoluble particle at fixed time and fixed position are being proposed.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5786-1
PROCEEDINGS PAPER
Simulating Fine Particle Deposition in Coolant Channel of Fast Reactor
Yaoxin Wang,
Yaoxin Wang
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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Bing Li
Bing Li
North China Electric Power University, Beijing, China
Search for other works by this author on:
Yaoxin Wang
North China Electric Power University, Beijing, China
Tao Zhou
North China Electric Power University, Beijing, China
Bing Li
North China Electric Power University, Beijing, China
Paper No:
ICONE25-66450, V008T09A013; 3 pages
Published Online:
October 17, 2017
Citation
Wang, Y, Zhou, T, & Li, B. "Simulating Fine Particle Deposition in Coolant Channel of Fast Reactor." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues. Shanghai, China. July 2–6, 2017. V008T09A013. ASME. https://doi.org/10.1115/ICONE25-66450
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