During a LOCA accident, the debris caused by the action of high energy fluid discharged from the break may transport to the containment sump, then may be entrained into the core by the ECCS water. The debris may cause the blockage of fuel assembly. The air may also enter the reactor with water. Numerical simulations are performed to analyze the air-water flow and particle-water flow through the blocked fuel assembly. The pressure drop in fuel assembly will impact the long-term core cooling capability. The effects of different parameters on the pressure drop over the fuel assembly are analyzed. Pressure drop increases as blockage percentage, mass flow rate or inlet velocity increases for both two-phase flow. The decrease of air volume fraction and the increase of particle volume fraction all cause the increase of pressure drop. Pressure drop increases slightly as bubble diameter increases, and the tiny effect of particle diameter on pressure drop was found as particle diameter varying at an increment of 10um.
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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
Numerical Simulations of Two-Phase Flow in a Fuel Assembly of Blockage due to LOCA
Jingwen Ren,
Jingwen Ren
North China Electric Power University, Beijing, China
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Fenglei Niu,
Fenglei Niu
North China Electric Power University, Beijing, China
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Weiqian Zhuo,
Weiqian Zhuo
North China Electric Power University, Beijing, China
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Da Wang
Da Wang
North China Electric Power University, Beijing, China
Search for other works by this author on:
Jingwen Ren
North China Electric Power University, Beijing, China
Fenglei Niu
North China Electric Power University, Beijing, China
Weiqian Zhuo
North China Electric Power University, Beijing, China
Da Wang
North China Electric Power University, Beijing, China
Paper No:
ICONE25-66729, V008T09A026; 10 pages
Published Online:
October 17, 2017
Citation
Ren, J, Niu, F, Zhuo, W, & Wang, D. "Numerical Simulations of Two-Phase Flow in a Fuel Assembly of Blockage due to LOCA." 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. V008T09A026. ASME. https://doi.org/10.1115/ICONE25-66729
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