The Design and CFD Simulation of a New Spent Fuel Pool Passive Cooling System

Author(s):  
Cheng Ye ◽  
Minglu Wang ◽  
Mingguang Zheng ◽  
Zhengqin Xiong ◽  
Ronghua Zhang

Due to the safety issues arising from the Fukushima accident, a novel completely passive spent fuel pool cooling system is proposed using the high-efficiency heat pipe cooling technology that is available in an emergency condition such as a station blackout. This cooling system’s ability to remove the decay heat released by the spent fuel assemblies is evaluated by a computational fluid dynamics (CFD) simulation. The spent fuel pool of CAP1400 (a passive PWR developed in China) is selected as the reference pool, and the passive cooling system is designed for this spent fuel pool. The pool with the passive cooling system is simulated using Fluent 13.0 with 4 million meshes. Four different cases have been studied, and some notable results have been obtained through this work. The simulation results reveal that the passive cooling system effectively removes the decay heat from the SFP with the storage of 15-year-old spent fuel assemblies with emergency reactor core unloading and prevents the burnout of the fuel rods. The results indicate that the water in the SFP will never boil, even in a severe accident with a lack of emergency power and outside aid.

2013 ◽  
Vol 58 ◽  
pp. 124-131 ◽  
Author(s):  
C. Ye ◽  
M.G. Zheng ◽  
M.L. Wang ◽  
R.H. Zhang ◽  
Z.Q. Xiong

2018 ◽  
Vol 126 ◽  
pp. 162-171 ◽  
Author(s):  
Mukhsinun Hadi Kusuma ◽  
Nandy Putra ◽  
Anhar Riza Antariksawan ◽  
Raldi Artono Koestoer ◽  
Surip Widodo ◽  
...  

2013 ◽  
Vol 2013 ◽  
pp. 1-11 ◽  
Author(s):  
Algirdas Kaliatka ◽  
Viktor Ognerubov ◽  
Virginijus Vileiniškis ◽  
Eugenijus Ušpuras

The safe storage of spent fuel assemblies in the spent fuel pools is very important. These facilities are not covered by leaktight containment; thus, the consequences of overheating and melting of fuel in the spent fuel pools can be very severe. On the other hand, due to low decay heat of fuel assemblies, the processes in pools are slow in comparison with processes in reactor core during LOCA accident. Thus, the accident management measures play a very important role in case of some accidents in spent fuel pools. This paper presents the analysis of possible consequences of fuel overheating due to leakage of water from spent fuel pool. Also, the accident mitigation measure, the late injection of water was evaluated. The analysis was performed for the Ignalina NPP Unit 2 spent fuel pool, using system thermal hydraulic code for severe accident analysis ATHLET-CD. The phenomena, taking place during such accident, are discussed. Also, benchmarking of results of the same accident calculation using ASTEC and RELAP/SCDAPSIM codes is presented here.


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