Concentric Annular Thermosyphon for Passive Cooling System of Spent Fuel Pool

2019 ◽  
Vol 31 (1) ◽  
pp. 111-118
Author(s):  
Jongsoo KIM
Keyword(s):  
Cooling System ◽  
Passive Cooling ◽  
Spent Fuel ◽  
Spent Fuel Pool ◽  
Passive Cooling System

The design and simulation of a new spent fuel pool passive cooling system

2013 ◽  
Vol 58 ◽  
pp. 124-131 ◽  
Author(s):  
C. Ye ◽  
M.G. Zheng ◽  
M.L. Wang ◽  
R.H. Zhang ◽  
Z.Q. Xiong
Keyword(s):  
Cooling System ◽  
Passive Cooling ◽  
Spent Fuel ◽  
Spent Fuel Pool ◽  
Passive Cooling System

Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe

2018 ◽  
Vol 126 ◽  
pp. 162-171 ◽  
Author(s):  
Mukhsinun Hadi Kusuma ◽  
Nandy Putra ◽  
Anhar Riza Antariksawan ◽  
Raldi Artono Koestoer ◽  
Surip Widodo ◽  
...  
Keyword(s):  
Heat Pipe ◽  
Cooling System ◽  
Passive Cooling ◽  
Spent Fuel ◽  
Spent Fuel Pool ◽  
Passive Cooling System

The study of passive cooling system assisted with separate heat pipe for decay heat removal in spent fuel pool

2018 ◽  
Vol 111 ◽  
pp. 523-535 ◽  
Author(s):  
Kun Lai ◽  
Wen Wang ◽  
Chongchong Yi ◽  
Yiwu Kuang ◽  
Cheng Ye
Keyword(s):  
Heat Pipe ◽  
Cooling System ◽  
Heat Removal ◽  
Passive Cooling ◽  
Spent Fuel ◽  
Decay Heat ◽  
Spent Fuel Pool ◽  
Passive Cooling System

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

2013 ◽  
Author(s):  
Cheng Ye ◽  
Minglu Wang ◽  
Mingguang Zheng ◽  
Zhengqin Xiong ◽  
Ronghua Zhang
Keyword(s):  
High Efficiency ◽  
Cfd Simulation ◽  
Cooling System ◽  
Severe Accident ◽  
Passive Cooling ◽  
Spent Fuel ◽  
Decay Heat ◽  
Fuel Assemblies ◽  
Spent Fuel Pool ◽  
Passive Cooling System

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.

Self-Propelling Cooling Systems: Back-Fitting Passive Cooling Functions to Existing Nuclear Power Plants

2012 ◽  
Author(s):  
Dominik von Lavante ◽  
Dietmar Kuhn ◽  
Ernst von Lavante
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Cooling System ◽  
Electrical Power ◽  
Reactor Core ◽  
Passive Cooling ◽  
Spent Fuel ◽  
Cooling Systems ◽  
Spent Fuel Pool

The present paper describes a back-fit solution proposed by RWE Technology GmbH for adding passive cooling functions to existing nuclear power plants. The Fukushima accidents have high-lighted the need for managing station black-out events and coping with the complete loss of the ultimate heat sink for long time durations, combined with the unavailability of adequate off-site supplies and adequate emergency personnel for days. In an ideal world, a nuclear power plant should be able to sustain its essential cooling functions, i.e. preventing degradation of core and spent fuel pool inventories, following a reactor trip in complete autarchy for a nearly indefinite amount of time. RWE Technology is currently investigating a back-fit solution involving “self-propelling” cooling systems that deliver exactly this long term autarchy. The cooling system utilizes the temperature difference between the hotter reactor core or spent fuel pond with the surrounding ultimate heat sink (ambient air) to drive its coolant like a classical heat machine. The cooling loop itself is the heat machine, but its sole purpose is to merely achieve sufficient thermal efficiency to drive itself and to establish convective cooling (∼2% thermal efficiency). This is realized by the use of a Joule/Brayton Cycle employing supercritical CO2. The special properties of supercritical CO2 are essential for this system to be practicable. Above a temperature of 30.97°C and a pressure of 73.7bar CO2 becomes a super dense gas with densities similar to that of a typical liquid (∼400kg/m3), viscosities similar tothat of a gas (∼3×105Pas) and gas like compressibility. This allows for an extremely compact cooling system that can drive itself on very small temperature differences. The presented parametric studies show that a back-fitable system for long-term spent fuel pool cooling is viable to deliver excess electrical power for emergency systems of approximately 100kW. In temperate climates with peak air temperatures of up to 35°C, the system can power itself and its air coolers at spent fuel pool temperatures of 85°C, although with little excess electrical power left. Different back-fit strategies for PWR and BWR reactor core decay heat removal are discussed and the size of piping, heat exchangers and turbo-machinery are briefly evaluated. It was found that depending on the strategy, a cooling system capable of removing all decay heat from a reactor core would employ piping diameters between 100–150mm and the investigated compact and sealed turbine-alternator-compressor unit would be sufficiently small to be integrated into the piping.

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