Since the Fukushima accident, the safety of spent fuel pool attracts more and more attention. As the feed water system of spent fuel pool fails to work, coolant in the spent fuel pool rises with water level in the pool dropping. As a result of this phenomenon, spent fuel assemblies are exposed to the atmosphere and maybe melt with leakage of radioactive fission products. It is necessary to research spray cooling under the condition of failure of the cooling system in the spent fuel pool. According to spray cooling under the condition of failure of the cooling system in the spent fuel pool, a model is established for a single spent fuel rod and  a code named ”SFSC” which is used to calculate the thermal-hydraulic characteristics of film on the spent fuel rod under the condition of spray cooling is developed. The results obtained from SFSC consist of film thickness, film temperature, film evaporation, fuel pellet temperature of spent fuel rod and cladding temperature of spent fuel rod at different height of spent fuel rod. At the same time, same model is estabished by RELAP and results calculated by RELAP is compared with that calculated by SFSC. The good agreement of two results demonstrates that SFSC is effective. SFSC fills in the blanks of thermal-hydraulic calculation for the spent fuel rod under the condition of spray cooling.


Preliminary Development on Thermal-Hydraulic Analysis Code for the Spent Fuel Rod Under the Condition of Spray Cooling

Division / Sponsors: 
Power Division & Nuclear Engineering Division (NED)

Power Conference
Paper Proceedings: https://asmedigitalcollection.asme.org/POWER/POWER2020/volume/83747

International Conference on Nuclear Engineering
Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE2020/volume/83761

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