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Study on natural circulation of the reactor pool under RVACS operation using fluid to fluid model simulating experiment

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Title
Study on natural circulation of the reactor pool under RVACS operation using fluid to fluid model simulating experiment
Author
Lee, Min Ho
Advisor
Bang, In Cheol
Keywords
liquid metal; natural circulation; similarity; passive; safety; RVCS; RVACS; PGSFR
Issue Date
2020-08
Publisher
Graduate School of UNIST
Abstract
Passive safety becomes more and more important under station black out situation like Fukushima, providing trustworthy countermeasure for the accident. Importance of the passive safety is emphasized in the generation-IV reactors which are under development. Among the gen-IV reactors, lead-cooled fast reactor and sodium-cooled fast reactor have advantages to apply passive safety system driven by natural circulation due to superior thermal properties of the liquid metal coolant. For design and performance evaluation of natural circulation driven passive safety systems, experimental approach is necessary. However, liquid metal natural circulation itself has many difficulties like high temperature, toxicity, handling, cost, etc. Therefore, simulating experiment is required for the liquid metal natural circulation. In this research, experimental validation was conducted with liquid metal and non-metallic fluid, water. And based on the result of the validation experiment, natural circulation behavior under reactor vessel auxiliary cooling system (RVACS) operation condition was investigated, changing decay heat and boundary condition. For the validation of the similarity law, Wood’s metal, which is alloy of bismuth, lead, tin and cadmium, was selected as a representative for the liquid metal and water was selected as a simulant of liquid metal. In this experiment, it was concluded that water experiment could simulate temperature field of liquid metal natural circulation with reasonable error, and could simulate velocity field with moderate error. Based on the validation experiment, 2-D slab model was designed for RVACS performance evaluation. Effect of decay heat and boundary condition on the temperature distribution inside of the reactor pool were observed in the experiment. It was concluded that change of the decay heat affected slightly to the normalized temperature distribution and boundary condition made global shift of the temperature in the whole reactor pool.
Description
Department of Nuclear Engineering
URI
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NUE_Theses_Ph.D.
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