사용후핵연료 건식 용기의 단기운영공정 열전달 평가 ANALYSIS OF HEAT TRANSFER ON SPENT FUEL DRY CASK DURING SHORT-TERM OPERATIONS

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When spent fuel assemblies from the reactor of nuclear power plants(NPPs) are transported, the assemblies are exposed to short-term operations that can affect the peak cladding temperature of spent fuel assemblies. Therefore, it needs to perform the analysis of heat transfer on spent fuel dry cask during the operation. For 3 dimensional computational fluid dynamnics(CFD) simulation, it is proposed that the short-term operation is divided into three processes: Wet, dry, and vacuum drying condition. The three processes have different heat transfer mode and medium. Metal transportation cask, which is Korea Radioactive Waste Agency(KORAD)’s developing cask, is evaluated by the methods proposed in this work. During working hours, the boiling at wet process does not occur in the cask and the peak cladding temperatures of all processes remain below 400℃. The maximum peak cladding temperature is 173.8℃ at vacuum drying process and the temperature rise of dry, and vacuum drying process occurs steeply.
Publisher
한국전산유체공학회
Issue Date
2016-06
Language
Korean
Citation

한국전산유체공학회지, v.21, no.2, pp.54 - 61

ISSN
1598-6071
URI
http://hdl.handle.net/10203/213626
Appears in Collection
AE-Journal Papers(저널논문)
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