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사용후핵연료 건식 용기의 단기운영공정 열전달 평가

ANALYSIS OF HEAT TRANSFER ON SPENT FUEL DRY CASK DURING SHORT-TERM OPERATIONS

  • 김형진 (한국원자력환경공단 기술연구소) ;
  • 이동규 ((주)코네스코퍼레이션 원자력팀) ;
  • 강경욱 (한국원자력환경공단 기술연구소) ;
  • 조천형 (한국원자력환경공단 기술연구소) ;
  • 권오준 (한국과학기술원 항공우주공학과)
  • Kim, H. (R&D Institute, Korea Radioactive Waste Agency) ;
  • Lee, D.G. (Nuclear Energy Team, Korea Nuclear Engineering and Service Co.) ;
  • Kang, G.U. (R&D Institute, Korea Radioactive Waste Agency) ;
  • Cho, C.H. (R&D Institute, Korea Radioactive Waste Agency) ;
  • Kwon, O.J. (Dept. of Aerospace Engineering, KAIST)
  • 투고 : 2016.04.06
  • 심사 : 2016.06.20
  • 발행 : 2016.06.30

초록

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 $400^{\circ}C$. The maximum peak cladding temperature is $173.8^{\circ}C$ at vacuum drying process and the temperature rise of dry, and vacuum drying process occurs steeply.

키워드

참고문헌

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