한국전산유체공학회지 (Journal of computational fluids engineering)

한국전산유체공학회 (Korean Society of Computational Fluids Engineering)
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사용후핵연료 집합체의 다공성 매질 적용영역에 따른 콘크리트 저장용기 열전달 해석

HEAT TRANSFER ANALYSIS OF CONCRETE STORAGE CASK DEPENDING ON POROUS MEDIA REGION OF SPENT FUEL ASSEMBLY

  • 김형진 (한국원자력환경공단, 기술연구소) ;
  • 강경욱 (한국원자력안전기술원, 방사선.폐기물평가실)
  • Kim, H.J. (Research & Development Institute, Korea Radioactive Waste Agency) ;
  • Kang, G.U. (Dept. of Radiation Protection & Radioactive Waste Safety, Korea Institute of Nuclear Safety)
  • Received : 2016.10.11
  • Accepted : 2016.11.17
  • Published : 2016.12.31
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Abstract

Generally, thermal analysis of spent fuel storage cask has been conducted using the porous media and effective thermal conductivity model to simplify the structural complexity of spent fuel assemblies. As the fuel assembly is composed of two regions; active fuel region corresponding to UO2 pellets and unactive fuel region corresponding to the top and bottom nozzle, the heat transfer performance can be influenced depending on porous media application at these regions. In this study, numerical analysis on concrete storage cask of spent fuel was performed to investigate heat transfer effects for two cases; one was porous media application only to active fuel region(case 1) and the other one was porous media to whole length of fuel assembly(case 2). Using computational fluid dynamics code, the three dimensional, 1/4 symmetry model was constructed. For two cases, maximum temperatures for each component were evaluated below the allowable limits. For the case 1, maximum temperatures for fuel cladding, neutron absorber and baskets inside the canister were slightly higher than those for the case 2. In particular, even though the helium flows with low velocity due to buoyant forces occurred at the top and bottom of unactive fuel region, treating only active fuel region as the porous media was ineffective in respect of the heat removal performance of concrete storage cask, implying a conservative result.

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References

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