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- 저자 : 강경욱(G.U. Kang) (검색결과 5 건)
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사용후핵연료 저장 캐니스터 구조물인 바스켓 디스크간 간극의 매질 종류 및 크기에 따른 열전달 연구
강경욱(G.U. Kang),육대식(D.S. Yook),차정훈(J.H. Cha) 한국전산유체공학회 2018 한국전산유체공학회지 Vol.23 No.3
This study investigates numerically the heat transfer effects on gap media and size between the basket and disc in the spent fuel dry storage canister using Fluent 14.5 code. For helium gas, helium solid and stainless steel in media, maximum temperatures of fuel region were measured by varying the heights and width of gap, and the heat transfer phenomena in the gap were described in detail. It is found that the maximum temperature of fuel region is kept low in case the width of the gap is narrowed at the fixed heights of disc. Setting the medium to helium solid in the range of 2 to 10 mm leads to the similar results for the helium gas regardless of the disc heights, and the less time is required for convergence. From these results, it is considered that the medium of the gap may be applied as a helium solid rather than the helium gas in order to increase the efficiency of thermal analysis in terms of heat removal. The results of this study will be used as the theoretical basis for the thermal analysis methodology of the spent fuel dry storage system.
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FLUENT를 활용한 콘크리트 건식 저장용기 공기유로 내부 유동장 해석
강경욱(G.U. Kang),김형진(H.J. Kim),조천형(C.H. Cho) 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.2
This study investigated natural convection flow behavior in airflow path designed in concrete dry storage cask to remove the decay heat from spent nuclear fuels. Using FLUENT 16.1 code, thermal analysis for natural convection was carried out for three dimensional, 1/4 symmetry model under the normal condition that inlet ducts are 100% open. The maximum temperatures on other components except the fuel regions were satisfied with allowable values suggested in nuclear regulation-1536. From velocity and temperature distributions along the flow direction, the flow behavior in horizontal duct of air inlet and outlet duct, annular flow-path and bent pipe was delineated in detail. Theses results will be used as the theoretical background for the composing of airflow path for the designing of passive heat removal system by understanding the flow phenomena in airflow path.
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사용후핵연료 건식저장 캐니스터 내부 금속 구조물 설계특성에 따른 열전달 영향
강경욱(G.U. Kang),육대식(D.S. Yook) 한국전산유체공학회 2019 한국전산유체공학회지 Vol.24 No.3
Heat transfer influences by design characteristics of metal structures inside a spent fuel canister were numerically investigated using a FLUENT 14.5 code with a simplified thermal model. The maximum temperature at a fuel region became lower in case of small gaps, increasing the number of discs because the heat transfer inside the canister was dominated by the conduction between metals structures rather than the natural convection by a helium flow. When the number of discs increased, the similar results were obtained with helium, even if the gap media was applied with the stainless steel rather than helium. In addition, the time required for the analysis was effectively shorten. These results will be used as the theoretical basis in terms of the thermal design on structures inside the dry storage cask.
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사용후핵연료 집합체의 다공성 매질 적용영역에 따른 콘크리트 저장용기 열전달 해석
김형진(H.J. Kim),강경욱(G.U. Kang) 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.4
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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김형진(H. Kim),이동규(D.G. Lee),강경욱(G.U. Kang),조천형(C.H. Cho),권오준(O.J. Kwon) 한국전산유체공학회 2016 한국전산유체공학회지 Vol.21 No.2
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.
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