Thermal-hydraulic experiment and analysis for interim dry storage of spent nuclear fuel = 사용후 핵연료의 중간건식저장에 대한 열유체 실험 및 해석

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dc.contributor.advisorNO, Hee-Cheon-
dc.contributor.advisor노희천-
dc.contributor.authorYoo, Seung-Hun-
dc.contributor.author류승훈-
dc.date.accessioned2011-12-14T08:06:48Z-
dc.date.available2011-12-14T08:06:48Z-
dc.date.issued2011-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=466426&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/49038-
dc.description학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2011.2, [ xii, 132 p. ]-
dc.description.abstractThe experimental and numerical studies of interim storages for nuclear spent fuels have been performed to investigate thermal-hydraulic characteristics of the dry storage systems and to propose new methodologies for the analysis and the design. Three separate researches have been performed in the present study: (a) Development of a scaling methodology and thermal-hydraulic experiment of a single spent fuel assembly simulating a dry storage cask; (b) Full-scope simulation of a dry storage cask by the use of Computational Fluid Dynamics (CFD) code; (c) Thermal-hydraulic design of a tunnel-type interim storage facility. In the first study, a scaling methodology has been developed to design a scaled-down canister. The scaling was performed in two steps. For the first step, the height of a spent fuel assembly was reduced from full height to half height. In order to consider the effect of height reduction on the natural convection, the scaling law of Ishii and Kataoka (1984) was employed. For the second step, the quantity of spent fuel assemblies was reduced from multiple assemblies to a single assembly. The scaling methodology was validated through the comparison with the experiment of the TN24P cask. The Peak Cladding Temperature (PCT), temperature gradients, and the axial and radial temperature distribution in the nondimensional forms were in good agreement with the experimental data. Based on the developed methodology, we have performed a single assembly experiment which was designed to simulate the full scale of the TN24P cask. The experimental data was compared with the CFD calculations. It turns out that their PCTs were less than the maximum allowable temperature for the fuel cladding and that the differences of their PCTs were agreed within 3℃, which was less than measurement uncertainty. In the second study, the full-scope simulations of the TN24P cask were performed by FLUENT. In order to investigate the sensitivity of the numerical and physical parameters ...eng
dc.languageeng-
dc.publisher한국과학기술원-
dc.subjectPWR-
dc.subjectdry storage cask-
dc.subjectinterim storage facility-
dc.subjectspent fuel-
dc.subjectCFD-
dc.subject전산유체역학-
dc.subject가압경수로-
dc.subject건식저장용기-
dc.subject중간저장시설-
dc.subject사용후 핵연료-
dc.titleThermal-hydraulic experiment and analysis for interim dry storage of spent nuclear fuel = 사용후 핵연료의 중간건식저장에 대한 열유체 실험 및 해석-
dc.typeThesis(Ph.D)-
dc.identifier.CNRN466426/325007 -
dc.description.department한국과학기술원 : 원자력및양자공학과, -
dc.identifier.uid020057367-
dc.contributor.localauthorYoo, Seung-Hun-
dc.contributor.localauthor류승훈-
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NE-Theses_Ph.D.(박사논문)
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