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논문 기본 정보

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학술저널
저자정보
김경문 (인천대학교) 황지환 (중앙대학교) Wongwises Somchai (King Mongkut's University of Technology Thonburi) 정동욱 (중앙대학교) 안호선 (인천대학교)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제8호
발행연도
2020.8
수록면
1,611 - 1,625 (15page)
DOI
10.1016/j.net.2020.01.005

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We propose a scaled-down experimental model of vertical air-natural convection channels by applying the modified IshiieKataoka scaling method with the assistance of numerical analyses to the Reactor Vault Cooling System (RVCS) of the Proto-type Gen-IV Sodium-cooled fast reactor (PGSFR) being developed in Korea. Two major non-dimensional numbers (modified Richardson and Friction number) from the momentum equation and Stanton number from the energy balance equation were identified to design the scaled-down experimental model to assimilate thermal-hydraulic behaviors of the natural convective air-cooling channel of RVCS. The ratios of the design parameters in the PGSFR RVCS between the prototype and the scaled-down model were determined by setting Richardson and Stanton number to be unity. The friction number which cannot be determined by the Ishii-Kataoka method was estimated by numerical analyses using the MARS-KS system code. The numerical analyses showed that the friction number with the form loss coefficient of 2.0 in the scale-down model would result in an acceptable prediction of the thermal-hydraulic behavior in RVCS. We also performed experimental benchmarking using the scaled-down model with the MARS-KS simulations to verify the appropriateness of the scaledown model, which demonstrated that the temperature rises and the average air flow velocity measured in the scale-down model.

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