• 생태와환경
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• 제44권1호
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• pp.66-74
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• 2011

This numerical study aims to investigate the effect of cohesive sediment on turbulence structure due to density stratification. The transport model for cohesive sediment incorporated with flocculation model has been selected and calculates the concentration, fluid momentum, and turbulence. From the model results, it is known that suspension of sediment decreases turbulence intensity. It is also found that cohesive sediment has a relatively weak effect on turbulence damping compared to noncohesive sediment. The low settling velocity and more suspension of cohesive sediment are considered to be mechanisms of this behavior. Richardson number determined with results of this study quantitatively shows that cohesive sediment causes less stable density stratification condition and, as a result, the turbulence structure is less damped compared to the case of noncohesive sediment.

• Wind and Structures
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• 제4권6호
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• pp.469-480
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• 2001

The Leipzig Wind Profile is generally known as a typical neutral planetary boundary layer flow. But it became clear from the present research that it was not completely neutral but weakly stable. We examined whether we could simulate the Leipzig Wind Profile by using a ($k-{\varepsilon}$) turbulence model including the equation of potential temperature. By solving analytically the Second Moment Closure Model under the assumption of local equilibrium and under the condition of a stratified flow, we expressed the turbulent diffusion coefficients (both momentum and thermal) as functions of flux Richardson number. Our ($k-{\varepsilon}$) turbulence model which included the equation of potential temperature and the turbulent diffusion coefficients varying with flux Richardson number reproduced the Leipzig Wind Profile.

• 한국해안해양공학회지
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• 제2권1호
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• pp.1-10
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• 1990

밀도류에 대한 하구에서의 수리조건을 수리모형실험을 통하여 조사하였다. 정상염수쐐기가 존재하는 하구에서의 유하방향의 계면현상은 하구에서의 밀도 Froude수가 커짐에 따라 그 기울기가 증대하였다. 적층 두께는 하도내에서는 거의 일정하였으나, 하도내를 벗어나면서 급격히 증대하였으며, Overall Richardson number가 커짐에 따라 감소하였다. 하구에서의 밀도 Froude 수는 반드시 1.0은 아니며, 상층수량에 따라 변화를 나타내었다. 하구에서의 수위는 상대밀도차가 커짐에 따라 증가하는 경향을 보였다. 섬진강 하구에서의 현상관측결과, 하천수와 외양수와의 사이에 강한 밀도전선이 형성되어 있었다.

• 융합정보논문지
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• 제9권8호
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• pp.155-163
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• 2019

수평원형관에서 나노입자인 산화알미늄과 기본유체인 물의 혼합인 나노유체에 대한 층류 혼합대류열전달현상을 유한체적법의 수치적 방법으로 규명하였다. 나노유체에 대하여 2상 혼합모델을 적용하였으며, 나노입자의 물성은 온도와 체적농도의 함수를 사용하였다. 수치해석에 적용한 모든 모델의 타당성 검증을 위하여 Kim등의 실험결과와 비교하였으며 좋은 결과를 얻었다. 벽면을 일정한 열유속으로 가열하므로 나노유체는 벽면부근에서 형성된 부력에 의하여 2차유동이 생성된다. Richardson수와 나노입자의 농도가 증가할수록 강한 2차유동이 형성되어 열전달을 향상시키게 된다. 또한 Richardson수와 나노입자의 농도가 증가하면 대류열전달계수와 전단응력도 증가한다. 이런 연구들은 열교환기의 성능향상을 위하여 나노유체를 적용하는데 기본자료로 활용이 가능하다. 이번 연구를 기반으로 향후 2중관형열교환기등 다양한 열교환기에 적용할 예정이다.

• 한국해양학회지:바다
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• 제15권3호
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• pp.97-109
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• 2010

하계 남강댐 방류수 유입에 의해 강하게 성층화된 남해 강진만에서 3차원 수치모델링 실험을 통해 태풍 통과시 염분장에 미치는 취송류의 영향과 성층 파괴에 대해 연구하였다. 조위와 유속장, 수온장, 염분장에 대해 각각 스킬 분석(skill analysis)을 이용하여 모델을 검증 하였고, 그 결과 대부분 90%가 넘는 재현율을 보였다. 모델은 조류, 담수유입에 의한 밀도류와 바람에 의한 취송류를 잘 재현했다. 대량 담수 유입이 있을 경우 바람의 영향은 강한 밀도류에 의해 상대적으로 큰 효과가 없으나, 담수유입이 감소하는 시기에는 바람이 수직 혼합작용을 촉진하여 바람을 부과하지 않은 모의 실험보다 2~3일 빠르게 성층을 파괴하였다. 담수 유입에 의한 성층과 바람에 의한 성층 파괴는 성층지수(Richardson 수(數), Ri)를 통하여 판단하였으며, 대량 방류시 성층지수는 급속도로 증가하여 Ri 수(數)가 7~20을 보였고, 방류가 중단된 이후에는 바람에 의한 혼합으로, 성층지수는 급격하게 감소하고 Ri 수(數)는 0~2까지 보였으며, 이 때 상하층간 염분은 일정하게 분포하였다.

• 대한기계학회논문집
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• 제18권1호
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• pp.184-192
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• 1994

The parameters such as Richardson numbers or stability parameters are widely used to account for the extra straining effects due to three-dimensionality, curvature, rotation, swirl and others arising in paractical complex flows. Existing expressions for the extra strain in turbulence models such as $k-{\epsilon}$ models, however, do not satisfy the tensor invariant condition representing the coordinate indifference. In the present paper, considering the characteristics of both the mean strain rate and the mean vorticity, a new parameter to deal with the extra straining effects is proposed. The new parameter has a simple form and satisfies the tensor invariant condition. A semi-quantitative analysis between the present and previous parameters for several typical complex flows suggests that the newly proposed parameter is more general and adequate in representing the extra straining effects than the previous ad-hoc parameters.

• Journal of Radiation Protection and Research
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• 제31권1호
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• pp.9-15
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• 2006

대기 중으로 방출된 방사성 물질의 이동 확산 현상을 이해하기 위하여 장거리 대기 확산 모델 LADAS가 개발되었다 개발된 수치모델의 검증을 위하여 ETEX 장거리 확산실험 결과와 비교하였다. 비교결과 LADAS모델 내 혼합층 높이를 일정하게 준 경우보다 Richardson number를 이용하여 혼합층 높이를 계산한 결과가 관측 값에 가장 근접함을 알 수 있었다. 또한 일부 포집 지점에서 관측된 농도의 시계열 자료와 비교한 바 계산 값은 어느 정도 일치하고 있었다.

• 한국대기환경학회지
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• 제12권4호
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• pp.369-376
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• 1996

Major atmospheric stability classification methods were evaluated with meteorological data obtained by scoustic sounding profiler (SODAR/RASS) in Seoul. The Psequill classificatio method, the method most widely used because of its good agreement in respect of synoptic scope under the steady state, fails to describe the time lag, the response time on stability by heating or cooling caused by daily insolation or noctrunal surface radiation. Horizontal and vertical standard deviation of wind fluctuation $(\sigma_A and \sigma_E)$ method tend to classify night-time stable condition (E, F class) into unstable condition (A, B class). The classification matrix tables for Vogt's vertical temperature difference and wind speed using method ($\Delta$T $\cdot$ U) and bulk Richardson number (Rb) were amended for practical use over Seoul. The modified tables for $\Delta$T $\cdot$ U and Rb method were made by using comprehensive frequency distribution from Pasquill's method and other existing results, and the correlation coefficient(r) was equal to 0.829. It was confirmed that atmospheric stability could be changed with monitoring site characteristics, height and vertical difference between sensors of monitoring station, and classification method itself.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1611-1625
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• 2020

We propose a scaled-down experimental model of vertical air-natural convection channels by applying the modified Ishii-Kataoka 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 scale-down model, which demonstrated that the temperature rises and the average air flow velocity measured in the scale-down model.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2204-2220
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• 2020

An open-pool type research reactor is designed and operated considering the accessibility around the pool top area to enhance the reactor utilization. The reactor structure assembly is placed at the bottom of the pool and filled with water as a primary coolant for the core cooling and radiation shielding. Most radioactive materials are generated from the fuel assemblies in the reactor core and circulated with the primary coolant. If the primary coolant goes up to the pool surface, the radiation level increases around the working area near the top of the pool. Hence, the hot water layer is designed and formed at the upper part of the pool to suppress the rising of the primary coolant to the pool surface. The temperature gradient is established from the hot water layer to the primary coolant. As this temperature gradient suppresses the circulation of the primary coolant at the upper region of the pool, the radioactive primary coolant rising up directly to the pool surface is minimized. Water mixing between these layers is reduced because the hot water layer is formed above the primary coolant with a higher temperature. The radiation level above the pool surface area is maintained as low as reasonably achievable since the radioactive materials in the primary coolant are trapped under the hot water layer. The key to maintaining the stable hot water layer and keeping the radiation level low on the pool surface is to have a stable flow of the primary coolant. In the research reactor with a downward core flow, the primary coolant is dumped into the reactor pool and goes to the reactor core through the flow guide structure. Flow fields of the primary coolant at the lower region of the reactor pool are largely affected by the dumped primary coolant. Simple, circular, and duct type discharge headers are designed to control the flow fields and make the primary coolant flow stable in the reactor pool. In this research, flow fields of the primary coolant and hot water layer are numerically simulated in the reactor pool. The heat transfer rate, temperature, and velocity fields are taken into consideration to determine the formation of the stable hot water layer and primary coolant flow. The bulk Richardson number is used to evaluate the stability of the flow field. A duct type discharge header is finally chosen to dump the primary coolant into the reactor pool. The bulk Richardson number should be higher than 2.7 and the temperature of the hot water layer should be 1 ℃ higher than the temperature of the primary coolant to maintain the stability of the stratified thermal layer.