• Proceedings of the Korean Vacuum Society Conference
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• 2016.02a
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• pp.383.2-383.2
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• 2016

임계 열유속 현상은 열전달 시스템에서 가열조건이나 유동조건이 변함에 따라 열전달 표면 부근의 유체상태가 액체에서 기체로 바뀌면서 열전달계수가 급격히 감소하는 현상을 말한다. 임계 열유속 발생 시 핵 비등 영역에서 순간적으로 막 비등 영역으로 넘어가면서 원전 시스템의 물리적 파괴를 일으킬 수 있게 된다. 따라서 임계 열유속 현상은 시스템 설계 및 안전해석 뿐만 아니라, 열교환 및 냉각 장치 설계에서 중요하게 고려되고 있다. 특히, 비등 열전달 시스템에서 임계 열유속 발생 시 시스템의 물리적 손상을 야기하게 된다. 따라서 원전 시스템을 보호하면서 성능을 극대화시키기 위해서는 임계 열유속 향상이 필수적이며, 임계 열유속 향상을 위한 대안 중 하나로서 열적 특성이 우수한 나노유체를 열전달 시스템에 적용하여 임계 열유속 향상을 위한 연구가 지속되고 있다. 따라서 본 연구에서는 산화 처리된 다중벽 탄소나노튜브 나노유체를 사용하여 각각 0.5 m/s, 1.0 m/s, 1.5 m/s의 유속에서 임계 열유속과 열전달 계수를 측정하였다. 그 결과 산화 처리된 다중벽 탄소나노튜브 나노유체의 유속이 증가 할수록 임계 열유속이 증가하는 것을 확인 하였으며, 순수물과 비교하여 최대 62.64% 증가함을 확인하였다. 그리고 산화 처리된 다중벽 탄소나노튜브 나노유체의 비등 열전달 계수 또한 유속이 증가 할수록 비등 열전달 계수가 증가하는 것을 확인하였며 최대 24.29% 증가함을 확인하였다.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.4
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• pp.343-352
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• 2013

In this study, a smooth flat surface, low fin, Turbo-B, and Thermoexcel-E surfaces are used to examine the effect of the flow velocity on the pool boiling heat transfer coefficients (HTCs) and critical heat fluxes (CHFs). HTCs and CHFs are measured on a smooth square heater of $9.53{\times}9.53mm^2$ at $60^{\circ}C$ in a pool of pure water at various fluid velocities of 0, 0.1, 0.15, and 0.2 m/s. Test results show that for all surfaces, CHFs obtained with flow are higher than those obtained without flow. CHFs of the low fin surface are higher than those of the Turbo-B and Thermoexcel-E surfaces due largely to the increase in surface area and sufficient fin spaces for the easy removal of bubbles. CHFs of the low fin surface show even 5 times higher CHFs as compared to the plain surface. On the other hand, both Turbo-B and Thermoexcel-E surfaces do not show satisfactory results because their pore sizes are too small and water bubbles easily cover them. At low heat fluxes of less than $50kW/m^2$, HTCs increase as the flow velocity increases for all surfaces. In conclusion, a low fin geometry is good for application to steam generators in nuclear power plants.

• Proceedings of the Korean Vacuum Society Conference
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• 2016.02a
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• pp.382.1-382.1
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• 2016

비등 열전달 시스템은 각종 발전 시스템, 열교환기, 냉방 및 냉동 시스템과 같이 다양한 산업에서 이용되며 매우 중요시 되고 있다. 또한 비등 열전달 시스템에서의 임계 열유속은 열전달 시스템의 한계 및 안정성을 나타내는 중요한 인자이다. 따라서 비등 열전달 시스템의 성능을 높이기 위해 임계 열유속을 향상시키려는 연구 및 개발이 지속적으로 이루어지고 있다. 최근에는 작동유체를 나노유체로 사용할 경우 임계 열유속을 크게 향상 시킬 수 있다고 보고되었다. 하지만 작동유체를 나노유체로 사용할 경우 나노입자가 열전달 표면에 침착되는 현상을 유발하며 열전달 시스템의 성능을 감소시킬 수 있다. 따라서 본 연구에서는 산화 처리된 그래핀 나노유체의 파울링 현상에 따른 열적 특성을 분석해 보았다. 그 결과 산화 처리된 그래핀 나노 파울링은 유속과 파울링을 위한 코팅시간이 증가할수록 산화 처리된 그래핀 나노유체의 임계 열유속이 크게 증가하고 있음을 확인할 수 있었다. 하지만 임계 열유속은 증가하나 비등 열전달 표면의 온도가 크게 증가하고 있음을 확인하였다. 그리고 열전달 계수는 유동이 없는 순수 물 비등 열전달 계수와 비교하여 감소하는 것으로 나타났다.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.144-144
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• 2002

• Transactions of the Korean Society of Mechanical Engineers B
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• v.36 no.5
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• pp.477-485
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• 2012

Fluid flow and heat transfer in horizontal ducts are strongly coupled with large changes in thermodynamic and transport properties near the critical region as well as the gravity force. Numerical analysis has been carried out to investigate convective heat transfer in horizontal rectangular ducts for water near the thermodynamic critical point. Convective heat transfer characteristics, including velocity, temperature, and the properties as well as local heat transfer coefficients along the ducts are compared with the effect of proximity on the critical point. When there is flow acceleration because of a density decrease, convective heat transfer characteristics in the ducts show transition behavior between liquid-like and gas-like phases. There is a large variation in the local heat transfer coefficient distributions at the top, side, and bottom surfaces, and close to the pseudocritical temperature, a peak in the heat transfer coefficient distribution resulting from improved turbulent transport is observed. The Nusselt number distribution depends on pressure and duct aspect ratio, while the Nusselt number peak rapidly increases as the pressure approaches the critical pressure. The predicted Nusselt number is also compared with other heat transfer correlations.

• Nuclear Engineering and Technology
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• v.26 no.3
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• pp.440-452
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• 1994

Nuclear fuel bundles are designed such that the heat flux at a-fuel pin surface should not exceed the critical heat flux (CHF) during normal operation and anticipated transient. Therefore, evaluation of the CHF for fuel bundle is demanded in an exact and reliable manner. One of the major concerns with the current application of CHF correlations is that the CHF based on circular tubes is applied to the fuel bundle subchannel analysis, mainly in terms of the hydraulic diameter with correction factors which may result in a source of possibly large uncertainties in CHF prediction. The hydraulic diameter does not recognize the local properties of fluid nor such effect as the surface curvature; the turbulence action on the convex surface is much more pronounced than that on the concave surface. Even for the tube having concave curvature, the effect of tube diameter on CHF becomes important with decreasing diameter. These facts imply that the convex curvature effect is significant and crucial to the reliable CHF prediction. This paper reviews and discusses analytical and experimental aspects of effect of transverse convex curvature in incompressible turbulent flow and heat transfer, and on CHF. Flow models to quantify this effect are briefly mentioned and future works are recommended.

• Economic and Environmental Geology
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• v.52 no.4
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• pp.291-297
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• 2019

Fluid flow through rock fractures has been quantified using equations such as Stokes equations, Reynolds equation (or local cubic law), cubic law, etc. derived from the Navier-Stokes equations under the assumption that linear flow prevails. Therefore, these simplified equations are limited to linear flow regime, and cause errors in nonlinear flow regime. In this study, causal mechanism of nonlinear flow and critical Reynolds number were presented by carrying out fluid flow modeling with both the Navier-Stokes equations and the Stokes equations for a three-dimensional rough-walled rock fracture. This study showed that flow regimes changed from linear to nonlinear at the Reynolds number greater than 10. This is because the inertial forces, proportional to the square of the fluid velocity, increased enough to overwhelm the viscous forces. This tendency was also shown for the unmated (slightly sheared) rock fracture. It was found that nonlinear flow was caused by the rapid increase in the inertial forces with increasing fluid velocity, not by the growing eddies that have been ascribed to nonlinear flow.

• Korean Chemical Engineering Research
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• v.58 no.2
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• pp.307-312
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• 2020

Fluidized bed reactors operated in subatmospheric pressure has been focused because several industrial applications such as vacuum drying and plasma cvd requires reduced pressure fludization. However, the hydrodynamics of fluidized beds in subatmospheric pressure has not been extensively investigated. The pressure drop in the fluidized bed has been measured with variation of downstream pressures from 1.33 to 101.3 kPa in the shallow and deep fluidized beds under the sub-atmospheric pressures. The obtained minimum fluidization velocity of powders is a function of pressure due to the changes of gas density and mean free path. We can experimentally determine the critical Knudsen number and the critical pressure to define the slip regime significantly to influence the hydrodynamics of fluidized beds.

• Journal of the Korean Society of Propulsion Engineers
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• v.7 no.2
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• pp.7-14
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• 2003

Computational work using the axisymmetric, compressible, Navier-Stokes Equations is carried out to predict the discharge coefficient of mass flow through a micro-critical nozzle. Several kinds of turbulence models and wall functions are employed to validate the computational predictions. The computed results are compared with the previous experimented ones. The present computations predict the experimental discharge coefficients with a reasonable accuracy. It is found that the standard $\kappa$-$\varepsilon$turbulence model with the standard wall function gives a best prediction of the discharge coefficients. The displacement thickness of the nozzle wall boundary layer is evaluated at the nozzle throat and is well compared to a prediction obtained by an empirical equation. The resulting displacement thickness of the wall boundary layer is about 2% to 0.6% of the diameter of the nozzle throat for the Reynolds numbers of 2000 to 20000.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.148.1-148
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• 2002