• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.10a
• /
• pp.487-494
• /
• 1997

비등이 발생하는 경사유로에서 이상유동 구조 파악을 위해 국부적 이상유동 변수의 측정이 이루어졌다. 국부 기포율, 국부 기포빈도, 국부기포속도 그리고 국부 기포크기와 같은 기상 관련 이상유동변수는 이중 전기전도도 탐침으로, 액상속도 분포는 Pilot tuba로 측정하였다. 유로의 경사도가 이상유동 구조에 미치는 영향을 파악하기 위해 실험은 수직, 수직으로부터 30도 경사도 및 60도 경사도에서 유량과 열유속을 변화시켜가며 수행하였으며 유동변수의 측정은 경사진 경우에 측면 방향으로의 대칭성을 고려하여 유로 반 단면내 총 91개 지점에서, 수직인 경우에는 13개 지점에서 이루어졌다. 유동조건은 1.4m/s 이하의 평균 액상 겉보기 속도에 제한되었고 유로내 압력은 대기압이며 유동양식은 미포화 비등에 국한되었다. 측정된 이상유동 변수의 분포를 이용하여 경사유로에 적용할 수 있는 distribution parameter와 drift velocity 같은 dirft flux parameter에 대한 상관식이 개발되었다.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
• /
• v.7 no.1
• /
• pp.132-141
• /
• 1995

Characteristics of pressure-drop oscillations(PDO) in a boiling channel were studied numerically and compared with experimental data. Effects of initial and boundary conditions on PDO were investigated in terms of oscillation period and amplitude. The period and amplitude of PDO increased with increasing of the compressible volume in the surge tank and the heat input. PDO occurred within the specific range of the fluid temperature, at which oscillation period and amplitude diminished rapidly with the increase of the fluid temperature. The increase of the loss coefficient in fluid supply line resulted in slightly longer oscillation period and larger amplitude. Numerical results showed good agreement with the experimental data.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
• /
• v.5 no.3
• /
• pp.179-186
• /
• 1993

The characteristics of pressure-drop oscillations(PDO) in boiling channel are studied experimentally. The effects of initial and boundary conditions on PDO are investigated in terms of oscillation period and amplitude. The period and amplitude of PDO are increased with the increase in the compressible volume in surge tank and heat input. However the amplitude of PDO is decreased with fluid temperature under low subcooling condition. Higher initial insurge flowrate resulted in almost invariant oscillation period but lower amplitude. At higher heat input the oscillation of heater wall temperature is significant, whose period is the same as that of pressure-drop instability.

• Transactions of the Korean Society of Mechanical Engineers B
• /
• v.37 no.4
• /
• pp.377-385
• /
• 2013

To identify the effects of an outflow area on pool boiling heat transfer in a vertical annulus, three different flow restrictors were studied experimentally. For the test, a heated tube of smooth stainless steel and water at atmospheric pressure were used. Both annuli with open and closed bottoms were considered. To validate the effects of the outflow area on the heat transfer, the results of the annulus with the restrictor were compared with the data for the plain annulus without the restrictor. The reduction of the outflow area ultimately results in a decrease in the heat transfer. As the outflow area is very small, a slight increase in heat transfer is also observed. The major cause of this tendency is explained as the difference in the intensity of liquid agitation cause by the movement of coalesced bubbles. It is identified that the convective flow, pulsating flow, and evaporative mechanism are considered as the important mechanisms.

• Nuclear Engineering and Technology
• /
• v.20 no.1
• /
• pp.35-46
• /
• 1988

The prediction of clad surface temperatures is important to the design and the safety anlaysis of nuclear reactor. The accurate prediction requires the detailed knowledge of the flow structure and heat transfer, which is complicate due to anisotropic turbulent phenomena. A two-equation model including anisotropic eddy viscosity model is applied to forecast the velocity distribution. And the temperature field is calculated with uniform wall heat flux. The Galerkin's weighted residual finite element method has been used to calculate the turbulent quantities right up to the wall. The numerical results show good agreement with available data and that turbulence anisotropy strongly affects on the mean flow and thus the temperature field. And Nu-P/D correlation is established for sodium coolant in close-packed equilateral triangular bundle in the P/D range of 1.05 to 1.30.

• Transactions of the Korean Society of Mechanical Engineers B
• /
• v.39 no.12
• /
• pp.953-963
• /
• 2015

There is an increasing need to understand the thermal-hydraulic phenomena, including the critical heat flux (CHF), in narrow rectangular channels and consider these in system design. The CHF mechanism under a saturated flow boiling condition involves the depletion of the liquid film of an annular flow. To predict this type of CHF, the previous representative liquid film dryout models (LFD models) were studied, and their shortcomings were reviewed, including the assumption that void fraction or quality is constant at the boundary condition for the onset of annular flow (OAF). A new LFD model was proposed based on the recent constitutive correlations for the droplet deposition rate and entrainment rate. In addition, this LFD model was applied to predict the CHF in vertical narrow rectangular channels that were uniformly heated. The predicted CHF showed good agreement with 284 pieces of experimental data, with a mean absolute error of 18. 1 % and root mean square error of 22.9 %.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
• /
• v.23 no.11
• /
• pp.718-725
• /
• 2011

Characteristics of flow boiling heat transfer in microchannels were investigated experimentally. The microchannels consisted of 9 parallel trapezoidal channels with each channel having 205 ${\mu}m$ of bottom width, 800 ${\mu}m$ of depth, $3.6^{\circ}$ of sidewall angle, and 7 cm of length. Tests were performed with R113 over a mass velocity range of 150~920 $kg/m^2s$, heat flux of 10~100 $kW/m^2$ and inlet pressures of 105~195 kPa. Flow boiling heat transfer coefficient in microchannels was found to be dominated by heat-flux. However the effect of mass velocity was not significant. Contrary to macrochannel trends, the heat transfer coefficient was shown to decrease with increasing thermodynamic equilibrium quality. A new correlation suitable for predicting flow boiling heat transfer coefficient was developed based on the laminar single-phase heat transfer coefficient and the nucleate boiling dominant equation. Comparison with the experimental data showed good agreement.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.05a
• /
• pp.164-164
• /
• 1999

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.10a
• /
• pp.150.2-150
• /
• 1999

• Proceedings of the Korean Nuclear Society Conference
• /
• 1997.05a
• /
• pp.575-580
• /
• 1997

반구형 간극에서의 비등시 이상 유체의 유동 가시화 실험을 수행하였다. 가시화를 위해 투명한 유리로 제작한 외부 용기는 내부의 가열 용기와 1mm 간격을 이루도록 하였으나 외부 용기가 완전한 반구 형태를 이루지 못하여 간극의 크기가 균일하지 못하였다. 열속이 높아짐에 따라 간극이 좁은 부분에서는 밖으로 빠져 나오려는 증기와 상부의 물이 역류유동제한 현상을 일으켜 물이 공급되지 못하였고 간극이 큰 부분에서는 물이 다수의 유로를 형성하며 증기와 분리되어 간극 내부로 공급되었다. CCFL 을 일으켜 물이 공급되지 못한 부분에서는 히터 표면이 건조되어 국부적인 CHF(Critical Heat Flux)가 발생하였다.