• 대한기계학회논문집B
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• 제26권1호
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• pp.116-124
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• 2002

An experimental parametric study of a tubular heat exchanger has been carried out far the saturated water at atmospheric pressure to determine effects of tube inclination on pool boiling heat transfer. For the analysis, seven inclination angles(0°, 15°, 30°, 45°, 60°, 75°, and 90°) and two tube diameters(12.7 and 19.1 mm) were tested. According to the results, inclination angles result in very much change on pool boiling heat transfer. As the inclination angle is around horizontal or vertical, maximum or minimum heat transfer is expected, respectively. For the same wall superheat(about 5.5K) the ratio between two heat fluxes fur $\theta$ =15° and 75° has the value of more than five when the tube diameter is 12.7 mm and heat flux is increasing.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2464-2476
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• 2021

Direct-contact heat transfer of a single saturated droplet upon colliding with a heated wall in the regime of film boiling was experimentally investigated using high-resolution infrared thermometry technique. This technique provides transient local wall heat flux distributions during the entire collision period. In addition, various physical parameters relevant to the mechanistic modelling of these phenomena can be measured. The obtained results show that when single droplets dynamically collide with a heated surface during film boiling above the Leidenfrost point temperature, typically determined by droplet collision dynamics without considering thermal interactions, small spots of high heat flux due to localized wetting during the collision appear as increasing We_n. A systematic comparison revealed that existing theoretical models do not consider these observed physical phenomena and have lacks in accurately predicting the amount of direct-contact heat transfer. The necessity of developing an improved model to account for the effects of local wetting during the direct-contact heat transfer process is emphasized.

• 대한기계학회논문집B
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• 제39권12호
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• pp.953-963
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• 2015

산업적으로 얇은 사각유로에서의 임계열유속을 포함한 열수력 현상을 이해하고 이를 시스템 설계에 반영해야 될 필요성이 증대되고 있다. 포화비등조건에서 임계열유속이 발생하는 주요기구는 일반적으로 환상유동 영역에서 액막이 건조되는 것이다. 이러한 임계열유속을 예측하기 위하여 원형관에 대한 대표적인 액막건조모델을 고찰하고 환상유동 시작 경계조건을 상수로 가정하는 기존 모델의 한계를 살펴보았다. 균일한 열유속으로 가열되는 얇은 수직사각유로 상향유동에서의 임계열유속을 예측하기 위하여 환상유동을 단순 모델링하고, 새로운 액막건조모델을 적용하였다. 284 개 실험데이타에 대한 예측성능을 확인한 결과 MAE 18.1%, RMSE 22.9% 예측오차로 실험데이타를 잘 예측할 수 있음을 확인하였다.

• 설비공학논문집
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• 제16권10호
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• pp.977-983
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• 2004

An experimental study on saturated flow boiling heat transfer of R113 was peformed in a vertical narrow rectangular channel with offset strip fins. Two-phase pressure gradients and boiling heat transfer coefficients in an electrically heated test section were measured in the range of quality $0{\sim}0.6$, mass flux $17{\sim}43kg/m^{2}s$, and heat flux of $500{\sim}3,000W/m^2$ Two-phase friction multipliers were determined as a function of Lockhart-Martinelli parameter. Local boiling heat transfer coefficients were analysed in terms of mass flux, heat flux and local vapor quality. Correlation for boiling heat transfer coefficients was proposed, which was in good agreement with experimental data.

• 한국식품저장유통학회지
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• 제16권1호
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• pp.87-93
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• 2009

삼겹살을 먹을 때, 동물성 지방의 섭취를 줄일 수 있는 효과적인 조리방법을 제시하기 위하여 삼겹살을 삶기, 찌기, 굽기 및 튀기기의 방법으로 가열조리한 후, 물리화학적 특성의 변화를 조사하였다. 가열조리에 의하여 전체적으로 수분 양은 감소하고 지질 양은 증가하였는데, 이에 따른 가열감량, 탈수량 및 탈유량은 튀기기와 삶기 처리구에서 높았다. 시료의 pH는 삶기 처리구에서 가장 많이 증가하였고, 시료로부터 추출한 지질의 산가와 굴절율은 튀기기 처리구에서 가장 많이 증가하였다. 경도, 점착성 및 저작성은 삶기에 의하여 크게 증가하였으나 튀기기 처리구에서는 크게 감소하였고, 탄력성은 삶기 처리구에서 가장 많이 감소하였으며, 응집성은 찌기 처리구에서 가장 많이 증가하였다. CIE $L^*$값은 찌기 처리구에서는 크게 증가하였지만 튀기기 처리구에서는 크게 감소하였고, CIE $a^*$값은 전체적으로 감소하였는데 삶기 처리구에서 가장 많이 감소하였으며, CIE $b^*$값은 삶기와 찌기 처리구에서는 감소하였지만 굽기와 튀기기 처리구에서는 증가하였다. 생 삼겹살 지방을 구성하는 지방산에는 oleic acid(42.4%), palmitic acid(23.9%)와 linoleic acid(16.1%)가 많았으며, 포화지방산에 대한 단일불포화지방산의 비율은 1.190 그리고 포화지방산에 대한 고도불포화지방산의 비율은 0.466 이었다. 가열조리 방법에 따른 시료의 지방산 조성은 튀기기 처리구를 제외하고는 거의 변화가 없었다. 따라서 삼겹살을 먹을 때 동물성 지방의 섭취를 줄일 수 있는 효과적인 조리방법은 삶기라고 판단된다.

• 대한기계학회논문집B
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• 제38권1호
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• pp.81-88
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• 2014

수평에 가깝게 설치된 튜브 원주면에 대해 평균 열전달계수를 결정하기 위한 실험적 연구를 수행하였다. 실험을 위하여 대기압 상태하의 물속에 잠긴 50.8 mm의 스테인리스강 튜브를 사용하였다. 과냉 및 포화 풀비등 조건을 모두 고려하였으며, 튜브 경사각은 수평으로부터 $9^{\circ}$까지 $3^{\circ}$ 간격으로 변경하였다. 포화상태에서는 튜브의 최하부로부터의 방위각이 $90^{\circ}$인 위치에서 측정한 국소비등열전달계수가 평균값으로 취급될 수 있으며, 이러한 경향은 튜브 경사각과는 무관함을 확인하였다. 그러나 물이 과냉상태인 경우, 평균 열전달계수의 위치는 경사각과 열유속에 의존한다. 열전달을 변화시키는 주된 열전달 기구는 액체교란 강도 및 기포군집에 의한 큰 기포 덩어리의 형성과 밀접한 관계가 있는 것으로 설명된다.

• Nuclear Engineering and Technology
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• 제50권7호
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• pp.1068-1078
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• 2018

Experiments were performed to investigate bubble behaviors and pool boiling Critical Heat Flux (CHF) on a thin flat rectangular copper heater fabricated on Printed Circuit Board (PCB), at various inclination angles. The surface inclination angles were $0^{\circ}$, $45^{\circ}$, $90^{\circ}$, $135^{\circ}$, and $180^{\circ}$. Results showed the Onset of Nucleate Boiling (ONB) heat flux increased with increasing heater orientation from $0^{\circ}$ to $90^{\circ}$, while early ONB occurred when the heater faced downwards ($135^{\circ}$ and $180^{\circ}$). The nucleate boiling was observed to be unstable at low heat flux (1-21% of CHF) and changed into typical boiling when the heat flux was above 21% of CHF. The result shows the CHF decreased with increasing heater orientation from $0^{\circ}$ to $180^{\circ}$. In addition, the bubble departure diameter at the heater facing upwards ($0^{\circ}$, $45^{\circ}$, and $90^{\circ}$) was more prominent compared to that of the heater facing downward ($135^{\circ}$). The nucleation site density also observed increased with increasing heat flux. Moreover, the departed bubbles with larger size were observed to require a longer time to re-heat and activate new nucleation sites. These results proved that the ONB, CHF, and bubble dynamics were strongly dependent on the heater surface orientation.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2591-2603
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• 2023

Simulating the Corrosion-Related Unidentified Deposit (CRUD) on the surface of fuel assemblies is necessary to predict the axial offset anomaly and the localized corrosion induced by the CRUD during the operation of nuclear power plants. A new CRUD model was developed to predict the formation of the CRUD deposits, considering the deposition and erosion mechanisms. The heat transfer and capillary flow within the CRUD were also considered to evaluate the boiling amount within the CRUD layer. This model predicted a CRUD deposit thickness of 44 ㎛ during a one-cycle operation of the Seabrook nuclear power plant. The CRUD deposition tended to accelerate and decelerate during the simulation, by being related to boiling mechanism on the deposits surface. Additionally, during a three-cycle operation corresponding to the refueling period, the CRUD deposition was saturated at a thickness of 80 ㎛, which was in good agreement with the suggested thickness for CRUD buildupin pressurized water reactors. Surface boiling on the thin CRUD deposits enhanced the acceleration of the deposition, even when the wick boiling properties were not favorable for CRUD deposition. To ensure the certainty of the simulation results, sensitivity analyses were conducted for the porosity, chimney density, and the constants employed in the proposed model of the CRUD.

• Journal of Mechanical Science and Technology
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• 제19권3호
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• pp.860-869
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• 2005

Local pool boiling on the outside and inside surfaces of a 51 mm diameter tube in horizontal direction has been studied experimentally in saturated water at atmospheric pressure. Much variation in local heat transfer coefficients was observed along the tube periphery. On the outside surface the maximum and the minimum are observed at ${\theta}=45^{\circ}$ and $180^{\circ}$, respectively. However, on the inside surface only the minimum was observed at ${\theta}=0^{\circ}$. Major mechanisms on the outside surface are liquid agitation and bubble coalescence while those on the inside surface are micro layer evaporation and liquid agitation. As the heat flux increases liquid agitation gets effective both on outside and inside surfaces. The local coefficients measured at ${\theta}=90^{\circ}$ can be recommended as the representative values of both outside and inside surfaces.

• Nuclear Engineering and Technology
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• 제41권3호
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• pp.271-278
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• 2009

Nucleate pool boiling of water in vertical annuli at atmospheric pressure has been studied experimentally and two empirical correlations have been suggested to obtain effects of geometric parameters on heat transfer. Data of the present and the previous tests range over a tube length of 0.50-0.57 m, a diameter of 16.5-34.0 mm, and an annular gap size of 3.7-44.3 mm. Through the analysis, tube bottom confinement (open or closed) has been investigated, as well. The developed correlations predict experimental data within a ${\pm}25%$ error bound. It has been identified that effects of the diameter and the length of heated tubes as well as the annular gap size should be counted into the analyses to estimate heat transfer coefficients accurately.