• Title/Summary/Keyword: Flow Boiling Heat Transfer

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Study on Heat Transfer and Fouling of Flow Boiling Systems using Oxidized Graphene Nanofluid (유동 비등 시스템에서 산화 그래핀 나노유체의 열전달 및 파울링에 대한 연구)

  • Kim, Woo-Joong;Kim, Nam-Jin
    • Journal of the Korean Solar Energy Society
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    • v.36 no.3
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    • pp.63-74
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    • 2016
  • The nanofluids are the fluids with excellent thermal property, it is expected as a working fluid of the next generation. The nanofluids are well known that if it is used in the boiling heat transfer system, the critical heat flux is enhanced up to 200%, and the thermal conductivity is increased up to from 10 to 160%. However, the fouling phenomenon can be occurred that nanoparticles of nanofluids are deposited on the heat transfer surface. Therefore, to investigate relation between nanofluid and fouling, this study is carried out using oxidized graphene nanofluid. Also it compared and analyzed the critical heat flux and the boiling heat transfer coefficient. As the result, in case of oxidized graphene deposition for fouling, the critical heat flux is increased up to 20% more than oxdized graphene nanofluid. However, the boiling heat transfer coefficient is decreased down to about $6kW/m^2K$ at $1,000kW/m^2$ more than pure water.

A Study on the Correlations Development for Film Boiling Heat Transfer on Spheres

  • Jeong, Yong-Hoon;Beak, Won-Pil;Chang, Soon-Heung
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.437-442
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    • 1998
  • Film boiling is the heat transfer mechanism that can occurs when large temperature differences exist between a cold liquid and hot material. In the nuclear reactor safety analysis, film boiling has become an important issue in recent years. During severe accident, hot molten corium fall into relatively cool water, and fragment into spheres or sphere-like particles. If the steam explosion is triggered, the thermal energy of corium is converted into the mechanical energy that can threaten the integrity of reactor vessel or reactor cavity. One of the important concerns in the heat transfer analysis during pre-mixing stage is the film boiling heat transfer between the corium and water/steam two-phase flow. Until now, considerable works on film boiling heat been performed. However, there is no available correlation adequate for severe accident analysis. In this study, boiling heat transfer correlations have been developed, and their applicable ranges heat been enlarged and their prediction accuracy has been enhanced.

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R-134a Flow Boiling on a Plain Tube Bundle (평활관군의 R-134a 흐름비등에 관한 연구)

  • 김종원;김정오;김내현
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.13 no.1
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    • pp.9-17
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    • 2001
  • In this study, flow boiling experiments were performed using R-134a on a plain tube bundle. Tests were conducted for the following range of variables; quality from 0.1 to 0.9, mass flux from $8\;kg/m^2s$ to $26\;kg/m^2s$ and heat flux from $10\;kW/m^2s$ to $40\;kW/m^2s$. The heat transfer coefficients were strongly dependent on the heat flux. However, they were almost independent on the mass flux or quality. The data are compared with the modified Chen model, which satisfactorily () predicted the data. Original Chen model, however, did not adequately predict the effect of quality. The reason may be attributed to the flow pattern of the present test, where the bubbly flow prevailed for the entire test range. The heat transfer coefficients of the tube bundle were 6~40% higher than those of the single tube pool boiling.

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Study on flow boiling heat transfer in two-phase micro-channels heat sink (2상 마이크로 채널 히트 싱크에서의 유동 비등 열전달에 관한 연구)

  • Choi, Yong-Seok;Lim, Tae-Woo
    • Journal of Advanced Marine Engineering and Technology
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    • v.39 no.7
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    • pp.702-708
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    • 2015
  • Two-phase flow boiling experiments were conducted using FC-72 as the working fluid. The micro-channels consisted of 15 channels with a depth of 0.2 mm, width of 0.45 mm, and length of 60 mm. Tests were performed over a mass flux range of $200-400kg/m^2s$, heat flux range of $5.6-49.0kW/m^2$, and vapor quality range of 0.02-0.93. Based on the results of the experiment, the heat transfer mechanism by nucleate boiling was dominant at a lower vapor quality (x<0.2), whereas that in the region of a vapor quality greater than 0.2 was complexly influenced by nucleate boiling and forced convection boiling. The nucleate boiling and forced convection boiling could be expressed as functions of the boiling number and convection number, respectively. In addition, the heat transfer coefficient obtained by the experiment was compared with the heat transfer coefficient by the existing correlation.

Boiling Heat Transfer Characteristics of $CO_2$ in Horizontal Smooth Microchannel (수평 microchannel의 $CO_2$ 비등열전달)

  • Choi, Kwang-Il;Ardiyansyah, Ardiyansyah;Oh, Jong-Taek
    • Proceedings of the SAREK Conference
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    • 2007.11a
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    • pp.241-246
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    • 2007
  • The present paper dealt with an experimental study of boiling heat transfer characteristics of $CO_2$. Heat transfer coefficients of the refrigerant flow inside horizontal smooth microchannel were obtained with inner tube diameter of 0.3mm and length of 300mm. The direct electric heating method was applied for supplying the heat uniformly to the refrigerant. The experiments were conducted with $CO_2$ purity of 99.99%, at saturation temperature of $10^{\circ}C$, mass flux ranges of $300{\sim}900\;kg/m^2s$, and heat flux ranges of $15{\sim}45\;kW/m^2$. While heat transfer coefficient increased with the increase of heat flux in the low quality region, the heat transfer coefficient decreased with the increase of quality in the high quality region. The heat transfer coefficients were compared with seven existing correlations with the Gungor-Winterton's(1986) correlation gave the best prediction. A new corelation to predict the two-phase flow heat transfer coefficient was developed based on the Chen(1966) correlation. The new correlation predicted the experimental data well with a mean deviation of 9.69% and average deviation of -3.03%.

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Effects of the Width and Location of a Flow Disturbing Plate on Pool Boiling Heat Transfer on a Vertical Tube

  • Kang Myeong-Gie
    • Nuclear Engineering and Technology
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    • v.35 no.3
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    • pp.191-205
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    • 2003
  • Effects of the width and location of a flow disturbing circular plate, installed at a vertical tube surface, on nucleate pool boiling heat transfer of water at atmospheric pressure have been investigated experimentally. Through the tests, changes in the degree of intensity of liquid agitation have been analyzed. The plate changes the fluid flow around the tube as well as heat transfer coefficients on the tube surface. It is identified that the plate width changes the rate of the circulating flow whereas its location changes the growth of the active agitating flow. Moreover, the flow chugging was observed at the downside of the plate.

Forced convective boiling heat transfer for a ternary refrigerant mixture inside a horizontal tube (수평관내 3성분 혼합냉매의 강제대류비등 열전달)

  • 오종택
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.11 no.6
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    • pp.912-920
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    • 1999
  • The forced convective boiling heat transfer coefficients of R-407C were measured inside a horizontal tube 6.0mm I.D. and 4.0m long. The heat transfer coefficients increased according to an increase in heat flux at constant mass flux. Because nucleation was completely suppressed in the two-phase flow region with high quality, heat transfer coefficients in forced convective evaporation were higher than those in nucleate boiling region. Average heat transfer coefficients of R-407C were about 30 percent lower than the pure refrigerant correlation, due to mass transfer resistance at the gas-liquid interface. However, the total experimental data shows an agreement with the predicted data for ternary refrigerant mixtures with a mean deviation of 30%.

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An Experimental Study on Flow Boiling Heat Transfer within Horizontal Rectangular Channels with Small Heights (미세 수평 사각 유로에서의 비등 열전달에 대한 실험적 연구)

  • Lee, Sang-Yong;Lee, Han-Ju
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.25 no.9
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    • pp.1209-1218
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    • 2001
  • The present paper proposes a new correlation for the flow boiling heat transfer coefficients in the low flow rate condition (Re(sub)LF$\leq$200) within horizontal rectangular channels with small gaps (heights). The gap between the upper and the lower plates of each channel ranges from 0.4 to 2mm while the channel width being fixed to 20mm. Refrigerant 113 was used as the test fluid. The mass flux ranges from 50 to 200kg/㎡s and the channel walls were uniformly heated with the heat flux range of 3-15kW/㎡. The quality range covers from 0.19 to 0.76 and the flow pattern is considered to be annular. The measured heat transfer coefficients increase with the mass flux and the local quality; however the effect of the heat flux appears to be minor. At the low mass flux condition, which is more likely with the smaller gap size, the heat transfer is primarily controlled by the liquid film thickness. The proposed F factor for the heat transfer coefficient in the range of Re(sub)LF$\leq$200 well represents the experimental data within the deviation of $\pm$20%. The Kandlikars flow boiling correlation covers the higher flow-rate range(Re(sub)LF>200) within the deviation of $\pm$20%.

A Study on Influence of Flow Boiling Heat Transfer on Fouling Phenomenon in Nanofluids (나노유체에서 파울링 현상이 유동 비등 열전달에 미치는 영향에 대한 연구)

  • Kim, Woojoong;Yang, Yongwoo;Kim, Younghun;Park, Sungseek;Kim, Namjin
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.28 no.3
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    • pp.95-102
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    • 2016
  • A boiling heat transfer is used in various industry such as power generation systems, heat exchangers, air-conditioning and refrigerations. In the boiling heat transfer system, the critical heat flux (CHF) is the important factor, and it indicated safety of the system. It has kept up studies on the CHF enhancement. Recently, it is reported the CHF enhancement, when working fluid used the nanofluid with high thermal properties. But it could be occurred nanoflouling phenomenon from nanoparticle deposition, when nanofluid applied the heat transfer system. And, it is reported that the safety and thermal efficiency of heat transfer system could decrease. Therefore, it is compared and analyzed to the CHF and the boiling heat transfer coefficient on effect of artificial nanofouling (coating) in oxidized multi-wall carbon nanotube nanofluids. As the result, the CHF of oxidized multi-wall carbon nanofluids and the CHF of artificial nanofouling in the nanofluids increased to maximum 99.2%, 120.88%, respectively. A boiling heat transfer coefficient in nanofluid increased to maximum 24.29% higher than purewater, but artificial nanofouling decreased to maximum -7.96%.

Study on Film Boiling Heat Transfer of Spray Cooling in Dilute Spray Region (희박 분무영역에서의 분무냉각 막 비등 열전달에 관한 연구)

  • Kim Yeung Chan
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.29 no.2 s.233
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    • pp.279-286
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    • 2005
  • This study presents experimental results on the heat transfer coefficients in the film boiling region of spray cooling for actual metallurgical process. In this study, the heat flux distributions of a two dimensional dilute spray impinging on a hot plate were experimentally investigated. A stainless steel block was cooled down from intial temperature of about $800^{\circ}C$ by twin fluid (air-water) flat spray. It was found from the experimental results that the heat transfer area was classified into the stagnation region and wall-flow region. In the stagnation region, the experimental data of local heat transfer coefficient was closely correlated with the local droplet-flow-rate supplied from the spray nozzle directly. Thus, the local heat transfer coefficients are in good agreement with the predicted values from the correlations proposed by our previous study. In wall-flow region, however, remarkable differences are observed between experimental data and predicted values because the number of rebound droplets increase with increasing the distance from the stagnation point.