• Title/Summary/Keyword: 유동비등

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Numerical Analysis of Rotating Channel Flow with an Anisotropic $k-\varepsilon$ Turbulence Model (비등방 $k-\varepsilon$ 난류모델에 의한 회전 덕트유동의 수치해석)

  • Myeong, Hyeon-Guk
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.21 no.8
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    • pp.1046-1055
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    • 1997
  • An anisotropic k-.epsilon. turbulence model for predicting the rotating flows is proposed with the simple inclusion of a new parameter dealing with the extra straining effects in the .epsilon.-equation. This model is employed to compute the effects of Coriolis forces on fully-developed flow in a rotating channel. The predicted results indicate that the present model captures fairly well the striking rotational-induced effects on the Reynolds stresses and the mean flow distributions, including the argumentation of turbulent transport on the unstable side (pressure surface) of the channel and its damping on the stable side (suction surface).

Numerical study on thermophoretic deposition of highly absorbing emitting particles suspended in a non-isothermal two-phase flow system (비등온 이상유동 시스템에 부유된 고흡수, 방사하는 입자의 열환산적 부착현상에 대한 수치적 연구)

  • Yoa, S. J.
    • Journal of the korean Society of Automotive Engineers
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    • v.11 no.5
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    • pp.90-100
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    • 1989
  • 본 논문은 이상유동 시스템에 부유도니 슈트, 미분탄과 같은 고 흡수, 방사하는 입자에 의한 열 확산 현상에 대한 복사효과를 수치적으로 검토하였다. 가스, 입자유동의 지배방정식들은 오일러 관점의 two-fluid model 의 근간에서 수행되었으며, 에너지 방정식의 비선형 복사생성항은 P-1 근사방법에 의해 계산되었다. 복사효과가 증가될 때에 열확산적 입자의 벽면에 대한 부착율은 상당히 낮아짐을 보였으며 열확산 현상의 스토크스 수에 따른 효과도 고려되었다.

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Effects of Pitch on Pool Boiling from Horizontal Tube Array (피치가 수평 튜브 배열의 풀비등에 미치는 영향)

  • Kang, Myeong-Gie
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.41 no.11
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    • pp.719-726
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    • 2017
  • An experimental study was performed to investigate the combined effects of the pitch and heat flux of nearby tubes on boiling in a pool as well as the heat transfer from a horizontally-installed tube bundle. For this test, two smooth stainless steel tubes (19 mm outside diameter) were used, and the water was at atmospheric pressure. The pitch of these tubes was varied between 28.5 mm and 95 mm, and the heat flux of the nearby tube altered between 0 and $90kW/m^2$. Enhancements in heat transfer were clearly observed when the heat flux of the nearby tube increased while the heat flux of the test section remained below $40kW/m^2$. The tube pitch was found to have a negligible effect on heat transfer when the pitch was greater than four times larger than the tube diameter. The circulating flow, convective flow, and liquid agitation were all seen to enhance heat transfer; however, the interaction between the flow and coalescence of bubbles was detrimental to heat transfer.

Boiling Heat Transfer in a Narrow Rectangular Channel with Offset Strip Fins (오프셋 스트립 휜이 있는 협소 사각유로의 비등열전달)

  • Kim Byong Joo;Jeong Eun Soo;Sohn Byong Hu
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.16 no.10
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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.

Numerical Study of Low-pressure Subcooled Flow Boiling in Vertical Channels Using the Heat Partitioning Model (열분배모델을 이용한 수직유로에서의 저압 미포화비등 해석)

  • Lee, Ba-Ro;Lee, Yeon-Gun
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.40 no.7
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    • pp.457-470
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    • 2016
  • Most CFD codes, that mainly adopt the heat partitioning model as the wall boiling model, have shown low accuracies in predicting the two-phase flow parameters of subcooled boiling phenomena under low pressure conditions. In this study, a number of subcooled boiling experiments in vertical channels were analyzed using a thermal-hydraulic component code, CUPID. The prediction of the void fraction distribution using the CUPID code agreed well with experimental data at high-pressure conditions; whereas at low-pressure conditions, the predicted void fraction deviated considerably from measured ones. Sensitivity tests were performed on the submodels for major parameters in the heat partitioning model to find the optimized sets of empirical correlations suitable for low-pressure subcooled flow boiling. The effect of the K-factor on the void fraction distribution was also evaluated.

탄소나노튜브 나노유체의 파울링 현상에 따른 열적 특성에 대한 연구

  • Mun, Ji-Eun;Kim, Yeong-Hun;Kim, Nam-Jin
    • Proceedings of the Korean Vacuum Society Conference
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    • 2016.02a
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    • pp.383.1-383.1
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    • 2016
  • 열전달 시스템에서 임계 열유속 발생 시 시스템의 물리적 손상을 야기하기 때문에 비등 열전달에서 임계 열유속은 열전달 시스템의 한계 또는 안전성을 나타낸다. 따라서 열전달 시스템의 안정성을 위해서는 임계 열유속 향상이 필수적이다. 최근에는 나노유체를 열전달 시스템에 적용할 경우 임계 열유속이 증가한다고 보고되었다. 하지만 나노유체는 원전 및 각종 열전달 시스템에 적용 시 나노입자가 열전달 표면에 침착되는 파울링 현상을 발생시킬 수 있으며, 이 때문에 시스템의 열효율이 크게 감소할 수 있다. 따라서 본 연구에서는 열전달 시스템에 나노유체를 적용했을 때, 나노유체의 침착현상이 시스템에 미치는 영향을 분석하였다. 그 결과 유속과 코팅시간이 증가할수록 산화처리된 다중벽 탄소나노튜브 나노유체의 임계 열유속이 크게 증가하고 있음을 확인할 수 있다. 하지만 나노입자 침착정도와 유속이 증가할수록 비등 열전달 표면과 유체의 포화온도의 차이인 과열도가 상당히 크게 증가함을 알 수 있었으며, 열전달 계수는 순수 물의 0 m/s의 비등 열전달 계수와 비교하면 감소하는 것을 확인하였다.

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Effects of Crud on reflood heat transfer in Nuclear Power Plant (핵연료 크러드가 원전 재관수 열전달에 미치는 영향)

  • Yoo, Jin;Kim, Byoung Jae
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.22 no.5
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    • pp.554-560
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    • 2021
  • CRUD (chalk river unidentified deposits) is a porous material deposited on the surface of nuclear fuel during nuclear power plant operation. The CRUD is composed of metal oxides, such as iron, nickel, and chromium. It is essential to investigate the effects of the CRUD layer on the wall heat transfer between the nuclear fuel surface and the coolant in the event of a nuclear accident. CRUD only negatively affects the temperature of the nuclear fuel due to heat resistance because the effects of the CRUD layer on two-phase boiling heat transfer are not considered. In this study, the physical property models for the porous CRUD layer were developed and implemented into the SPACE code. The effects of boiling heat transfer models on the peak cladding temperature and quenching were investigated by simulating a reflood experiment. The calculation results showed some positive effects of the CRUD layer.

Flow Characteristics of Cryogenic Oxidizer in Liquid Propellant Rocket Engine (액체로켓 엔진에서의 극저온 산화제의 유동 특성)

  • 조남경;정용갑;문일윤;한영민;이수용;정상권
    • Journal of the Korean Society of Propulsion Engineers
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    • v.6 no.4
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    • pp.15-23
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    • 2002
  • In most cryogenic liquid rocket engines, liquid oxygen manifold and injector are not thermally insulated from room temperature environment fur reducing system complexity and the weight. This feature of cryogenic liquid rocket engine results in the situation that cryogenic liquid oxygen flow is easy to be vaporized especially in the vicinity of the manifold and the injector wall. The research in this paper is focused on two-phase flow phenomena of liquid oxygen in rocket engine. Vapor fraction was estimated by comparing the measured two-phase flow pressure drop in engine manifold and the injector with ideal single phase pressure drop. Heat flux into cryogenic flow is estimated by measuring the wall temperature on the engine manifold to examine boiling characteristics. Suitable correlations for cryogenic two-phase flow were also reviewed to see their applicability. In addition, the effect of vapor generation in liquid rocket engine manifold and injector on engine performance and stability was considered.