• 제목/요약/키워드: Nucleate

검색결과 244건 처리시간 0.03초

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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    • 제35권3호
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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.

A Dry-Spot Model for the Prediction of Critical Heat Flux in Water Boiling in Bubbly Flow Regime

  • Ha, Sang-Jun;No, Hee-Cheon
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 추계학술발표회논문집(1)
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    • pp.546-551
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    • 1997
  • This paper presents a prediction of critical heat flux (CHF) in bubbly flow regime using dry-spot model proposed recently by authors for pool and flow boiling CHF and existing correlations for forced convective heat transfer coefficient, active site density and bubble departure diameter in nucleate boiling region. Without any empirical constants always present in earlier models, comparisons of the model predictions with experimental data for upward flow of water in vertical, uniformly-heated round tubes are performed and show a good agreement. The parametric trends of CHF have been explored with respect to variations in pressure, tube diameter and length, mass flux and inlet subcooling.

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열전달 촉진관에서 탄화수소계 냉매의 풀비등 열전달계수 (Pool Boiling Heat Transfer Coefficients of Hydrocarbon Refrigerants on Various Enhanced Tubes)

  • 박기정;정동수
    • 설비공학논문집
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    • 제18권12호
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    • pp.1017-1024
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    • 2006
  • In this work, pool boiling heat transfer coefficients (HTCs) of five hydrocarbon refrigerants of propylene, propane, isobutane, butane and dimethylether (DME) were measured at the liquid temperature of $7^{\circ}C$ on a 26 fpi low fin tube, Turbo-B, and Thermoexcel-E tubes. All data were taken from 80 to $10kW/m^2$ in the decreasing order of heat flux. The data of hydrocarbon refrigerants showed a typical trend that nucleate boiling HTCs obtained on enhanced tubes also increase with the vapor pressure. Fluids with lower reduced pressure such as DME, isobutane, and butane took more advantage of the heat transfer enhancement mechanism of enhanced tubes than those enhancement ratios of $2.3\sim9.4$ among the tubes tested due to its sub-channels and re-entrant cavities.

튜브 경사각이 포화풀핵비등 열전달에 미치는 영향 (Effects of Tube Inclination on Saturated Nucleate Pool Boiling Heat Transfer)

  • 강명기
    • 대한기계학회논문집B
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    • 제32권5호
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    • pp.327-334
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    • 2008
  • Effects of tube inclination on pool boiling heat transfer have been studied for the saturated water at atmospheric pressure. For the analysis, seven inclination angles varying from the horizontal to the vertical and two tube diameters(25.4 and 30.0 mm) are tested. According to the results, inclination angles result in much change on heat transfer. For the same wall superheat(about $5.3^{\circ}C$) the ratio between two heat fluxes for the $45^{\circ}$ inclined and the vertical has the value of more than five when the tube diameter is 25.4mm. As the inclination angle is increasing from the horizontal to the vertical direction heat transfer is gradually increasing because of the increase in liquid agitation. However the detailed tendency depends on the ratio between the tube length and the diameter.

Solanum nigrum L.의 약배양에 관한 연구 II (Studies on The Anther Culture of Solanum nigrum L. II)

  • 한창열
    • Journal of Plant Biology
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    • 제14권2호
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    • pp.7-10
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    • 1971
  • Haploid cell obta-ined from microspores of Solanum nigrum were cultured on two kinds of medium, "Callus-inducing medium" and "Differentiation medium", in order to conduct histological studies of callus and examine differentiation of plantlets. On the callus-inducing medium the calli grew rapidly. The bulk of callus mass was light brown colored "Wet callus" covered on the surface with thin layers of rough and gleaming "White callus". The wet callus was consisted of parenchyma and meristematic tissues, while the white callus had no meristematic tissues. Large parenchyma cells, by successive divisions, became multicellular or poly nucleate cells which developed later to be meristematic tissues. The calli embedded on the differentiation medium quickly turned to dark brown color. Plantlets, however, came out later from these blackened callus mass. In the callus sectioned about ten weeks after imbedding on the differentiation medium, radially elongated tissue, concentric tissue, epidermis, tracheid-like structure, and plant jprimordia were observed.ure, and plant jprimordia were observed.

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각종 담금제의 냉각성능에 관한 연구 II

  • 민수홍;구본권;김상열
    • 대한기계학회논문집
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    • 제13권3호
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    • pp.419-423
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    • 1989
  • 본 연구에서는 담금유의 냉각능에 관한 상세한 연구는 우리나라에서는 아직 미비한 상태에 있으나, 저자 등은 제1보에서 서술한 실험장치 및 은시편을 사용하여 여러 광.식물성유의 냉각곡선을 구하고, 이로부터 냉각성능을 나타내는 파라미터들을 구하여, 객관적인 냉각성능을 평가하였다.

2상 격자 볼츠만 방법을 이용한 접촉각과 Bubble Necking 2차원 수치 모사 (Two-dimensional Numerical Simulation of the Contact Angle and the Bubble Necking Using the Two Phase Lattice Boltzmann Method)

  • 유승엽;김재용;고성호
    • 한국유체기계학회 논문집
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    • 제14권3호
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    • pp.10-17
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    • 2011
  • Free energy based lattice Boltzmann method (LBM) has been used to simulate the contact angle and the bubble necking with large density ratio. LBM with the proper contact angle model is able to reduce the spurious currents and eliminate the singularity in the contact lines. The numerical results of the contact angles are satisfied with the Youngs law. For bubble necking flows, simulations are executed for various viscosities and contact angles. The phenomena of the bubble necking are simulated successfully and the subsequent results are presented. The present method is also applicable to the nucleate boiling flows.

The Role of SH2 Domain-containing Leukocyte Phosphoprotein of 76 kDa in the Regulation of Immune Cell Development and Function

  • Koretzky, Gary A.
    • IMMUNE NETWORK
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    • 제9권3호
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    • pp.75-83
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    • 2009
  • Recent years have seen an explosion of new knowledge defining the molecular events that are critical for development and activation of immune cells. Much of this new information has come from a careful molecular dissection of key signal transduction pathways that are initiated when immune cell receptors are engaged. In addition to the receptors themselves and critical effector molecules, these signaling pathways depend on adapters, proteins that have no intrinsic effector function but serve instead as scaffolds to nucleate multimolecular complexes. This review summarizes some of what has been learned about one such adapter protein, SH2 domain-containing leukocyte phosphoprotein of 76 kDa (SLP-76), and how it regulates and integrates signals after engagement of immunoreceptors and integrins on various immune cell lineages.

A Study on the Enhancement of Westinghouse DNB Protection Logic

  • Na, Man-Gyun
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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    • pp.515-520
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    • 1996
  • Since the conventional Westinghouse DNB (Departure from Nucleate Boiling) protection logic is implemented on analog circuits, the logic must be very simple. However, if the DNB protection logic is implemented in a digital processor, a little bit of complexity can be allowed to increase the thermal (or operation) margin. The Westinghouse OTΔT DNB protection logic heavily restricts the operation region by applying the same logic for a full range of pressure in order to maintain its simplicity. In this work, the different DNB protection logic is used for several regions of pressure. The proposed method is applied to Yonggwang 1&2 nuclear power plants and it is calculated that the improved OTΔT can have 5.07% percent more thermal margin than the conventional OTΔT trip logic.

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A Heuristic Application of Critical Power Ratio to Pressurized Water Reactor Core Design

  • Ahn, Seung-Hoon;Jeun, Gyoo-Dong
    • Nuclear Engineering and Technology
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    • 제34권1호
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    • pp.68-79
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    • 2002
  • The approach for evaluating the critical heat flux (CHF) margin using the departure from nucleate boiling ratio (DNBR) concept has been widely applied to PWR core design, while DNBR in this approach does not indicate appropriately the CHF margin in terms of the attainable power margin-to-CHF against a reactor core condition. The CHF power margin must be calculated by increasing power until the minimum DNBR reaches a DNBR limit. The Critical Power Ratio (CPR), defined as the ratio of the predicted CHF power to the operating power, is considered more reasonable for indicating the CHF margin and can be calculated by a CPR orrelation based on the heat balance of a test bundle. This approach yields directly the CHF power margin, but the calculated CPR must be corrected to compensate for many local effects of the actual core, which are not considered in the CHF test and analysis. In this paper, correction of the calculated CPR is made so that it may become equal to the DNB overpower margin. Exemplary calculations showed that the correction tends to be increased as power distribution is more distorted, but are not unduly large.