• 제목/요약/키워드: vertical two-phase flow

검색결과 137건 처리시간 0.022초

수직관에서 2상선회유동이 보이드분포와 압력강하에 미치는 영향 (The Effects of Two - Phase Swirling Flow on Void Distribution and Pressure Drop in a Vertical Tube)

  • 김인석;손병진;신현동;곽기태
    • 설비공학논문집
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    • 제1권2호
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    • pp.190-201
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    • 1989
  • This experimental investigation has been conducted to determine the effects of swirling angle and flow patterns on distributions of void fraction, bubble velocity and two-phase pressure drop in a vertical straight tube. Swirling angles of $0^{\circ}$ (non swirling), $30^{\circ}$, and $45^{\circ}$ were tested with air-water two components over a range of superficial air velocities. A transparent lucite tube of 38mm in internal diameter was used for the test section. The void fraction and bubble velocities were measured by means of a optical fiber probe at the upper part of the swirler in the test section. Pressure drops which seem to be closely related with flow patterns and swirling angle were measured by a differential pressure transducer. It is shown that the probability density functions of pressure drop demonstrate peculiar features for both swirling angles and flow patterns, whereas the distributions of void fraction and bubble velocities are parabolic and flat shape in the vicinity of tube center, respectively except bubbly flow in any swirling angle cases, and the void fraction increases with increasing swirling angle around the center of tube.

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A SIMPLE ANALYTICAL METHOD FOR NONLINEAR DENSITY WAVE TWO-PHASE INSTABILITY IN A SODIUM-HEATED AND HELICALLY COILED STEAM GENERATOR

  • Kim, Seong-O;Choi, Seok-Ki;Kang, Han-Ok
    • Nuclear Engineering and Technology
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    • 제41권6호
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    • pp.841-848
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    • 2009
  • A simple model to analyze non-linear density-wave instability in a sodium-cooled helically coiled steam generator is developed. The model is formulated with three regions with moving boundaries. The homogeneous equilibrium flow model is used for the two-phase region and the shell-side energy conservation is also considered for the heat flux variation in each region. The proposed model is applied to the analysis of two-phase instability in a JAEA (Japan Atomic Energy Agency) 50MWt No.2 steam generator. The steady state results show that the proposed model accurately predicts the six cases of operating temperatures on the primary and secondary sides. The sizes of three regions, the secondary side pressure drop according to the flow rate, and the temperature variation in the vertical direction are also predicted well. The temporal variations of the inlet flow rate according to the throttling coefficient, the boiling and superheating boundaries and the pressure drop in the two-phase and superheating regions are obtained from the unsteady analysis.

수직상향 이상류에서 동심원관 간극이 유동양식과 보이드분포에 미치는 영향 (Effects of Annular Gap Size on the Flow Pattern and Void Distribution in a Vertical Upward Two-Phase Flow)

  • 손병진;김인석;김문철
    • 대한설비공학회지:설비저널
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    • 제16권4호
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    • pp.383-391
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    • 1987
  • An experimental investigation has been conducted to determine the flow pattern for two-component , two-phase mixtures which flow vertically upwards in concentric annuli based on the measurement for the local void fraction and the distribution of the local void fraction in various radial locations in the annular gap. The annular test section consists of a lucite outer tube whose inside diameter is 38mm and a stainless steel rod, The rod diameter is either :2mm,16mm or 20mm. It is demonstrated that the probability density function of the fluctuations in void fraction may be used as an flow pattern indicator and the local void fraction distribution depends on the flow pattern and radial location in the annular passage.

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협소 사각유로에서 대향류 2상유동의 기공률과 압력구배 (Void Fraction and Pressure Gradient of Countercurrent Two-Phase Flow in Narrow Rectangular Channels)

  • 김병주;정은수;손병후
    • 설비공학논문집
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    • 제13권4호
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    • pp.304-311
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    • 2001
  • An experimental study on the countercurrent two-phase flow in narrow rectangular channels has been performed. The void fraction and the pressure gradient were investigated using air and water in 760 mm long, 100 mm wide. vertical test sections with 2, 3 and 5 mm channel gaps. Tests were systematically performed with downward liquid superficial velocities and upward gas velocities covering 0 to 0.08 and 0 to 2.5 m/s ranges. respectively. the experimental results were compared with the previous correlations, which were mainly for round tubes, and the qualitative trends were found to be in good agreements. However the quantitative discrepancies were hardly neglected. as the superficial gas velocities increased, the void fraction increased and the pressure gradient decreased, where the effects of the liquid superficial velocities were infinitesimal. as the gap width of the rectangular channel increased the void fraction and the 2-phase frictional pressure gradient approached those values for the round tubes. Equi-periphery diameter, rather than the hydraulic diameter, seemed to be more effective in the analysis of two-phase flow behavior.

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수직상향류 공기-물 이상유동영역 판별 (Vertical Upward Air-Water Two-Phase Flow Regime Identification)

  • 이바로;장영준;고민석;이보안;이연건;김신
    • 에너지공학
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    • 제22권4호
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    • pp.362-369
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    • 2013
  • 이상유동은 원자력 발전소 내 노심과 석유 수송 등 여러 산업 분야에서 빈번히 관찰된다. 이상유동영역은 두 상의 성질과 유량의 차이, 그리고 유로의 구조에 따라 결정된다. 유동영역의 판별은 시스템 설계 및 안전 해석에 있어 중요하기 때문에 많은 이론과 실험 연구들이 수행되었다. 본 연구는 파이프 내의 이상유동장에서 각 이상유동영역 및 천이경계에서의 특징 파악을 위한 기초 연구로서, 30 mm의 내경을 갖는 수직관의 수직상향류 공기-물 이상유동영역을 고속카메라와 Wire-mesh sensor(WMS)를 이용하여 판별하였다. 또한 유동양식을 정량적으로 판별하기 위해 액막 두께를 적용하였다. 판별한 실험 데이터를 Taitel 외와 Mishima와 Ishii의 유동양식선도와 비교하였다. 실험을 통해 판별한 유동영역은 기존의 유동양식선도와 전체적으로 잘 일치함을 보였다.

단상 및 이상유동 유량 계측을 위한 평균 양방향 유동 튜브 개발 (Development of an Average Bi-directional Flow Tube for the Measurement of Single and Two phase Flow Rate)

  • 윤병조;강경호;어동진;백원필
    • 유체기계공업학회:학술대회논문집
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    • 유체기계공업학회 2004년도 유체기계 연구개발 발표회 논문집
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    • pp.172-179
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    • 2004
  • Average Bi-directional flow tube was suggested to measure single and two phase flow rate. Its working principle is similar with Pilot tube, however, it makes it possible to eliminate the cooling system which is normally needed to prevent from flashing in the pressure impulse line of Pilot tube when it is used in the depressurization condition. The suggested instrumentation was tested in the air-water vertical test section which has 80mm inner diameter and 10m length. The flow tube was installed at 120 of L/D from inlet of test section. From the test, single air and water flow rate was measured successfully. For the emasurement of two phase flow rate, Chexal drift-flux correlation was used. In the test a new correlation of momentum exchange factor was suggested. The test result shows that the suggested instrumentation using the measured void fraction and Chexal drift-flux correlation can predict the mass flow rates within $10\%$ error of measured data.

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Development of a Linear Stability Analysis Model for Vertical Boiling Channels Connecting with Unheated Risers

  • Hwang, Dae-Hyun;Yoo, Yeon-Jong;Zee, Seong-Quun
    • Nuclear Engineering and Technology
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    • 제31권6호
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    • pp.572-585
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    • 1999
  • The characteristics of two-phase flow instability in a vertical boiling channel connecting with an unheated riser are investigated through the linear stability analysis model. Various two-phase flow models, including thermal non-equilibrium effects, are taken into account for establishing a physical model in the time domain. A classical approach to the frequency response method is adopted for the stability analysis by employing the D-partition method. The adequacy of the linear model is verified by evaluating experimental data at high quality conditions. It reveals that the flow-pattern-dependent drift velocity model enhances the prediction accuracy while the homogeneous equilibrium model shows the most conservative predictions. The characteristics of density wave oscillations under low-power and low-quality conditions are investigated by devising a simple model which accounts for the gravitational and frictional pressure losses along the channel. The necessary conditions for the occurrences of type-I instability and flow excursion are deduced from the one-dimensional D-partition analysis. The parametric effects of some design variables on low quality oscillations are also investigated.

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Experimental Study on Two-Phase Flow Parameters of Subcoolet Boiling in Inclined Annulus

  • Lee, Tae-Ho;Kim, Moon-Oh;Park, Goon-Cherl
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.29-48
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    • 1999
  • Local two-phase flow parameters of subcooled flow boiling in inclined annulus were measured to investigate the effect of inclination on the internal flow structure. Two-conductivity probe technique was applied to measure local gas phasic parameters, including void fraction, vapor bubble frequency, chord length, vapor bubble velocity and interfacial area concentration. Local liquid velocity was measured by Pilot tube. Experiments were conducted for three angles of inclination; 0$^{\circ}$(vertical), 30$^{\circ}$, 60$^{\circ}$. The system pressure was maintained at atmospheric pressure. The range of average void fraction was up to 10% and the average liquid superficial velocities were less than 1.3 m/sec. The results of experiments showed that the distributions of two-phase How parameters were influenced by the angle of channel inclination. Especially, the void fraction and chord length distributions were strongly affected by the increase of inclination angle, and flow pattern transition to slug flow was observed depending on the How conditions. The profiles of vapor velocity, liquid velocity and interfacial area concentration were found to be affected by the non-symmetric bubble size distribution in inclined channel. Using the measured distributions of local phasic parameters, an analysis for predicting average void fraction was performed based on the drift flux model and flowing volumetric concentration. And it was demonstrated that the average void fraction can be more appropriately presented in terms of flowing volumetric concentration.

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CFD simulation of compressible two-phase sloshing flow in a LNG tank

  • Chen, Hamn-Ching
    • Ocean Systems Engineering
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    • 제1권1호
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    • pp.31-57
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    • 2011
  • Impact pressure due to sloshing is of great concern for the ship owners, designers and builders of the LNG carriers regarding the safety of LNG containment system and hull structure. Sloshing of LNG in partially filled tank has been an active area of research with numerous experimental and numerical investigations over the past decade. In order to accurately predict the sloshing impact load, a new numerical method was developed for accurate resolution of violent sloshing flow inside a three-dimensional LNG tank including wave breaking, jet formation, gas entrapping and liquid-gas interaction. The sloshing flow inside a membrane-type LNG tank is simulated numerically using the Finite-Analytic Navier-Stokes (FANS) method. The governing equations for two-phase air and water flows are formulated in curvilinear coordinate system and discretized using the finite-analytic method on a non-staggered grid. Simulations were performed for LNG tank in transverse and longitudinal motions including horizontal, vertical, and rotational motions. The predicted impact pressures were compared with the corresponding experimental data. The validation results clearly illustrate the capability of the present two-phase FANS method for accurate prediction of impact pressure in sloshing LNG tank including violent free surface motion, three-dimensional instability and air trapping effects.