• Title/Summary/Keyword: 횡유동

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A Study on Fluid Flow and Heat Transfer of a Corrugated Structure for Crossflow Reduction of Impingement Jet (충돌제트에서의 횡방향 유동 감소를 위한 파형 구조의 유동 및 열전달에 관한 연구)

  • Hwang, Byeong Jo;Kim, Seon Ho;Joo, Won Gu;Cho, Hyung Hee
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.41 no.5
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    • pp.329-339
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    • 2017
  • Impingement jets have been applied in a wide variety of fields as they provide significantly high heat transfer on the impingement-jet stagnation zone. However, the crossflow in an impingement chamber developed by spent wall jets can disrupt and deflect the downstream jets in the array, leading to a decrease in the cooling performance of an array of impingement jets. A numerical analysis is made of the fluid flow and heat transfer characteristics in a corrugated structure that traps the spent air in the corrugations between impingement jets and reduces crossflow effects on downstream jets. All computations are performed by considering a three-dimensional, steady, and incompressible flow by using the ANSYS-CFX 15.0 code. The effects of the configuration parameters of the corrugated structure on crossflow reduction of the array of impingement jets are presented and discussed.

Hydrodynamic Mass and Damping of Tube Bundles in Two-Phase Cross-Flow (2상 횡유동을 받는 튜브집합체의 추가질량과 감쇠)

  • 김범식;손갑헌;김병구
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.13 no.6
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    • pp.1128-1146
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    • 1989
  • 본 논문에서는 2상 횡유동의 진동 메카니즘을 규명하기 위한 실험계획의 일환으로 실시된 실험으로 부터 튜브집합체의 추가질량(hydrodynamic mass)과 감쇠 (damping)에 대해 고찰하였다. 실험은 튜브배열과 피치 대 직경비(pitch-over-di- ameter:.rho./d)가 상이한 튜브집합체에 대해 2상 유체를 모의한 공기-물(air-water) 혼합물에서 수행하였다. 액체상태로부터 99%의 보이드율까지 변화된 2상 유체의 유량은 튜브가 유체탄성 불안정성 (fluidelastic instability)에 도달할 때까지 점진적으로 증가하였다.

Numerical Simulation Study on Gas-Particle Two-Phase Jets in a Crossflow (I) -Two-Phase Jet Trajectory and Momentum Transfer Mechanism- (고체입자가 부상된 자유 횡분류 유동에 대한 전산모사 연구 (I) -2상 분류궤적과 운동량 전달기구-)

  • 한기수;정명균
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.15 no.1
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    • pp.252-261
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    • 1991
  • A particle trajectory model to simulate two-phase particle-laden crossjets into two-dimensional horizontal free stream has been developed to study the variations of the jet trajectories and velocity variations of the gaseous and the particulate phases. The following conclusions may be drawn from the predicted results, which are in agreement with experimental observations. The penetration of the two-phase jet in a crossflow is greater than that of the single-phase jet. The penetration of particles into the free stream increases with increasing particle size, solids-gas loading ratio and carrier gas to free stream velocity ratio at the jet exit. When the particle size is large, the solid particles separate from the carrier gas , while the particles are completely suspended in the carrier gas for the case of small size particles. As the particle to carrier gas velocity ratio at the jet exit is less than unity, the particles in the vicinity of the jet exit are accelerated by the carrier gas. As the injection angle is increased, the difference of the particle trajectory from that of the pure gas becomes larger. Therefore, it can be concluded that the velocities and trajectories of the particle-laden jets in a crossflow change depending on the solids-gas loading ratio, particle size, carrier gas to free stream velocity ratio and particle to gas velocity ratio at the jet exit.

Fluid-Elastic Instability of Tube Bundles in Two-Phase Cross-Flow (2상 횡유동을 받는 튜브군의 유체탄성 불안정성)

  • 김범식;장효환
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.15 no.6
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    • pp.1948-1966
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    • 1991
  • Two-phase cross-flow exists in many shell-tube heat exchangers such as condensers, reboilers and nuclear steam generators. To avoid problems due to excessive vibration, information on vibration excitation in two-phase cross-flow is required. Fluid-elastic instability is discussed in this paper. Four tube bundle configurations were subjected to increasing flow up to the onset of fluid-elastic instability. The tests were done on bundles with one flexible tube surrounded by rigid tubes. The fluid-elastic instability behavior is different for intermittent flows than for bubbly flows. For bubbly flows, the observed instabilities satisfy the relationship V/fd=K(2.pi..zeta. m/rho. $d^{21}$)$^{0.51}$ in which the minimum instability factor K was found to be 2.3 for bundles of p/d=1.22. The lowest critical velocities for fluid-elastic instability were experienced with parallel-triangular tube bundles. For intermittent flow, the observed instabilities did not follow the forgoing relation-ship. Significantly lower flow velocities were required for instability..

Fluid-elastic Instability in a Tube Array Subjected to Two-Phase Cross Flow (2 상 횡 유동장에 놓인 관군의 유체탄성불안정성)

  • Sim, Woo-Gun;Park, Mi-Yeon
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.33 no.2
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    • pp.124-132
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    • 2009
  • Experiments have been performed to investigate fluid-elastic instability of tube bundles, subjected to twophase cross flow. Fluid-elastic is the most important vibration excitation mechanism for heat exchanger tube bundles subjected to the cross flow. The test section consists of cantilevered flexible cylinder(s) and rigid cylinders of normal square array. From a practical design point of view, fluid-elastic instability may be expressed simply in terms of dimensionless flow velocity and dimensionless mass-damping parameter. For dynamic instability of cylinder rows, added mass, damping and the threshold flow velocity are evaluated. The Fluid-elastic instability coefficient is calculated and then compared to existing results given for tube bundles in normal square array.

Pressure Distribution over Tube Surfaces of Tube Bundle Subjected to Two-Phase Cross-Flow (이상 유동에 놓인 관군의 표면에 작용하는 압력 분포)

  • Sim, Woo Gun
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.37 no.1
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    • pp.9-18
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    • 2013
  • Two-phase vapor-liquid flows exist in many shell and tube heat exchangers such as condensers, evaporators, and nuclear steam generators. To understand the fluid dynamic forces acting on a structure subjected to a two-phase flow, it is essential to obtain detailed information about the characteristics of a two-phase flow. The characteristics of a two-phase flow and the flow parameters were introduced, and then, an experiment was performed to evaluate the pressure loss in the tube bundles and the fluid-dynamic force acting on the cylinder owing to the pressure distribution. A two-phase flow was pre-mixed at the entrance of the test section, and the experiments were undertaken using a normal triangular array of cylinders subjected to a two-phase cross-flow. The pressure loss along the flow direction in the tube bundles was measured to calculate the two-phase friction multiplier, and the multiplier was compared with the analytical value. Furthermore, the circular distributions of the pressure on the cylinders were measured. Based on the distribution and the fundamental theory of two-phase flow, the effects of the void fraction and mass flux per unit area on the pressure coefficient and the drag coefficient were evaluated. The drag coefficient was calculated by integrating the measured pressure on the tube by a numerical method. It was found that for low mass fluxes, the measured two-phase friction multipliers agree well with the analytical results, and good agreement for the effect of the void fraction on the drag coefficients, as calculated by the measured pressure distributions, is shown qualitatively, as compared to the existing experimental results.

Cross Flow Characteristics of the Core Simulator in SMART Reactor Flow Distribution Test Facility (SMART 유동분포시험장치 노심모의기에서의 횡방향 유동 특성)

  • Yoon, Jung;Kim, Young-In;Chung, Young-Jong;Lee, Won-Jae
    • The KSFM Journal of Fluid Machinery
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    • v.15 no.4
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    • pp.5-11
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    • 2012
  • To identify the flow characteristics of the SMART reactor, a flow distribution model test and a numerical simulation are performed in KAERI. Among several part of the SMART reactor, the fuel assemblies are simulated using simulators because of the complexity. The geometries of the core in the SMART reactor and simulator are different, but some similarities are maintained such as the ratio of pressure drop in the vertical and cross directions. There are cross flow holes in each core simulator to reproduce the cross flow of SMART fuel assemblies. To know the flow characteristics of the cross flow, numerical analysis is performed. As the cross flow area is decreased, the pressure drop between inlet and outlet is decreased. Also, when the flow imbalance between two core simulators is constant, the cross flow area does not significantly affect the cross flow.

2차 유동 분사에 의한 추력 방향 제어(TVC)에 관한 2차원 및 3차원 유동해석

  • 오대환;구상모;손창현;이중원
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 1999.04a
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    • pp.15-15
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    • 1999
  • 2차 유동 분사에 의한 추력 방향 제어 방법은 복잡한 기계적 작동장치와 이에 따른 무게의 증가를 배제할 수 있다. 본 연구에서는 유동 해석을 통하여 2차원 및 3차원 초음속 수축-팽창 노즐 유동에 2차 유동을 분사하여, 2차 유동의 분사 위치, 분사 유량 및 분사 각도 등이 추력의 방향 및 크기에 미치는 영향을 밝혀 추력 방향 제어를 위한 최적의 2차 분사 조건을 제시하였다. 유동 해석 결과 2차 유동의 분사 위치는 생성된 경가 충격파가 노즐 출구까지 분포되는 지점이 최대 전향각과 횡추력을 가지는 분사위치임을 알 수 있었고, 분사 각도는 주 유동의 역방향으로 분사하는 것이 수직방향으로 분사하는 것보다 더 큰 전향각을 얻을 수 있었다. 또한 2차원의 경우보다 3차원 유동에서 큰 전향각이 생김을 알 수 있었다.

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2차 유동 분사에 의한 추력 방향 제어(TVC)에 관한 유동해석

  • 손창현;오대환;이충원
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 1998.10a
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    • pp.33-33
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    • 1998
  • 2차 유동 분사에 의한 추력 방향 제어 방법은 기존의 기계적인 장치를 이용한 방향제어 방법에 비해 부가적인 복잡한 기계적 작동장치와 이에 따른 무게의 증가를 배제할 수 있다. 본 연구에서는 전산 유동해석을 이용하여 2차원 초음속 수축-행창 노즐 유동에 2차 유동을 분사하여, 2차 유동의 분사우치 및 분사 유량 및 분사 각도 등이 추력의 방향 및 크기에 미치는 영향을 밝혀 이들 상호간의 상관관계를 구하여 추력 방향 제어를 위한 최적의 2차 분사 조건을 제시하였다. 유동 해석 견과 2차 유동의 분사 위치는 생성된 경사 충격파가 노즐 출구까지 분포되는 지점이 최대 전향각과 횡추력을 가지는 분사 위치임을 알 수 있었다

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자유면 사질대수층에서의 분산지수 결정

  • 조규혁;김동주
    • Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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    • 2001.09a
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    • pp.239-243
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    • 2001
  • 대수층에서 오염물질의 이동은 대류, 확산, 흡착 등의 물리화학적 현상에 영향을 받는다. 지하수 유동과 오염 물질 운송에 관련된 분석은 지하수 자원의 관리와 평가, 복원사업에 필요한 요소이다. 본 연구의 목적은 사질대수층에서의 2차원 plume 모니터링을 통하여 오염운의 관측치와 모사치를 비교하므로써 종분산지수와 종/횡분산지수비를 결정하는 것이다. 실내 자유면 대수층 실험에서 MT3D를 이용한 case study로부터 추정된 종분산지수는 0.4 cm였으며 횡/종분산지수비는 1/5로 나타났다.

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