• 제목/요약/키워드: flow tubes

검색결과 643건 처리시간 0.023초

평행관 모델링을 통한 보일러 화로벽관 내 밀도파 불안정의 해석 (Analysis of Density Wave Oscillation in Boiler Furnace Wall Tubes with Parallel Channel Modeling)

  • 김진일;최상민
    • 대한기계학회논문집B
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    • 제37권2호
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    • pp.187-196
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    • 2013
  • 화력발전용 관류보일러 화로벽관에서의 밀도파 불안정 예측을 목적으로 수치모델을 개발하였다. 시간 도메인에서 1 차원 유한체적법을 적용하여 관내 비정상상태의 유동장을 계산하였으며, 화로벽관의 평행관 연결을 모사하기 위해 헤더의 모델도 포함하였다. 평행관들 가운데 하나의 관에 열 섭동을 부가 후 관 입출구 유량의 변동을 관찰함으로써 밀도파 불안정을 찾았다. 개발된 모델은 문헌의 실험결과와 검증을 거쳐 700MW 보일러 화로벽관에 적용하였다. 그 결과 Takitani 의 실험결과에서는 평행으로 연결된 우회 유량이 줄어들수록 불안정 경계 열량이 상승하는 경향이 있었던 반면, 보일러 화로벽관의 경우에는 평행관 모델링에 크게 영향을 받지 않음을 확인하였다.

평활관 및 미세휜관 내에서의 물을 이용한 열전달 및 압력강하 특성에 관한 실험 (Experimental study of heat transfer and pressure drop characteristics for flow of water inside circular smooth and micro-fin tubes)

  • 박혁범;유승문;윤백;유국철
    • 설비공학논문집
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    • 제9권4호
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    • pp.454-461
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    • 1997
  • Heat transfer and pressure drop for single phase flow of water in circular smooth and micro-fin tubes are measured. Copper tubes of 9.52 and 7mm outer diameter were used. The internal roughness in micro-fin tubes was formed by spiral grooves having $25^{\circ}$ helx angle, 0. 12mm fin height and 0.454mm pitch in 9.52mm tubes; $18^{\circ}$ helix angle, 0.15mm fin height and 0.322mm pitch in 7mm tubes. The measured friction factor and heat transfer coefficient are compared with relevant previous works, and the correlations for micro-fin tube are developed.

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두 평행한 관의 출구로부터 방출되는 펄스파에 관한 연구 (A Study of the Impulse Wave Discharged from the Exit of Two Parallel Tubes)

  • 권용훈;김희동;이동훈
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2002년도 학술대회지
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    • pp.151-154
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    • 2002
  • The twin impulse wave leads to very complicated flow fields, such as Mach stem, spherical waves, and vortex ring. The twin impulse wave discharged from the exits of the two tubes placed in parallel is investigated to understand detailed flow physics associated with the twin impulse wave, compared with those in a single impulse wave. In the current study, the merging phenomena and propagation characteristics of the impulse waves are investigated using a shock tube experiment and by numerical computations. The Harten-Yee's total variation diminishing (TVD) scheme is used to solve the unsteady, two-dimensional, compressible, Euler equations. The Mach number $M_{s}$, of incident shock wave is changed below 1.5 and the distance between two-parallel tubes, L/d, is changed from 1.2 to 4.0. In the shock tube experiment, the twin impulse waves are visualized by a Schlieren optical system for the purpose of validation of computational work. The results obtained show that on the symmetric axis between two parallel tubes, the peak pressure produced by the twin-impulse waves and its location strongly depend upon the distance between two parallel tubes, L/d and the incident shock Mach number, $M_{s}$. The predicted Schlieren images represent the measured twin-impulse wave with a good accuracy.

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작은 수직관을 흐르는 기-액 슬러그 유동의 유동특성 (Flow Characteristics of a Gas-Liquid Slug Flow in Small Vertical Tubes)

  • 계석현;김동선
    • 설비공학논문집
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    • 제25권5호
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    • pp.246-254
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    • 2013
  • Some characteristics of nitrogen-water slug flow were optically measured, in vertical acrylic tubes of 2, 5 and 8 mm diameter. Bubble velocity, bubble and unit cell lengths were measured, by analyzing the light intensity signals from two sets of dot laser-infrared sensor modules mounted along the transparent tubes. Optical images of the bubbles were also taken and analyzed, to measure bubble shapes and liquid film thickness. It was found that the measured bubble velocities were in good agreement with the empirical models in the literature, except for those measured under high superficial velocity condition in the 2 mm tube. Bubble length was found to be the longest in the 2 mm tube, being 4 to 5 times those of the other tubes. Liquid film was found to have developed early in the 2 mm tube, which made the blunt shape of the bubble head. Liquid film thickness in the 8 mm tube was measured at almost twice those of the other tubes.

분기관내 뉴턴유체와 혈액의 맥동유동특성에 관한 연구 (A study on the pulsatile flow characteristics of Newtonian and non-Newtonian fluids in the bifurcated tubes)

  • 서상호;유상신김영호노형운
    • 대한기계학회논문집B
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    • 제20권11호
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    • pp.3607-3619
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    • 1996
  • Experimental and numerical studies for three-dimensional pulsatile flows are conducted to investigate the flow characteristics in the bifurcated tubes. Velocity measurements in experimental study were made by both Pulsed Doppler Ultrasound(PDU) machine and Laser Doppler Anemometer(LDA) system. Glycerin is used for experimental study. Experimental results are used to verify the results of the numerical simulation. Flow characteristics of Newtonian fluid and blood in the bifurcated tubes under the steady and pulsatlie flows are numerically investigated. Finite volume method is employed for three-dimensional numerical simulations. Blood is considered as a non-Newtonian fluid and the constitutive equation of blood is used for the numerical analysis. Numerical analyses are focused on the flow patterns for various branch angles ranging from 30.deg. to 90.deg. and diameter ratios such as 1.0, 0.8, and 0.6. Pulsatile flow characteristics of blood are compared with those of Newtonian fluid. Parameter effects on axial velocity, pressure and wall shear stress distribution along the bifurcated tubes are discussed in terms of the branch angle, diameter ratio, and Reynolds number.

이상 유동 환경이 증기 발생기 세관과 지지대의 프레팅 마모에 미치는 영향에 대한 연구 (The Influence of Two Phase Flow on Fretting Wear between Steam Generator Tube and Supporting Bar)

  • 이영제;박정민;정성훈;김진선;박세민
    • Tribology and Lubricants
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    • 제24권6호
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    • pp.362-367
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    • 2008
  • Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube-support. The fretting wear of tube-support can threaten the safety of nuclear power plant. The tube and support materials were Inconel 690 and STS 409. The wear tests were conducted in various environments, which are in water without flow, in flowing water and in flowing water with air. The results showed that the flow of water influenced on the wear-life of tube. The wear-life of tube decreased in water flow as compared with wear-life in stationary water.

Investigation on reverse flow characteristics in U-tubes under two-phase natural circulation

  • Chu, Xi;Li, Mingrui;Chen, Wenzhen;Hao, Jianli
    • Nuclear Engineering and Technology
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    • 제52권5호
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    • pp.889-896
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    • 2020
  • The vertically inverted U-tube steam generator (UTSG) is widely used in the pressurized water reactor (PWR). The reverse flow behavior generally exists in some U-tubes of a steam generator (SG) under both single- and two-phase natural circulations (NCs). The behavior increases the flow resistance in the primary loop and reduces the heat transfer in the SG. As a consequence, the NC ability as well as the inherent safety of nuclear reactors is faced with severe challenges. The theoretical models for calculating single- and two-phase flow pressure drops in U-tubes are developed and validated in this paper. The two-phase reverse flow characteristics in two types of SGs are investigated base on the theoretical models, and the effects of the U-tube height, bending radius, inlet steam quality and primary side pressure on the behavior are analyzed. The conclusions may provide some promising references for SG optimization to reduce the disadvantageous behavior. It is also of significance to improve the NC ability and ensure the PWR safety during some accidents.

원전 습분분리재열기 튜브 번들 교체를 위한 열전달 고찰 (Heat Transfer Study to Replace a Tube Bundle of Moisture Separator Reheater at Nuclear Power Plant)

  • 최유성;최광희;이상국
    • 한국압력기기공학회 논문집
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    • 제6권1호
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    • pp.65-71
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    • 2010
  • The plugging rate of reheater tubes of Wolsung unit 1 nuclear power plant has been increased by corrosion and erosion since 1990. As the dimensions of the new first stage reheater bundle tubes which were supplied by Hanjung company to replace were different from old one, numerical calculations are carried out for flow and heat transfer in the reheater bundle tubes of the N.P.P. Numerical calculations consists of thermal performance, drain line pressure drop, flow change by pressure drop of line, stress analysis of finned tubes and analysis of flow induced vibration. Computational analysis using heat transfer research institute program is adopted to verify the results of the numerical calculations. It contains the evalution of performance in the system with view to location of the new reheater bundle and it shows the differences between the numerical calculation results and heat transfer research institute program output.

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Fretting-Wear Characteristics of Steam Generator Tubes by Foreign Object

  • Jo Jong Chull;Jhung Myung Jo;Kim Woong Sik;Choi Young Hwan;Kim Hho Jung;Kim Tae Hyung
    • Nuclear Engineering and Technology
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    • 제35권5호
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    • pp.442-453
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    • 2003
  • This study investigates the safety assessment of the potential for fretting-wear damages on steam generator (SG) U-tubes caused by foreign object in operating nuclear power plants. The operating SG shell-side flow field conditions are obtained from three-dimensional SG flow calculation using the ATHOS3 code. Modal analyses are performed for the finite element modelings of U-tubes to get the natural frequency, corresponding mode shape and participation factor. The wear rate of U-tube caused by foreign object is calculated using the Archard formula and the remaining life of the tube is predicted. Also, discussed in this study is the effect of the flow velocity and vibration of the tube on the remaining life of the tube.

수정멱법칙 비뉴턴유체의 협착관내 유동장해석 (Flow Analysis of the Modified Power-Law Non-Newtonian Fluids in the Stenotic Tubes)

  • 서상호;유상신;장남일
    • 설비공학논문집
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    • 제6권3호
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    • pp.227-236
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    • 1994
  • Steady flows of Newtonian and non-Newtonian fluids in the stenotic tubes with various stenotic shapes are numerically simulated. Validity of the modified power-law model as a constitutive equation for the purely viscous non-Newtonian fluid is discussed and the results of the power-law model are compared with those of the Carreau model, the Powell-Eyring model and experimental data for blood. Flow characteristics and reattachment lengths for non-Newtonian fluids in the stenotic tubes are presented extensively. Also, the analysis is extended to predict the influences of diameter ratio, stenosis spacing, number of stenosis and Reynolds number on the flow characteristics in the multiple stenotic tubes.

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