• Title/Summary/Keyword: Fluidelastic Instability

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Vibration Characteristics of Steam Generator U-tubes with Defect (결함을 가진 증기발생기 U-튜브의 진동특성)

  • 조종철;정명조;김웅식;김효정;김태형
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.13 no.5
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    • pp.400-408
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    • 2003
  • This paper investigates the vibration characteristics of steam generator (SG) U-tubes with defect. The operating SG shell-side flow field conditions for determining the fluidelastic instability parameters such as added mass are obtained from three-dimensional SG flow calculation. Modal analyses are performed for the U-tubes either with axial or circumferential flaw with different sizes. Special emphases are on the effects of flaw orientation and size on the modal and instability characteristics of tubes, which are expressed in terms of the natural frequency, corresponding mode shape and stability ratio. Also, addressed is the effect of the internal pressure on the vibration characteristics of the tube.

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.

Vibration Characteristics of Heat Exchanger Tube Bundles in Two-Phase Cross-Flow (2상 횡유동을 받는 열교환기 관군의 진동특성)

  • 김범식;박태철
    • Journal of KSNVE
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    • v.4 no.2
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    • pp.199-208
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    • 1994
  • Two-phase cross-flow exists in many shell-tube heat exchangers such as nuclear steam generators, condensers and reboilers. An understanding of damping and of flow-induced vibration excitation mechanisms in necessary to avoid problems due to excessive tube vibration. In this paper, we present the results of experiments on normal-triangular tube bundles of pitch to tube diameter ratio, p/d, 1.22, 1.32 and 1.47. The bundle were subjected to air-water mixtures to simulate realistic mass fluxes and vapour qualities corresponding to void fractions from 5 to 99%. Damping, fluidelastic instability and turbulence- induced excitation are discussed. The behaivior of damping and two vibration mechanisms are different for intermittent flows from for bubbly flows. The effect of pitch to tube diameter ratio and void fraction is dominant on damping and fluidelastic instability.

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The effects of tube bundle geometry on vibration in two-phase cross-flow (2상 횡유동에서 열교환기 관군 배치에 다른 진동특성 고찰)

  • 김범식
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2001.05a
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    • pp.681-687
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    • 2001
  • Two-phase cross-flow exists in many shell-tube heat exchangers such as steam generators, condensers and reboilers. An understanding of flow-induced vibration excitation mechanism is necessary to avoid problems due to excessive tube vibration. This paper presents the results of a series of experiments done on tube bundles of different geometries subjected to two-phase cross-flow simulated by air-water mixtures. Normal(30$^{\circ}$) and rotated (60$^{\circ}$)triangular, and normal(90$^{\circ}$) and rotated (45$^{\circ}$) square tube bundle configurations of pitch-to-diameter ratio of 1.2 to 1.5 were tested over a range of mass fluxes from 0 to 1,000kg/$m^2$ㆍ s and void fraction from 0 to 100%. The effects of tube bundle geometry on vibration excitation mechanism such as fluidelastic instability and random turbulence, and on dynamic parameters such as damping and hydrodynamic mass are discussed. A lower pitch-to-diameter results in a higher hydrodynamic mass. The effect of tube bundle configurations on damping and random turbulence excitation is minor. The effect of pitch-to-diameter on the fluidelastic instability, however, is significant.

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Fluidelastic Instability Analysis of the U-Tube Bundle of a Recirculating Type Steam Generator (재순환식 증기발생기 U-튜브군에 대한 유체탄성 불안정 해석)

  • 조종철;이상균;김웅식;신원기;은영수
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.17 no.1
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    • pp.200-214
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    • 1993
  • This paper presents the results of fluidelastic instability analysis performed for the U-tube bundle of a Westinghouse model 51 steam generator, one of the recirculating types designed at an early stage, in which the principal region of external cross-flow is associated with the U-bend portion of tube. The prerequisites for this analysis are detailed informations of the secondary side flow conditions in the steam generator and the free vibration behaviours of the U-tubes. In this study, the three-dimensional two-phase flow field in the steam generator has been calculated employing the ATHOS3 steam generator two-phase flow code and the ANSYS engineering analysis code has been used to calculate the free vibration responses of specific U tubes under consideration. The assessment of the potential instability for the suspect U-tubes, which is the final analysis process of the present work, has been accomplished by combining the secondary side velocity and density distributions obtained from the ATHOS3 prediction with the relative modal displacement and natural frequency data calculated using the ANSYS code. The damping of tubes in two-phase flow has been deduced from the existing experimental data by taking into account the secondary side void fraction effect. In operation of the steam generator, the tube support conditions at the tube-to-tube support plate intersections due to either tube denting degradation or deposition of tube support plate corrosion products or ingression of dregs. Thus, various hypothetical cases regarding the tube support conditions at the tube-to-tube support plate intersections have been considered to investigate the clamped support effects on the forced vibration response of the tube. Also, the effect of anti-vibration bars support in the curved portion of tube has been examined.

A Study on the Flow=Induced Vibration of Tube Array in Uniform Crossflow(II) On the Flow-Induced Vibration of Two Interfering Circular Cylinders in Tandem (균일 유동장내 튜브배열의 유동관련 진동에 관한 연구( II ) 직렬로 배열된 두 원주의 유동여기 진동에 관하여)

  • 이기백;김봉환;양장식
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.17 no.6
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    • pp.1518-1528
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    • 1993
  • The wake-induced vibration and proximity-induced vibration of two interfering circular cylinders in tandem are investigated experimentally, using an elastically supported cylinder and a fixed cylinder in uniform crossflow. Dynamic responses and flow periodicity in wake are measured to investigate the effect of system parameters on aerodynamic instability. The parameters include the free stream wind velocity and the position of two interfering circular cylinders. The oscillating behavior of the amplitude of the elastically supported cylinder is changed by varying the position, the relative gap spacing between two interfering circular cylinders and the reduced velocities. In small gap spacing between the elastically supported cylinder located to upstream and the circular cylinder fixed to downstream, the fluidelastic instability is founded. The vibration amplitude decreases notably as gap spacing between two interfering circular cylinders becomes large. The dynamic behavior at g/D-4.0 is similar to that of the single circular cylinder.

Study on the Fluid-elastic Instability and Turbulence Excitation for the Steam Generator Tube (증기발생기 전열관의 유체탄성불안정성 및 난류가진 특성 연구)

  • 유기완;박치용;박수기;이종호
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2001.11b
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    • pp.1400-1405
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    • 2001
  • In this study, an analysis program to assess the susceptibility of steam generator tubes due to the flow-induced vibration was developed. Analysis of fluid-elastic instability and random turbulence excitation for the U-tube bundle in CE-type steam generator was accomplished. The effective mass distribution along the U-tube was obtained to calculate the natural frequency and dynamic mode shape. Finally, stability ratios and rms vibration amplitude for selected tubes are obtained.

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유동유발진동에 의한 제어봉 Fretting Wear의 열수력학적 원인 분석

  • Kim, Sang-Nyeong;Shin, Cheol
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.489-495
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    • 1998
  • 최근 울진 1,2호기의 급정지 제어봉 E.C.T(Eddy Current Test) 결과 Fretting Wear가 심한 것이 관찰되었다. 이는 유동유발 진동에 의해 제어봉과 그 지지물 간의 접촉으로 인한 손상이 주요인으로 추정되고 있다. 제어봉 손상은 제어봉 교체로 인한 비용뿐만 아니라 마모금속의 방사화로 인한 냉각재의 오염을 수반한다. 따라서 본 연구는 원자로의 유동유발진동을 선별하여 파손 위치 및 형태, 유동조건, 제어봉과 안내관의 기하학적 구조 등을 분석한 결과 지배적인 손상원인을 Turbulence Excitation과 Fluidelastic Instability로 선정하였다. 특히 안내관내의 6번째 card 위치에서 발생하는 높은 마모현상이 난류도 증가에 의한 손상임을 제시하였다

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Jet-Flow-Induced Vibration of Tube Arrays (제트유동에 의한 튜우브 집합체의 진동 연구)

  • Lee, Hae;Chang, Young-Bae
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.10 no.1
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    • pp.1-6
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    • 1986
  • This paper presents a study on jet-flow-induced vibration, which has been one of the main causes of fuel damage in many pressurized water reactors. A systematic investigation was carried out experimently to identify the mechanism of jet-flow-induced vibration and to provide a design guide. Fluidelastic instability occurs when the jet velocity exceeds a critical value. The threshold of instability is given by V/f$_{n}$D=K.root.(D/h)(m$_{0}$.delta.$_{0}$/.sigma.D$^{2}$), where K is a stability constant. The effect of axial flow velocity and stand-off distance of a tube array on the stability of the array were investigated. A design guide is proposed.posed.