• Journal of the Korea Academia-Industrial cooperation Society
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• v.17 no.2
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• pp.712-718
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• 2016

A heat exchanger tube array in a heat recovery steam generator is exposed to hot exhaust gas flow that can cause flow induced vibrations, which could damage the heat exchanger tube array. The characteristics of flow induced vibration in the tube array need to be established for the structural safe operation of a heat exchanger. Several studies of the flow induced vibrations of typical heat exchangers have been conducted and the nondimensional PSD (Power Spectral Density) function with the Strouhal number, fD/U, had been derived using an experimental method. The present study examined the results of the previous experimental research on the nondimensional PSD characteristics by CFD analysis and the basis for the application of flow induced vibration to the heat recovery steam generator tube array was determined from the present CFD analysis. The present CFD analysis introduced circular cylinder tube array and calculated using unsteady laminar flow for the tube array. The characteristics of lift and drag fluctuations over the cylinder tube array was investigated. The derived nondimensional lift and drag PSD was compared with the results of the previous experimental research and the characteristics of lift and drag PSD for a circular cylinder tube array was established from the present CFD study.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.695-700
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• 1995

최근 일부 PWR 원전에서는 냉각수 유동유발에 의한 집합체 진동에 기인한 것으로 보이는 핵연료 손상이 잇달아 발생하고 있다. 본 시험에서는 모의 핵연료 집합체에 대해 원전운전시 유량(유속)에 따른 집합체외 진동특성을 규명하기 위해 모의 집합체에 대한 유동시험을 수행하였다. 시험결과 매져 모의 연료는 발전소 운전 유동영역 범위내에서 냉각수 유동에 기인한 집합체의 진동현상이 발생함이 확인되었다.

• Proceedings of the KSME Conference
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• 2005.11a
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• pp.173.1-173.1
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• 2005

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2007.11a
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• pp.281-286
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• 2007

Needs of fuel's performance evaluation for the dual-cooled fuel pellet (annular shape) necessitate the irradiation test in the test reactor. Irradiation test rig for the HARARO reactor, which is a special-purposed equipment used for material, irradiation and creep test, must satisfy the operational requirement on the hydraulic characteristics and structural integrity. In this paper, pressure drop and flow-induced vibration test for the newly developed non-instrumented test rig were carried out using FIVPET as a out-pile evaluation test. The test results show that the new test rig satisfy the HANARO operational requirement with sufficient margin. The spectral response characteristics of the flow-induced vibration of the test rid were also discussed.

• Journal of KSNVE
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• v.9 no.6
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• pp.1200-1209
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• 1999

This paper reports a peculiar example of flow-induced vibration in a very large plant and the whole procedure of reducing the vibration. During the operation of flue gas desurfurization unit of the thermal power plant, serious vibration was dtected at all around the plant. The worst vibration was recorded on the heat exchanger surface, which weighed 180 tones, as 17.8 m/$s^2$ in vibration amplitude at 34 Hz. To identify the vibration, frequency analysis on the response vibration as well as on the expected excitation forces and the system resonance was executed. This investigation revealed that the cause of the vibration was vortex shedding from the circular pipes in the heat exchanger. Vortices from the pipes excited acoustic resonance in the heat exchanger room, which, in turn, made the structure vibrate. Through inserting the baffles between the pipes, which had an effect of cutting the acoustic wave at resonance frequency, the vibration was eliminated dramatically.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.46-51
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• 1997

최근 경수로 핵연료 손상 원인 중의 하나인 연료봉 마모(Fretting Wear)가 지지격자의 스프링력 저하뿐만 아니라 원자로 냉각재 유동에 기인한 집합체 진동(Self-excited Fuel Assembly Vibration)에 의해 유발될 수 있는 것으로 밝혀져 해외 연료공급자들은 새로운 연료개발시 집합체 유동시험을 수행하여 냉각재 유동에 의한 집합체 진동 여부를 확인하고 있다. 본 연구에서는 경수로 핵연료집합체에 대한 모드해석 및 진동시험으로부터 고유진동수 및 진동모드형태를 구하여 모의 집합체 유동시험 결과와 비교 평가하였고 냉각재 유동에 의해 과도한 집합체 진동이 발생됨을 확인하였으며 가연성흡수봉집합체를 삽입한 경우에 대한 유동시험 결과와도 비교하였다. 또한, 이들 집합체의 진동 변위량과 손상 연료의 마모량 분포의 상관성을 비교 평가하였다.

• Journal of the Korean Institute of Gas
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• v.20 no.2
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• pp.23-29
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• 2016

Heat exchanger tube array in a heat recovery steam generator is exposed to the hot exhaust gas flow and it could cause the flow induced vibration, which could damage the heat exchanger tube array. It is needed for the structural safe operation of the heat exchanger to establish the characteristics of flow induced vibration in the tube array. The researches for the flow induced vibration of typical heat exchangers have been conducted by using single cicular tube or circular tube array and the nondimensional PSD(Power Spectral Density) function with the Strouhal number, fD/U, had been derived by experimental method. From the present study, the basis for the application of flow induced vibration to the heat recovery steam generator tube array would be prepared. For the previous mentioned purpose, the present CFD analysis introduced a single fin tube and calculated with the unsteady laminar flow over the single fin tube. The characteristics of vortex shedding and lift and drag fluctuation over the fin tube was investigated. The derived nondimensional lift PSD was compared with the results of the previous experimental studies and the characteristics of lift and drag PSD over a single fin tube was established from the present CFD study.

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.141.2-141
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• 1999

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.4
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• pp.359-366
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• 2013

This study aims to investigate the characteristics of the flow-induced vibrations of two circular cylinders. The characteristics of the flow-induced vibrations are examined for various flow velocities and spaces between the two cylinders when they are arranged in tandem, staggered, and side-by-side positions. The results are as follows: (i) Seven flow-induced vibration patterns are observed when the two circular cylinders are placed in either tandem, staggered, or side-by-side positions. (ii) The two cylinders induce a vibration because they affect each other. (iii) The easiest way to induce a vibration of the two cylinders is by placing them in the side-by-side position among the three arrangements (tandem, staggered, and side-by-side). (iv) The change in the maximum flow-induced vibration of the two cylinders depends strongly on the fluctuating lift forces of each of them.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 1993.10a
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• pp.35-41
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• 1993

산업사회가 발전함에 따라 거대한 플랜트(plant)를 포함하여, 원자력 발전소 와 로켓트 등과 같이 구조적 안전성과 정확한 성능의 확보가 극히 중요시되 는 설비들이 많이 등장하고 있다. 이들 설비를 구성하고 있는 파이프계 (piping system)는 강성 또는 연성재료 및 각종 valve등으로 구성되어 있기 때문에, 고온 고압 고속의 유체가 파이프 내부를 흐를 때 일으키는 진동현상 및 플랜트의 과도운전 상황에서의 일어나는 수격현상(water hammer 또는 steam hammer)과 이로 기인한 제반 진동문제는 안전성확보 측면에서 많은 관심이 고조되고 있다. 이와 관련되어 유체유발진동에 관한 많은 연구들이 수행되었으며, 파이프계에 장착된 밸브에 대한 연구는 Weaver등에 의하여 실험적, 이론적으로 수행되었다. 그들은 유동방정식에서 비정상 베르누이 방 정식을 사용하여 내부유동방정식을 간략하게 유도하였으나, jet flow에 의한 유체의 운동량변화를 고려하지 않고 해석되어 그 결과에 의문이 제기된다. 그러므로 본 연구에서는 체크밸브(check valve)가 부착된 파이프계에서 일어 나는 유체유발진동 및 안정성에 관한 이론적 연구를 수행하여, 파이프계의 설계에 필요한 파라미터의 영향을 파악하고자 한다. 원자력 발전소와 같이 구조적 안정성이 요구되는 플랜트를 국내 기술로 설계 시공하려는 국내 실 정에서 이로 인한 파이프계에 발생할 수 있는 유체유발진동과 안정성을 예 측할 수 있는 해석이론은 파이프계의 설계 및 운전조건의 선정에 있어서 그 의의가 크다고 할 수 있겠다.