• Transactions of the Korean Society of Mechanical Engineers B
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• v.24 no.6
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• pp.886-893
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• 2000

The Characteristics of dividing the dispersed bubble, plug, and slug steam-water flow in the horizontal junctions with horizontal branches have been experimentally investigated. The experimental investigation of the separation phenomena in a $45^{\circ}$ horizontal wye with equal pipe inner diameter of 25 mm is presented to provide a data base for the development and verification of the analytical models. The phase separation and pressure distribution in the three legs of each test section are obtained through the set of measurements made in the present work. And the dependence of phase separation on different parameters, such as inlet quality and mass flux, is discussed.

• Proceedings of the KSME Conference
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• 2003.11a
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• pp.1180-1185
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• 2003

One of the main degradation of steam generator tubes is stress corrosion cracking induced by residual stress. The resulting damages can cause tube bursting or leakage of the primary water which contained radioactivity. Primary water stress corrosion crack occurs at the location of tube/tubesheet hard rolled transition zone. In order to investigate the effect of shot peening on stress corrosion cracking, stress intensity factors are calculated for the crack which is located in the induced residual stress field.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.11 no.1
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• pp.25-32
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• 2015

Many crack flaws have been detected at tubing seal weld zone in Steam Generator with Alloy600 material tubes. it is very difficult to discriminate the signal from parent material and that from weld zone because weld zone gives complicated ECT signal due to manufacturing processes. ECT signal analysis in the seal weld zone is very important since the tubes with crack in this area shall be out of service by plugging. The purpose of this paper is to distinguish between Parent material and Weld Zone ECT signal in the seal weld zone through the demonstration test of Steam Generator seal weld mock-up.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.741-746
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• 1995

일체형원자로는 노심, 증기발생기, 가압기, 펌프 등 1차측 주기기들을 하나의 압력용기 안에 모두 포함하고 있고 또 1차측 냉각재가 원자로 안에서만 순환하므로 기존의 분리 형에 비해 구조특성상 상당히 다른 설계개념이 필요하다. 본 연구에서 개발중에 있는 일체형 열병합원자로에서 채택한 설계개념은, 먼저 증기발생기는 많은 수의 전열관들이 나사선처럼 노심지지원통을 감고 올라가는 일체형 관류식 나선형을 사용하였으며, CEDM은 지진하중과 같은 동적하중에 의한 영향을 최소화하기 위하여 원자로용기 외부로의 돌출부분을 최소화하는 설계개념을 채택하였다. 또한 가압기는 별도의 부품없이 원자로용기 헤드의 빈공간을 활용한 자기가압방식으로 대체하였고 냉각재 펑프는 Canned Motor Pump를 원자로벽에 직접 부착하는 개념을 사용하였다. 본 논문에서는 예비개념설계된 일체형 신형원자로의 기계구조설계상의 특징들을 설명하고 앞으로의 연구방향을 간략히 소개한다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2003.05a
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• pp.670-676
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• 2003

To investigate the group plugging effect the fluid-elastic instability analysis has been performed on various column and row number of the KSNP steam generator lutes. This study compares the stability ratio of the plugged tube with that of the intact one. The information on the thermal-hydraulic data of the steam generator have been obtained by using the ATHOS3-MOD1 code with and without the thermal energy transfer at the plugged region. Both of the boundary conditions of hot-leg temperature and feedwater mass flow rate are fixed for this investigation. From the results of this study the stability ratios inside the group plugging zone are decreased slightly. At the outside of group plugging zone, however, most of the stability ratios tend to be increased.

• Journal of Advanced Marine Engineering and Technology
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• v.18 no.4
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• pp.13-24
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• 1994

The demand of clean energy, like liquefied gas(LNG), increase suddenly because it generates few polluting substances when burned and from the point of view with caloric value it generates ralatively less $CO_2$ gas than the other energy sources. LNG transpotion method of our country is marine transportion by ships because the LNG producing district is far away from Korea. Main engines for most LNG ships are steam turbines, and the efficiency of steam turbine is influenced by the degree of vacuum of main steam condenser. This paper introduce the design method of the vacuum system for high efficiency marine steam turbine. Especially, it is developed the CAD program for the large steam condenser and steam ejector. Also, it is designed the pilot plant including high pressure boiler for the performance test and maked a part of this plant.

• Proceedings of the KSME Conference
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• 2000.04a
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• pp.19-24
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• 2000

Stress corrosion crack growth is simulated after assuming a small axial surface crack inside a S/G tube. Internal pressure and residual stresses are considered as applied forces. Stress intensity factors along crack front, variation of crack shape and crack growth rate are obtained and discussed. It is noticed that the aspect ratio of the crack is not depend on the initial crack shape but depend on the residual stress distribution.

• 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.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.549-554
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• 1997

원자력발전소 중기발생기 전열관 sleeve의 레이저 보수용접은 원자로 외부의 레이저 광원을 sleeve 내부의 용접 head까지 광섬유로 수백 미터를 전송하여 수행된다. 전열관 레이저용접은 용접 중의 레이저출력, 레이저 전송 광학계의 파손여부, 광학계의 정렬상태 등을 정확히 감시하여 수행하여야 하지만, 작업공간의 협소함과 방사능 구역이라는 어려움 때문에 실시간 감시가 쉽지 않다. 본 연구에서는 광섬유 전송 광학계와 지시용 레이저를 이용하여, 광섬유의 끝단에서 반사된 레이저 빔을 이용하여 광섬유 상태를 실시간 감시할 수 있음을 실험적으로 확인하였다. 실험은 core 직경 800um 의 step index 레이저 전송용 광섬유를 사용하였으며, 광섬유 끝단에 물등의 불순물이 있을 경우와 광섬유가 파손되었을 경우의 감시결과를 얻어, 광섬유 광학계의 실시간 감시가 가능함을 보였다.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.5
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• pp.513-522
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• 2013

In the present work, a numerical study of a horizontal falling film evaporator in a multi-effect distillation (MED) plant is performed. Tube bundles in the evaporator are described as porous media, and a volume-averaged method is applied. To calculate the fluid flow and phase change in the evaporator due to heat transfer in the system, FLUENT and user-defined functions (UDF) are used. To observe the performance of the evaporator under different operational conditions, tests are conducted for a steam mass flux ranging from 0.5 to 2.5 $kg/m^2s$ in the horizontal tube, for mass fraction of the noncondensable gas in the tube inlet ranging from 0% to 1%, and for film Reynolds numbers ranging from 100 to 1,000 for the falling film. The evaporation rate increases with the steam mass flux and Reynolds number. In contrast, the evaporation rate decreases by 0.87% with a 1% increase in the mass fraction of the noncondensable gas in the tube.