• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2005년도 동계학술발표대회 논문집
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• pp.486-491
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• 2005

Nowadays heat exchangers that have been applied for freon refrigerating systems, a shell and tube type condenser, but because of their large size, large space for installation and more amount of refrigerants are needed. Therefore, in this study, we will find the most suitable operating condition through the comparison of performance between the shell & tube type and shell & disk type heat exchanger with R22. The experiments are carried out for the condensing pressure of refrigeration system from 1500kPa to 1600kPa and for the degree of superheat from 0 to $1^{\circ}C$ at each condensing pressure. As a result of experiment, if the shell & disk type heat exchanger is applied for R22 refrigerating systems, minimized input of refrigerants and space required for installation will be secured, which will have a great contribute to financial improvement for industry.

• 대한기계학회논문집B
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• 제39권3호
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• pp.223-229
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• 2015

배플과 관군간의 누설유동이 쉘-관 열교환기 성능에 미치는 영향을 FLUENT 를 사용하여 조사하였다. 쉘측 출구온도를 최대로 하는 최적누설유동을 찾기 위해 쉘측 단면적에 대한 누설단면적 비가 0%-40% 범위의 5 가지 누설유동을 가진 쉘-관 열교환기에 대하여 CFD 모델이 개발되었다. 관 입구 및 벽면온도를 일정하게 유지하고 Reynolds 수를 4952 부터 14858 증가시키면서 유동장 및 온도장을 계산하였다. 해석결과, 출구온도, 압력강하, 열전달률은 Reynolds 수뿐만 아니라 누설유동에도 크게 영향을 받는 것으로 나타났다. 누설유동은 열전달률과 압력강하를 동시에 낮추는 결과를 제시한 기존의 결과와는 달리, 본 연구에서는 적정의 누설유동은 배플 주위의 재순환영역에 추가적인 모멘텀을 공급함으로써 최대출구온도, 작은 압력강하, 높은 열전달률을 유도하는 효과를 발휘하는 새로운 결과를 얻었다. 20%의 누설단면적이 최적의 누설단면적으로 나타났다.

• Journal of Advanced Marine Engineering and Technology
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• 제40권5호
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• pp.403-411
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• 2016

Usually shell and tube heat exchangers are employed to recover energy between fluids. Recently, numerous papers on these heat exchangers have been published; however, the velocity and temperature profiles or comparison of the features of the flow with or without inside tubes have rarely been described. In this research, experimental and numerical studies were carried out to investigate the characteristics of the flow around the spiral baffle plates without inside tubes in a horizontal circular tube using a particle image velocimetry method and ANSYS 14.0~15.0 version (Fluent). The results showed that swirling flow was produced between the spiral baffle plates. The tangential components were strong between the two spiral baffles; however, the axial or radial velocities components were indicating nearly zero. From the spiral motion in the space of the two baffles, it is considered that there were no dead zones between the spiral baffle.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.78-84
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• 2016

The FHX (Forced-draft sodium-to-air Heat Exchanger) employed in the ADHRS (active decay heat removal system) is a shell-and-tube type counter-current flow heat exchanger with M-shape finned-tube arrangement. Liquid sodium flows inside the heat transfer tubes and atmospheric air flows over the finned tubes. The unit is placed in the upper region of the reactor building and has function of dumping the system heat load into the final heat sink, i.e., the atmosphere. Heat is transmitted from the primary cold sodium pool into the ADHRS sodium loop via DHX (decay heat exchanger), and a direct heat exchange occurs between the tube-side sodium and the shell-side air through the FHX tube wall. This paper describes the DHRS and the structural design of the FHX.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.257-264
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• 2024

The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, which is the sodium-water reaction. Since sodium and water are separated only by a heat transfer tube with a thickness of only a few mm, there is inherently a risk of a sodium-water reaction (SWR) accident in the SFR. In this study, it is attempted to quantitatively evaluate the resistance of SWR accidents by replacing the shell and tube steam generator with printed circuit steam generator (PCSG) as a method to mitigate the SWR accident. To do this, a CATS-S (Compact Accident Tolerance Steam Generator-SWR) facility was designed and built. And for the quantitative evaluation of accident resistance, a methodology for measuring the impingement wastage rate was established. As a result of this research, the impingement wastage rate caused by SWR generated in a PCSG was measured first time. It was confirmed that the impingement wastage phenomenon was suppressed in the PCSG, and the accident resistance was higher than that of the SWR through comparison with the experimental results performed in the existing shell and tube steam generator. In conclusion, a PCSG is more resistant to impingement wastage as a result of the SWR accident than existing shell and tube steam generators, and it is estimated that a PCSG can mitigate SWR accidents, an inherent problem of SFR.

• 한국태양에너지학회 논문집
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• 제24권1호
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• pp.47-52
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• 2004

An experimental investigation was performed to compare ice making characteristics of ice storage system with smooth and spiral tube. During the freezing processes in the shell and tube type ice storage tank with smooth tube, heat resistance of the ice layer caused a decrease in freezing rate. Also, the phenomena of bridging made the increasing rate of ice making less. In order to improve the ice making rate, spiral tube(pitch=6mm) was used in the present study. The ice making rate and the decreasing of bridging for the spiral tube were higher than those for the smooth tube.

• 대한기계학회논문집
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• 제14권1호
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• pp.251-258
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• 1990

본 연구에서는 제 1보에서 다루었던 프로세스 해석의 결과들을 토대로 하여 열교환기의 최적 설계를 행하는데 주력하였다. 먼저, 열교환기의 최적 설계를 행하 는데 주력하였다. 먼저, 열교환기의 열설계에 필요한 CO$_{2}$와 Natrium의 물성치 및 열전달에 관한 기존의 실험식들을 여러문헌으로부터 연구 검토한 후 프로그램에 편 리하게 이용할 수 있도록 전산화 하였으며, 열교환기의 설계시 필요한 전체 경비의 최 소화를 기하는 방향으로 최적화된 설계인자들을 결정하도록 시도하였고 또한 최적화된 프로그램을 개발함으로써 인력, 외화 및 에너지 절감의 효과를 얻고자 하였다.

• Korean Chemical Engineering Research
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• 제46권5호
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• pp.931-937
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• 2008

공정변수의 변화와 반응기의 성능을 정확하게 예측하기 위하여 Water Gas Shift Reaction(WGSR)을 위한 Multi-Tubular Reactor (MTR)의 상세 multiscale 모델링과 모사를 수행하였다. MTR은 비 균일 고체 촉매로 충진 된 4개의 관형반응기와 냉각을 위해 주변을 싸고 있는 shell side로 구성되어 있다. 유체의 흐름과 반응 kinetics가 반응기 성능에 큰 영향을 주고 있는 점을 고려할 때, Computational Fluid Dynamics (CFD)기법과 공정모델링 기법을 포함한 multiscale 방법론의 채택은 자연스럽고 필수 불가결한 일이다. $345^{\circ}C$로 관형반응기 부분으로 유입된 반응물은 반응의 결과 $390^{\circ}C$로 $45^{\circ}C$가량 온도가 증가하였으며, CO의 전환율은 0.89에 이르렀다. 쉘 사이드로 $190^{\circ}C$로 유입된 유체는 쉘 출구에서 $240^{\circ}C$로 약 $50^{\circ}C$ 가량의 온도 증가를 보였으며 이를 통하여 에너지 절감효과를 가져 올 수 있었으며 높은 전환율을 얻기 위해 반응기 부분의 온도를 적절히 제어할 수 있었다. 모사의 결과는 여러 문헌에 보고된 실험 결과와 매우 근접한 값을 나타내 본 연구를 통해 제시된 모델과 모사의 결과가 정확함을 알 수 있었다.

• 한국압력기기공학회 논문집
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• 제11권1호
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• pp.1-11
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• 2015

Feedwater Heaters are important components in a nuclear power plant. As the age of heater increases, the maintenance cost required for continuous operation also increases. Most heaters have the carbon steel shells, tube support plates and flow baffles. The carbon steel is susceptible to flow-accelerated corrosion. This is especially true if the flow has a two-phase mixture of steam and condensate. The wall thinning around the wet steam entrance area of the shell is inevitable during some long term operation. The structural integrity of the feedwater heater shell affects the safe operation of the nuclear power plant. Therefore, it is needed for the thinned shell to be repaired. The maintenance method for preventing failure of the shell should be determined by investigating various factors including the stress distribution of thinned area. The stress analysis of the shell including the steam entrance region is studied in this paper. The results of thinned shell is compared with that of intact shell.

• 소음진동
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• 제4권2호
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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.