• Journal of the Korea Convergence Society
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• v.13 no.3
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• pp.191-196
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• 2022

Unlike an international combustion engine car, a battery-powered electric vehicle requires an additional heat source for its heating system. A high-voltage coolant heater has the advantages of high efficiency and a wide operating temperature range. In its development, the geometry design of the coolant flow path is essential. This paper presents the thermal flow simulations of a 7kW high-voltage heater with symmetric serpentine flow channels arranged parallelly. The heater performance was evaluated from the simulation results in terms of the pressure and temperature differences and the flow uniformity. The proposed design showed a greater flow resistance and similar heat exchanging capability than the existing parallel serpentine design. It has the advantage of a relatively wide low-temperature surface area, where the control circuit board susceptible to high temperatures can be located.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.5
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• pp.459-465
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• 2013

In the manufacturing process of steel plates, materials at high temperatures above $800^{\circ}C$ are rapidly cooled by using a circular impinging water jet to determine their strength and toughness. In this study, the basic heat and fluid flow is solved by using the existing numerical model for boiling heat transfer. Actually, steel undergoes a phase change from austenite to ferrite or bainite during the cooling process. The phase change induces changes in its thermal properties. Instead of directly solving the phase change and the material cooling together, we solve the heat transfer only by applying the thermal properties that vary with temperature, which is already known from other studies. The effects of the changes in the thermal properties on the cooling of steel and the necessity of calculating the phase change are discussed.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.36 no.12
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• pp.1653-1661
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• 2012

In this study, the pressure drop changes and structural characteristics of a SMART rod bundle under the effect of a coolant were investigated. The turbulence model of the BSL Reynolds stress model was used to model the coolant flow, and a fluid solid interaction simulation was conducted. First, fuel rod vibration analysis was performed to confirm the natural frequency of the fuel rod, which was supported by spacer grid assemblies, and this was compared with experimental results. From the experimental results, the natural frequency was found to be 48 Hz, and the error compared with the simulation results was 2%. The pressure drop at the rod bundle was calculated and compared with the experimental data; it showed an error of 8%, demonstrating the simulation accuracy. In the flow analysis, the flow velocity and secondary flow at different domains were calculated, and vortex generation was also observed. Finally, through the fluid solid interaction analysis, the fuel rod displacements caused by flow-induced vibrations were calculated. Then, calculated displacement PSD at maximum displacement happed point.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.47 no.2
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• pp.122-129
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• 2019

Predicting heat transfer from the inner wall of the combustion chamber of the liquid rocket is a very difficult task. Several complex processes, such as convection, radiation and conduction must be taken into consideration. Usually commercial programs are used for the analysis of this processes. However, commercial programs are not a perfect solution, because of the long calculation times and a burdening data-input work. In this study, we developed and implemented one - dimensional thermal analysis. This technique can be easily used on the initial stage. The design of the combustion chamber's cooling channel of the steam generator designed using developed technique. In order to compare experimental and theoretical data, the combustion test was performed. Obtained experimental data for the coolant temperature differ from the theoretical prediction by only 8.5%.

• Proceedings of the KSME Conference
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• 2004.11a
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• pp.7-12
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• 2004

A lifetime prediction of holddown spring screw in nuclear fuel assembly was performed using fracture mechanics approach. The spring screw was designed such that it was capable of sustaining the loads imposed by the initial tensile preload and operational loads. In order to investigate the cause of failure and to predict the stress corrosion cracking life of the screw, a stress analysis of the top nozzle spring assembly was done using finite element analysis. The elastic-plastic finite element analysis showed that the local stresses at the critical regions of head-shank fillet and thread root significantly exceeded than the yield strength of the screw material, resulting in local plastic deformation. Normalized stress intensity factors for PWSCC life prediction was proposed. Primary water stress corrosion cracking life of the Inconel 600 screw was predicted by using integration of the Scott model and resulted in 1.78 years, which was fairly close to the actual service life of the holddown spring screw.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.22 no.8
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• pp.1183-1194
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• 1998

This paper describes a theoretical model developed for analyzing the heat transfer of automotive cooling systems. From the model, heat transfer rate of automotive cooling systems can be predicted, providing useful information at the early stages of the design and development. The aim of the study is to develop a simulation program for automotive cooling system analysis and a performance analysis program for analyzing heat exchanger. Heat release rate from combustion gas to coolant through cylinder wall in engine cylinder was analyzed by using a two zone combustion model. This paper studied how cooling condition would affect engine heat release rate and measured temperature distribution of coolant in water jacket.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.557-562
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• 1997

노심용융물의 노내 자연 냉각 현상은 TMI-2 사고 이래로 실험과 해석 분야에서 많은 연구가 이루어지고 있으나, 아직까지는 이에 대한 명확한 규명이 이루어지지 않은 상태이다. 원자로 용기 냉각 Mechanism 중에서 노심용융물이 원자로 용기 하부 반구내로 재배치되어 하부 반구 내벽과 접촉할 때 용융물과 하부 반구 내벽 사이에 생길 수 있는 작은 간극으로 냉각수가 침투되어 노심용융물의 냉각이 이루어질 수 있다는 가정이 유력하게 제기되고 있다 본 논문에서는 노심용융물과 원자로 용기 하부 반구 사이의 간극을 통한 노심용융물의 냉각 특성을 규명하는 SONATA-IV실험 연구와 연계하여 이상 유동이 존재하는 고온 표면에서의 미세한 간극을 측정할 수 있는 방법의 검토 및 시편을 이용한 실험을 통하여 가장 적합한 간극측정기법을 도출하였다 간극 측정 기법으로는 중성자 래디오그라피, X 선 후방산란 단층기법 그리고 초음파 펄스 반사 탐상법을 검토하였으며, 시편 측정 실험결과 실시간 간극 측정방법으로는 초음파 펄스 반사 탐상법이 가장 적합한 것으로 나타났다.

• Nuclear Engineering and Technology
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• v.25 no.2
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• pp.343-352
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• 1993

다목적연구로(KMRR)는 일반 발전용 원자로와는 매우 다른 특성을 가지고 있으며, 설계 개념 또한 특이하다. 위와 같은 특이한 설계 특성을 파악하기 위하여 열수력 실험을 수행하였으며 시운전 시험도 설계 개념의 입증에 중점을 두고 수행될 예정이다. 실증실험은 크게 설계 자료 생산을 위한 실험, 기기 설계 검증 시험, 시운전 성능 시험으로 나눌 수 있다. 설계 자료 생산을 위한 실험으로 핵연료의 열수력학적 특성을 규명하는 실험, 우회 유동에 의한 노심 출구 냉각수 상승 억제를 입증 또는 해석하기 위한 자료 생산용 실험 등이 이루어졌다. 기기 설계 검증 시험으로는 Pump 특성 시험, Flap valve 특성 시험 등을 들 수 있다. 또한, 시운전 성능 시험으로는 설계 개념을 입증하기 위한 여러 시험들이 행해질 예정이다. 이러한 실험들을 통하여 설계에 필요한 많은 자료들이 생산되었고, 시운전 시험을 통하여 설계를 검증하고 실제 운전에 필요한 많은 자료를 얻을 수 있으리라 기대된다. 본 기고를 통하여 이러한 실험의 중요성 및 내용에 대해 간략하게 기술하고자 한다.

• Journal of Advanced Marine Engineering and Technology
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• v.32 no.1
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• pp.119-130
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• 2008

Diesel engine is one of the most expensive and important components in a ship. Many researchers are interested in increasing the performance of diesel engines. Design of an optimum cooling system should also contribute to the enhancement of the performance as well as the efficiency of engines. In this study, we investigated the flow pattern within the cooling system of a marine diesel engine by using numerical simulation prior to the study of the heat-transfer problem. The engine cooling system is composed of five cooling units each unit containing a water-jacket and a cylinder head. Based on the calculated data, we also conducted theoretical analysis that can predict the flow-rate delivery in each of the five units.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.276-282
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• 1996

일체형원자로는 노심, 증기발생기, 가압기, 펌프 등 1차측 주기기들을 하나의 압력용기안에 모두 포함하고 있고, 또 1차측 냉각재가 원자로 안에서만 순환하므로 기존의 분리형원자로에 비해 구조특성상 대용량 원자로 냉각재 상실사고(LBLOCA)의 발생 가능성을 원천적으로 제거할 수 있다. 반면 원자로 냉각재의 보충 등을 위한 소형 배관의 파단 가능성은 역시 존재하므로 소용량 원자로 냉각재 상실 사고(SBLOCA)는 여전히 존재한다. 따라서 현재 한국원자력연구소에서 연구 개발중인 중소규모 전력생산 및 열 활용 목적의 일체형 원자로에는, 원자로 압력용기 외부에 별도의 압력용기(안전용기)를 설치하여 SBLOCA시 원자로 압력용기로부터 방출되는 냉각수를 안전 용기내에 보관하도록 함으로써 사고시 외부로의 방사성 물질 유출 가능성을 획기적으로 줄 일수 있는 설계 개념을 도입하고 있다. 본 논문에서는 안전용기의 설계시 효율적인 냉각방식에 대한 열유체 해석적 접근을 시도하였고, 예비개념설계된 일체형 열병합원자로의 설계상의 특징들 및 안전용기 설계시 앞으로의 연구방향 등도 간략히 소개하였다.