• Transactions of the Korean Society of Automotive Engineers
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• v.10 no.6
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• pp.1-10
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• 2002

As the preliminary stage for the countermeasure of thermal loading in miller cycle engine, coolant flows in the cylinder head of base engine including exhaust valve bridge were visualized and analyzed by using PIV technique. It was found that low coolant velocity regions were around exhaust valve bridge, around which stagnation of the coolant flow was observed due to the complex geometry configuration of water jacket. And velocity variation between each cylinder was remarkable. For the countermeasure of these, it is necessary to enhance coolant flow around exhaust valve bridge and to improve the deviation of coolant flow between each cylinder.

• Transactions of the Korean Society of Automotive Engineers
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• v.3 no.5
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• pp.17-23
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• 1995

A numerical analysis on engine coolant is made by the use of FVM based general purpose 3 dimensional Navier-Stokes solver, TURB-3D. Numerical solutions are verified by comparison with the experimental data of Lotus model. The results show a good qualitative as well as quantitative comparison. Coolant flow rate control is attempted through adjusting the cross section area of passage base on the results of an original coolant passage. It is concluded from the results that the flow rate control is possible as attempted, and thus can be used in the real engine design.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.8 no.2
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• pp.33-41
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• 2012

The component cooling water heat exchangers are critical components in a nuclear power plant. As the operation years of the heat exchanger go by, the maintenance costs required for continuous operation also increase. Most heat exchangers have carbon steel shells, tube support plates and flow baffles. The titanium tube is susceptible to flow induced vibration. The damage on carbon steel tube support rod and titanium tube around cooling water entrance area is inevitable. Therefore, analysis of internal flow around the component cooling water entrance and tube channel is a good opportunity to seek for failure prevention practice and maintenance method. The numerical study was carried out by FLUENT code to find out the causes of tube failure and its location.

• Journal of the Korean Society of Propulsion Engineers
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• v.19 no.3
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• pp.39-46
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• 2015

A numerical study has been conducted on CO after burning and NO generation of the rocket plume as the cooling water injected to the rocket plume. The present study shows that the cooling water has a role of increasing the degree of CO after burning and reducing NO generation. However the effect varies as the injection configuration of the cooling water. When the cooling water is injected at the side of the plume, NO generation is dramatically reduced while the degree of CO after burning is relatively low. When the cooling water is injected at the side and the center of the plume, CO after burning is highly increased and NO generation is also dramatically reduced.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.23-29
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• 1997

유한요소법을 이용하여 경수로형 핵연료집합체에서 냉각수 유동에 의한 수직 상승력으로부터 핵연료를 지지하는 판형 HDS의 강성도를 수치해석적으로 평가할 수 있는 방법을 제안하였다 I-DEAS code의 8 node brick element를 사용하고 판스프링들간의 간섭 부위에 접촉요소를 사용한 유한요소 모델링 및 해석기법으로 평가한 탄성강성도가 변형 에너지법에 근거하여 유도된 탄성강성도 평가식으로부터 얻은 결과와 잘 일치하고 있어서 제안된 유한요소 모델링 및 해석기법은 판형 HDS의 거동 분석에 유용하게 이용될 수 있다.

• Journal of the KSME
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• v.28 no.3
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• pp.270-280
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• 1988

증기폭발현상에 대한 기존의 연구내용들이 개괄적으로 소개되었다. 지난 30여년간 대규모 및 소규모 증기폭발에 대해 수많은 이론 및 실험적 연구가 진행되어 왔으나 아직 많은 과제들이 미해결의 상태로 남아 있다. 이들은 (1) 연료-냉각수 접촉양식의 영향 (2) 초기 혼합과정에 대한 에너지 전달 및 유동해석 (3) 연료파괴 과정에 대한 정량적 해석 (4) 폭발과정의 전파에 대한 제인자의 영향 (5) 팽창과정 중 슬러그(slug)의 영향 등이며 현상 자체의 난이성과 위 험성에 비추어 볼 때 해석에 많은 문제점을 안고 있다. 그러나 과학적인 호기심과 더불어 산 업재해 방지 및 현상의 생산적 이용이라는 최종목표에 도달하기 위해서는 체계적으로 집중적인 연구가 꾸준히 계속되어야 할 것이다.

• Transactions of the Korean Society of Automotive Engineers
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• v.1 no.1
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• pp.32-40
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• 1993

Flow fields in model engine cooling passages are studied numerically by using TURBO-3D program, a finite volume based 3-D turbulent flow program adopting a general body fitted coordinate system. The effects of exit position on mass flow rate at each gasket hole are examined for a model cooling passage in order to understand the flow distribution inside the water jacket. The results of the present study can be applied to the design of high performance, high reliability engine.

• 한국전산유체공학회:학술대회논문집
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• 2008.03b
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• pp.444-447
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• 2008

A nuclear fuel test loop (after below, FTL) is installed in IR1 of an irradiation hole in HANARO for testing neutron irradiation characteristics and thermo hydraulic characteristics of a fuel loaded in a light water power reactor (PWR) or a heavy water power reactor (CANDU). There is an in-pile section (IPS) and an out-pile section (OPS) in this test loop. When HANARO is normally operated, the fuel loaded in the IPS has a nuclear reaction heat generated by a neutron irradiation. To remove the generated heat and to maintain an operation condition of the test fuel, a main cooling water system (MCWS) is installed in the OPS of the FTL. The pump can not continuously suck a fluid and not pressurize the fluid during a cold function test. To verify the flow characteristics of the MCWS, a flow net work analysis has been conducted. When the higher elevation pipelines wholly filled with coolant, it was confirmed through the analysis results that the pump pressurized the coolant normally. And the analysis results described the system characteristics with operation temperature and pressure variation satisfactorily.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.573-578
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• 1997

기존 냉각수 주입 계통의 안전성 및 신뢰도를 높이려는 노력에서 미국, 일본, 이태리 등 여러 나라에서는 증기 주입기에 대한 분석 기법 개발과 실험을 통한 연구가 활발하게 진행되고 있다. 이들이 이상 유동 현상이 일어나는 혼합 노즐을 해석하기 위해 사용한 방법은 제어체적 분석기법으로, 이 분석 방법에서는 응축 메커니즘을 고려할 수 없다. 본 연구에서는 이러한 사항을 개선하기 위해 혼합 노즐 해석시 one dimensional two fluid model을 적용하여 상간의 운동량 및 에너지 전달을 고려함으로써 비교적 정확하게 해석 모델 및 코드를 개발하였고, 출력 변수인 방출 압력과 방출 온도를 계산하였으며, 개발한 해석 코드를 검증 및 분석을 하기 위해 ANL 실험자료를 근거로 하였다. 개발한 코드에 의해 계산된 방출 압력은 ALN 실험치에 비해 높은 경향을 보여 주었지만 ANL에서 제어 체적 분석 기법을 적용하여 이론식으로 계산한 값보다는 비교적 정확한 경향을 보여 주었다.

• Proceedings of the KAIS Fall Conference
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• 2005.05a
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• pp.75-78
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• 2005

본 논문은 CPU의 수냉식 쿨러 자켓에 대하여 CFD(computational fluid dynamics) 해석을 수행하여 내부면적이 큰 쿨러 자켓의 효율이 어느 정도 좋은 지를 내부면적이 작은 쿨러 자켓과 비교 분석한다. 쿨러 자켓이 냉각수와 열 교류를 원활히 할 수 있도록 쿨러 자켓의 온도분포를 통하여 적절한 형상을 설계하여 CPU 수냉식 쿨러 자켓의 제작시 설계 자료로 이용하고자 한다.