• Structural Engineering and Mechanics
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• 제2권2호
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• pp.157-171
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• 1994

A general approach to the dynamic time-history analysis of the reactor core is presented in this paper as a part of the fuel assembly qualification program. Several detailed core models are set up to reflect the placement of the fuel assemblies within the core shroud. Peak horizontal responses are obtained for each model for the motions induced form earthquake. The dynamic responses such as fuel assembly deflected shapes and spacer grid impact loads are carefully investigated. Also, the sensitivity responses are obtained for the earthquake motions and the fuel assembly non-linear response characteristics are discussed.

• 한국복합재료학회:학술대회논문집
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• 한국복합재료학회 2003년도 추계학술발표대회 논문집
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• pp.175-178
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• 2003

Mechanical behavior of a fuel stack was studied by the orthotropic material model. The fuel stack is mainly composed of bipolar plate (BP), gasket, end plate, membrane electrolyte assembly (MEA), and gas diffusion layer (GDL). Each component is fastened with a suitable pressure. It is very important to maintain a suitable contact pressure of BP, because it affects the efficiency of the fuel cell. This study compared mechanical behavior of various fastening types of the fuel cell stack. Bar, band, and modified band fastening type are used. The band fastening type showed that it reduces total volume of the cell, but it does not improve the contact pressure distribution of each BP. The modified band fastening type was designed by considering the deformations of band fastening type, and it showed a good enhancement of contact pressure distribution.

• 한국자동차공학회논문집
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• 제9권2호
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• pp.19-27
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• 2001

This paper is the first of 3 companion papers which investigate axial stratification process. In-cylinder fuel behavior has been investigated in the port injected SI engine by visualization for the purpose of understanding stratification. Planar laser light sheet from an Nd:YAG laser has been illuminated through the transparent quartz cylinder of the single cylinder optical engine and the Mie scattered light has been replaced with an air-ethanol mixture to utilize atomized fuel spray for the visualization purposes. This results have been compared with steady flow concentration measurement. For no swirl port, the axial penetration depends on the fuel injection timing. The fuel tends to remain in the upper region of the cylinder far from the spark plug and the distribution is not affected by the injection timing except 90 ATDC.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.363-364
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• 2005

• 대한기계학회논문집B
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• 제38권9호
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• pp.763-771
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• 2014

본 연구는 에멀젼연료($diesel/H_2O_2$)의 분무거동특성에 관한 기초 연구로서 에멀젼연료를 제조하여 분무 거동특성에 영향을 주는 연료의 물성치(점도, 표면장력, 밀도)와 연료액적 증발특성을 조사하였다. 또한 에멀젼연료와 디젤연료의 거시적 분무거동특성인 분무선단도달거리, 분무각을 비교 분석하였다. 에멀젼연료의 교반 조건은 디젤 연료와 계면활성제 span 80, tween 80을 각각 9:1로 혼합한 유화제를 제작하여 사용 하였으며 과산화수소의 혼합비율은[EF(Emulsified Fuel)2, EF12, EF22, EF32, EF42, EF52, EF62, EF72, EF82, EF92]로 설정하였고, 분사압력은 400bar, 600bar, 800bar 및 1000bar로 설정하였다. 본 연구의 결과로서 연료의 점도는 과산화수소의 혼합비율이 증가할수록(EF52까지) 점도가 증가하나, 그 이후부터는 점도가 낮아져 기존의 디젤연료와 같은 점도를 가지게 된다. 이는 디젤의 혼합비율이 큰 EF52까지는 교반 시 수중유형(Water in Oil)이 생성되나 과산화수소의 혼합비율이 큰(EF52 이상) 에멀젼연료에서는 유중수형(Oil in Water)이 생성되기 때문이다. 또한 혼합비 변화에 따른 분무거동의 특성(분무선단도달거리, 분무각)의 변화는 크지 않았다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.907-908
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.373-374
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• 2005

• Nuclear Engineering and Technology
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• 제43권6호
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• pp.499-508
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• 2011

The paper briefs a fuel performance code, COSMOS, which can be utilized for an analysis of the thermal behavior and fission gas release of fuel, up to a high burnup. Of particular concern are the models for the fuel thermal conductivity, the fission gas release, and the cladding corrosion and creep in $UO_2$ fuel. In addition, the code was developed so as to consider the inhomogeneity of MOX fuel, which requires restructuring the thermal conductivity and fission gas release models. These improvements enhanced COSMOS's precision for predicting the in-pile behavior of MOX fuel. The COSMOS code also extends its applicability to the instrumented fuel test in a research reactor. The various in-pile test results were analyzed and compared with the code's prediction. The database consists of the $UO_2$ irradiation test up to an ultra-high burnup, power ramp test of MOX fuel, and instrumented MOX fuel test in a research reactor after base irradiation in a commercial reactor. The comparisons demonstrated that the COSMOS code predicted the in-pile behaviors well, such as the fuel temperature, rod internal pressure, fission gas release, and cladding properties of MOX and $UO_2$ fuel. This sufficient accuracy reveals that the COSMOS can be utilized by both fuel vendors for fuel design, and license organizations for an understanding of fuel in-pile behaviors.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.439-440
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• 2005

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.398-399
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• 2005