• Clean Technology
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• v.10 no.2
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• pp.53-59
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• 2004

Direct methanol fuel cells (DMFC) are presently paid attention due to their higher energy density and portability. In order to slove problems such as high anodic overpotential and methanol crossover in DMFC, an analytical analysis for electrochemical model using Tafel equation and limiting current density was performed. Change of operational parameters such as temperature, transfer coefficients and membrane thickness results in helpful informations on voltage-current curves.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.29 no.4 s.235
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• pp.477-484
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• 2005

Model fer the dynamic simulation of dynamic behaviors of a solid oxide fuel cell (SOFC) is provided. This model is based upon (1) coupled mass and heat transfer characteristics and (2) important chemical reactions such as electrochemical and reforming reactions in high temperature fuel cells such as SOFC. It is found that the thermal inertia of solid materials in SOFC plays an important role to the dynamic behavior of cell temperature. Dynamic characteristics of cell voltage, power, and chemical compositions with different levels of load change are investigated.

• 한국전기화학회:학술대회논문집
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• 2002.10a
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• pp.3-4
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• 2002

• Journal of the korean Society of Automotive Engineers
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• v.15 no.5
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• pp.31-41
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• 1993

7. 음파의 흡수와 분산. 8. 초음파의 지향성. 9. 고유진동과 공명,공진. 9.1 고유진동. 9.2 공진,공명. 9.3 공진주파수. 10. 캐비테이션. 10.1 현상. 10.2 거동. 11. 초음파. 11.1 초음파의 발생기구.

• Proceedings of the Materials Research Society of Korea Conference
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• 2007.11a
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• pp.105.2-105.2
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• 2007

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.121-122
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• 2015

• Fire Science and Engineering
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• v.30 no.2
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• pp.92-97
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• 2016

The present study has been conducted to estimate the chemical flame height based on fuel consumption in fire field model. The calculation algorithms based on cumulative fraction of HRRPUL and fuel concentration along the z axis were applied to the results predicted by Fire Dynamics Simulator (FDS) version 6.3.2 and the mean chemical flame height was obtained by time averaging of instantaneous flame height with the algorithms. The mean flame height calculated by fuel concentration was quite well matched with that of cumulative value of HRRPUL within 10% over-prediction. This study contribute to a more detailed understanding of fire behavior and quantitative evaluation of flame height in the computational fire model.

• Nuclear Engineering and Technology
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• v.21 no.4
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• pp.332-340
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• 1989

Destructive examination of 14$\times$14 PWR fuel burned for 3 cycles are carried out to investigate the in-reactor fuel performance. The results obtained are as follows; 1) Grain growth is not occured at the fuel center. 2) Fuel density is decreased as the turnup increase, the density is down to 94.4% TD at burnup of 36,000 MWD/MTU. 3) Average thickness of oxide layer on cladding is less than 10 $\mu$m in the lower and middle section, while it is rapidly increased above 20 $\mu$m in the upper section. 4) The rate of hydride production in the cladding is large in the upper section than lower section and is related to the production of oxide on the cladding

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 2008.05a
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• pp.77-81
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• 2008

The local regression rate behavior of solid fuel in swirl injection hybrid rocket were studied. In generally, axial injection regression rate was tending to be decrease with axial distance, beyond which increased with increasing axial distance from the leading edge. On the other hand, swirl injection regression rate was high at the leading edge of the fuel and comparatively uniform regression rate at the downstream. Overall regression rate of swirl injection was increased about 54% for the overall regression rate of axial injection. Through this study, it was found that using swirl injector was useful in applying to the small sounding rocket.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.39 no.3
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• pp.249-257
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• 2015

A fuel assembly consists of fuel rods composed of pellets (UO2) and a cladding tube (Zircaloy). The role of the fuel rods in the reactor is to generate heat by nuclear fission, as well as to retain fission products during operation. A simulation method using a computer program was used to evaluate the safety of the nuclear fuel rods. This computer program has been called the fuel performance code. In the analysis of a light water reactor fuel rod, the gap conductance, which depended on the distance between the pellets and cladding tube, mainly influenced the thermomechanical behavior of the fuel rod. In this work, a 3D gap element was proposed to simulate the thermo-mechanical behavior of the nuclear fuel rod, considering the gap conductance. To implement the proposed 3D gap element, a 3D thermo-mechanical module was also developed using FORTRAN90. The asymmetric characteristics of the nuclear fuel rod, such as the MPS (missing pellet surface) and eccentricity, were simulated to evaluate the proposed 3D gap element.