• Nuclear Engineering and Technology
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• v.29 no.3
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• pp.229-239
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• 1997

To investigate the realistic behavior of mass and energy release and resultant containment response during large break Loss of Coolant accident (LOCA), analyses are performed for Yonggwang (YGN) 3&4 nuclear power plants by using a merged version of RELAP5/CONTEMPT4 computer code. Comparative analyses by using conservative design computer codes are also peformed. The break types analyzed are the double-ended guillotine breaks at the cold leg and hot leg. The design analysis resulted in containment peak pressure during post-blowdown phase for the cold leg break. However, the RELAP5/CONTEMPT4 analyses show that the containment pressure has a peak during blowdown phase, thereafter it decreases monotonously without the second port-blowdown peak. For the hot leg break, revised design analysis shows much lower pressure than that reported in YGN 3&4 final safety analysis report. The RELAP5/CONTEMPT4 analysis shoos similar trend and confirmed that the bypass flow through the broken loop steam generator during post-blowdown is negligibly small compared to that of cold leg break. The low pressure and temperature predicted tv realistic analysis presented in this paper suggest that the design analysis methodology contains substantial margin and it can be improved to provide benefit in investment protection, such as, relaxing plant technical specifications and reducing containment design pressure.

• Nuclear Engineering and Technology
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• v.39 no.5
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• pp.591-602
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• 2007

The results of Reactivity-Initiated Accidents (RIA) experiments have been analysed and the main variables affecting the fuel failure propensity identified. Fuel burn-up aggravates the mechanical loading of the cladding, while corrosion, or better the hydrogen absorbed in the cladding as a consequence of corrosion, may under some conditions make the cladding brittle and more susceptible to failure. Experiments point out that corrosion impairs the fuel resistance for RIA transient occurring at cold conditions, whereas there is no evidence of important embrittlement effects at hot conditions, unless the cladding was degraded by oxide spalling. A fuel failure threshold correlation has been derived and compared with experimental data relevant for BWR and PWR fuel. The correlation can be applied to both cold and hot RIA transients, account taken for the lower ductility at cold conditions and for the different initial enthalpy. It can also be used for non-zero power transients, provided that a term accounting for the start-up power is incorporated. The proposed threshold is easy to use and reproduces the results obtained in the CABRI and NSRR tests in a rather satisfactory manner. The behaviour of advanced PWR alloys and of MOX fuel is discussed in light of the correlation predictions. Finally, a probabilistic approach has been developed in order to account for the small scatter of the failure predictions. This approach completes the RIA failure assessment in that after determining a best estimate failure threshold, a failure probability is inferred based on the spreading of data around the calculated best estimate value.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.24 no.5
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• pp.409-414
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• 2012

A theoretical investigation to optimize thermoelectric elements for thermoelectric coolers was performed using a new one-dimensional analytic model. Mathematical expressions for the optimum current and the optimum length of a thermoelectric element, which maximize the coefficient of performance of thermoelectric coolers, were obtained. The optimum current is expressed in terms of the cooling load for a thermoelectric element, the hot and cold side temperatures and thermoelectric properties, but not the length of a thermoelectric element. The optimum current is proportional to the cooling load and decreases as the temperature difference between the hot and cold sides decreases. It is also shown that the optimum length of a thermoelectric element decreases as the cooling load increases.

• Journal of Satellite, Information and Communications
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• v.12 no.3
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• pp.103-107
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• 2017

The Satellite OBC(On Board Computer) manages critical functionality such as satellite attitude control, fault management, payload management, command/telemetry processing etc. The OBC consist of various modules. Each module perform mission critical operation. So all modules designed as hot or cold redundancy architecture. The redundancy design gives a guarantee high reliability and it allows normal operation of satellite using reconfiguration capability. In this paper, introduces reconfiguration unit operation and describe the results of testing in the ETB.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.32 no.2
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• pp.92-99
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• 2008

The "energy separation phenomenon" through a vortex tube has been a long-standing mechanical engineering problem whose operational principle is not yet known. In order to find the operational principle of the vortex tube, CFD analysis of the flow field in the vortex tube has been carried out. It was found that the energy separation mechanism in the vortex tube consists of basically two major thermodynamic-fluid mechanical processes. One is the isentropic expansion process at the inlet nozzle, during which the gas temperature is nearly isentropically cooled. Second process is the viscous dissipation heating due to the high level of turbulence in both flow passages toward cold gas exit as well as the hot gas exit of the vortex tube. Since the amount of such a viscous heating is different between the two passages, the gas temperature at the cold exit is much lower than that at the hot exit.

• Transactions of the Korean Society of Automotive Engineers
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• v.9 no.1
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• pp.84-93
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• 2001

The aim of this study is to provide fundamental informations that make it possible to use a cool stream and a hot stream simultaneously. We changed the pressure of compressed air that flows into a tube, the inner diameter of orifice that a cold stream exits, and the mass flow rate ratio. And in each case, we measured the temperature of a cold stream and a hot stream in each exit of a tube. Also we measured the axial temperature distribution and the radial temperature distribution in internal space of a tube. From the study, following conclusive remarks can be made. Average flow rate that flows into a tube is in proportion to square root of inlet pressure. As inlet pressure increases axial and radial temperature distribution in the inner space of vortex-tube increase. As mass flow rate ratio change, separation point moves.

• Journal of the KSME
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• v.33 no.9
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• pp.780-792
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• 1993

난류 열유속 측정을 위한 실험기법을 고찰해본 결과, 열선-냉선 조합 프로브의 사용이 현재로 서는 가장 가능성 있는 기법임을 알 수 있었다. 이와 같은 기법에서 가장 중요한 요소는 난류의 온도 변동량을 정확히 측정할 수 있는 계측장치의 확보임을 알았다. 그동안 사용되어 왔던 각종 냉선온도계의 검토와 본 연구실에서 새로이 개발한 냉선온도계의 설계 및 제작 기법에 대해 소 개하였다. 여러 가지 관점에서의 성능 비교를 통해 본 연구실에서 개발된 냉선 브리지의 성능이 상당히 우수함을 보였다. 난류 열유속의 측정과 비등온 유동에서의 난류 속도 성분을 측정하기 위한 프로브는 X형 hot-wire 프로브와 I형 cold wire 프로브를 조합하여 만들어졌으며, 온도와 속도를 함께 고려하여 교정함으로써 온도구배가 있는 속도장과 난류열유속을 측정할 수 있는 방법을 소개하였다.

• Proceedings of the Korean Society for Technology of Plasticity Conference
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• 1999.03a
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• pp.149-152
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• 1999

The effect of initial orientation on the microstructure and texture evolution of two ferritic stainless steels was investigated. the columnar and equiaxed crystal specimens which were prepared from continuous casting slab were hot rolled annealed cold rolled and annealed respectively. The rolling and recrystallization textures at each process stage were examined by orientation distribution function (ODF) and electron back-scattered diffraction (EBSD); The observation showed that the orientation density of the $\alpha$-fibre of hot rolled band of columnar crystal specimen was more pronounced than that of the equaxed one at the center layer. Nevertheless the cold rolled textures of Type 430 steel have demonstrated a rather similar development . Compared to Type 430 steel the development of the $\alpha$-fibre in the center layer of Type 409L steel was much more pronounced. The relation between texture evolution and ridging behaviour has been discussed.

• Nuclear Engineering and Technology
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• v.12 no.2
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• pp.111-120
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• 1980

Nuclear physics parameters of the Wolsung CANDU-PHW reactor are computed by use of the PHWCELL computer code that is an improved version of LATREP. The PHWCELL code mainly computes cell parameters of heavy water moderated reactors, and modeling scheme of heavy water reactor cell calculations has been developed with the PHWCELL computer code. The reactor operating conditions considered in the study are cold zero power (CZP) and hot full power (HFP) with equilibrium poison. The cell parameters are also computed as a function of fuel burnup and the numerical results are compared with the results in PSR of the Wolsung unit and in the previous study.

• IE interfaces
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• v.17 no.1
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• pp.104-112
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• 2004

The purposes of the study were twofold: to investigate the stereotype of position and direction that the users expect when operating the handles of a water faucet in different directions, and to collect information about user’s preferred directions. Six hundred subjects, aged from teens to over sixties, participated in the experiment with the procedure of showing them actual water faucets of a lever-type handle and two round-shaped handles mounted on the sink(horizontal plane) and wall(vertical plane). The water faucets presented to the subjects were most widely used devices in our living environment. The results showed that when the handle of the lever-type water faucet was in the 'up' position, 63% of the subjects expected the device was 'open'. When the cold hot separated water faucets were mounted on the horizontal or vertical plane, over 50% of those who answered the 'open' direction of round type handles responded as 'counter clockwise' for a 'hot' water faucet and 'clockwise' for a 'cold' water faucet. In conclusion, this study suggests that water faucet devices be designed and installed in the way that the users expect them to operate.