• Proceedings of the Korean Environmental Sciences Society Conference
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• 2020.10a
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• pp.124-124
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• 2020

• Proceedings of the KSME Conference
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• 2007.05b
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• pp.2303-2308
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• 2007

Experiments were performed to determine the thermal (or turbulent) diffusion coefficient (TDC) and to investigate the critical heat flux (CHF) performance in the 5${\times}$5 rod bundle with 5 unheated rods which are supported by Hybrid Mixing Vane. In this study, HFC-134a fluid was used as working fluid and the fluid temperature were measured in the important subchannels. To determine the TDC value, the measured fluid temperatures were compared with the predicted values obtained from the MATRA code. The best optimized value of ${\beta}$ was found to be 0.02 by considering prediction statistics, i.e., average and standard deviations of the differences between the experimental results and code calculations. Using the best optimized value of ${\beta}$ as 0.02, the MATRA code predicts the test results of the fluid temperature within ${\pm}$1.0 % of error. According to the experimental results on CHF of 5 non-heating guide tubes, the case with non-heating guide tube showed a little good performance in terms of CHF.

• Proceedings of the KSME Conference
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• 2007.05b
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• pp.2873-2878
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• 2007

The mixing vanes attached to the spacer grid of rod bundles are used to improve the heat transfer in heat exchanger devices by controlling the characteristics of the flow structures and turbulence. In this study, velocity patterns induced by two types of mixing vane(split and swirl vane) are measured by the PIV technique to better understand how to effect on the cross and secondary vortex flow patterns in $5{\times}$ rod bundle simulating the fuel assembly of the nuclear reactor. A successful measurement of the lateral velocity patterns was conducted using a specially designed beam sheet generator and experimental loop at KAERI. As the result, we found that for the cross flow between subchannels, the split vane is more effective than the swirl vane, while for the secondary vortex flow in each subchannel, the swirl vane's one is larger and longer than split vane's one.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.29 no.10
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• pp.538-550
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• 2017

In a PWR (Pressurized Water Reactor), the appropriate heat removal from the surface of fuel rod bundle is important for ensuring thermal margins and safety. Although many CFD (Computational Fluid Dynamics) software have been used to predict complex flows inside fuel assemblies with mixing vanes, there is no domestic regulatory guideline for the comprehensive evaluation of CFD software. Therefore, from the nuclear regulatory perspective, it is necessary to perform the systematic assessment and prepare the domestic regulatory guideline for checking whether valid CFD software is used for nuclear safety problems. In this study, to provide systematic evaluation and guidance on the applicability of CFD software to the domestic nuclear safety area, the results of the sensitivity analysis for the effect of the discretization scheme accuracy for the convection terms and turbulence models, which are main factors that contribute to the uncertainty in the calculation of the nuclear safety problems, on the prediction performance for the turbulent flow distribution inside the fuel assembly with split-type mixing vanes were explained.

• Journal of Energy Engineering
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• v.13 no.2
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• pp.101-111
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• 2004

The main purpose of a liquid metal reactor core thermal-hydraulic design is to efficiently extract the core thermal power by distributing the appropriate sodium coolant flow according to the power distribution in the core. The thermal-hydraulic design procedure consists of the coolant flow distribution to the sub-assemblies, the coolant/fuel temperature calculations and detailed subchannel analysis. This paper describes the LMR core thermal-hydraulic design methodology and summarizes the major design and analysis results of KALIMER breeder and breakeven cores and subassemblies. KALIMER is a 150 MWe rated (392 MWth) heterogeneous core with U-TRU-Zr ternary alloy fuel and sodium coolant.

• Nuclear Engineering and Technology
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• v.24 no.2
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• pp.168-177
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• 1992

The importance of the study of two phase flow phenomena has increased for both fuel performance and safety analysis of nuclear power plants. In the analysis of two phase flow system, an accurate prediction of local void fractions is very important. In this study, a vertical rectangular subchannel having 4 electrically heated rods is constructed for the measurement of local void fraction under two phase flow. The measurement has been conducted by electrical conductivity probes and signal processing circuit which are known to be adequate to measuring local void fraction. Also experiments are performed with varying the inlet flow rate to search for radial void fraction profile accordingly to the different flow rate even with the same averaged void fraction. From the result of experiments, the validity of electrical conductivity probe and electrical circuit is confirmed.

• Proceedings of the Korean Society for Cognitive Science Conference
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• 2002.05a
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• pp.183-188
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• 2002

데이비슨에서부터 시작됐다고 해도 과언이 아닌 것으로 보이는 정신적 속성들의 인과적 힘과 관련된 논의 - 정신인과의 문제를 해결하기 위해서 설정하는 - 는 그가 주장한 이론이 맞이하게 되는 심각한 문제에 해결책을 제시하고자 하는 많은 책학자들의 관심을 불러일으킨다. 그 중의 하나인 포돌도 결국 데이비슨이 주장한 세 가지의 원리들 중에서 중요한 한가지 원리, 즉 정신적인 것들의 무법칙성의 원리, 를 거절하면서 자신의 정신인과 이론을 발전시키고자 한다. 즉 정신적 속성들과 물리적 속성들을 연결시키는 "참 인과의 법칙으로서 다른 것들이 같다면의 법칙"을 정신인과의 현상을 설명하는 그의 설명적 모델로 제시하면서 데이비슨의 문제를 해결하려고 시도한다. 그러나 그가 스케치하는 그런 그림은 인과적 배제의 원리를 명백하게 위반하는 것이다. 설상가상으로 이러한 문제를 벗어나기 위해서 그가 의지하는 수반의 개념도 그 효력은 충분하게 강하지 못한 것으로 드러난다. 이것이 틀리지 않다면 여기서 어떤 딜레마가 일어난다. 만약 정신적 속성들이 아직까지 인과적으로 효력을 가지고 있다면 명백하게 물리적 세계의 인과적 폐쇄의 원리의 위반이 일어난다. 만약 정신적 속성들이 인과적 효력을 가지고 있지 않다면 우리는 여기서 명백히 부수현상론을 보게 된다.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.28 no.5
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• pp.186-194
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• 2016

As a turbulence-enhancing device, a mixing vane installed at a spacer grid of the fuel assembly plays a role in improving the convective heat transfer by generating either swirl flow in the subchannels or cross flow between fuel rod gaps. Therefore, both configuration and arrangement pattern of a mixing vane are important factors that determine the performance of a mixing vane. In this study, in order to examine the flow distribution features inside $5{\times}5$ fuel assembly with swirl-type mixing vanes used in benchmark calculation of OECD/NEA, simulations were conducted with commercial CFD software ANSYS CFX R.14. Predicted results were compared to data measured from MATiS-H (Measurement and Analysis of Turbulent Mixing in Subchannels-Horizontal) test facility. In addition, the effect of swirl-type mixing vanes on flow pattern inside the fuel assembly was described.

• The Journal of Korean Institute of Communications and Information Sciences
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• v.18 no.9
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• pp.1269-1282
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• 1993

In this paper, we propose to method of recognizing printed chinese characters which combine the coventional deterministic methods and the neural networks. Firstly, we extract four directional vector of strokes from chinese characters. Secondly, we make the mesh of the center of gravity in the vector and then constitute the H x8 feature matrix using black pixel lenth from each meshs. This normalized feature matrix value offer as the input of neural network for classifying into the 14 character types. And this calssified character classify again into Busu group by the Busu recognizing neural network. Finally, we recognize each characters using the distance of similarity between input characters and reference characters. The usefulness of the proposed algorithm is evaluated by experimenting with recognizing the chinese characters.

• Nuclear Engineering and Technology
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• v.27 no.6
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• pp.888-893
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• 1995

The turbulence structure for fully developed flow through the subchannels formed by the bare rod array depends on the pitch to rod diameter ratio. For fairly open spaced bare rod arrays, the distributions of the three components of the turbulent normal stresses are similar to those measured in circular pipe. However, for more closely spaced arrays, the turbulence structure, especially in the gap region, depart markedly from the pipe flow distribution. A linear relationship between turbulent normal stresses and turbulent kinetic energy for fully developed turbulent flow through regularly spaced bare rod arrays has been developed. This correlation can be used in connection with various theoretical analyses applied in turbulence research.