• 설비공학논문집
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• 제17권12호
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• pp.1177-1184
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• 2005

A numerical analysis was carried out on the heat and mass transfer, and pressure drop characteristics of the modular tube bundle heat exchanger. The finite volume method with a $k-\varepsilon$ turbulence model was used for the analysis. Due to condensation, the total heat transfer rate is observed about $4\~8\%$ higher than that on dry surfaces. Total heat transfer rate increases with increase in the velocity, temperature and relative humidity of incoming air. It also increases with decreasing the aspect ratio of heat exchanger tube. The inlet velocity of cooling water has little effect on the total heat transfer when the other conditions are fixed.

• Nuclear Engineering and Technology
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• 제45권7호
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• pp.895-910
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• 2013

The reflood test data from the rod bundle heat transfer (RBHT) test facility showed that the grids in the upper portion of the rod bundle could become wet well before the arrival of the quench front and that the sizes of liquid droplets downstream of a wet grid could not be predicted by the droplet breakup models for a dry grid. To investigate the water droplet generation from a wet grid spacer, a viscous linear temporal instability model of the water sheet issuing from the trailing edge of the grid with the surrounding steam up-flow is developed in this study. The Orr-Sommerfeld equations along with appropriate boundary conditions for the flow are solved using Chebyshev series expansions and the Tau-Galerkin projection method. The effects of several physical parameters on the water sheet oscillation are studied by determining the variation of the temporal growth rate with the wavenumber. It is found that a larger relative steam velocity to water velocity has a tendency to destabilize the water sheet with increased dynamic pressure. On the other hand, a larger ratio of steam boundary layer to the half water sheet thickness has a stabilizing effect on the water sheet oscillation. Droplet diameters downstream of the spacer grid predicted by the present model are found to compare reasonably well with the data obtained at the RBHT test facility as well as with other data recently reported in the literature.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2702-2713
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• 2022

A steam generator tube rupture accompanying a core damage may cause the fission product to be released to environment bypassing the containment. In such an accident, the steam generator is the major path of the radioactive aerosol release. AEOLUS facility, the scaled-down model of Korean type steam generator, was built to examine the aerosol removal in the steam generator during the steam generator tube rupture accident. Integral and separate effect tests were performed with the facility for the dry and flooded conditions, and the decontamination factors were presented for different tube configurations and submergences. The dry test results were compared with the existing test results and with the analyses to investigate the aerosol retention physics by the tube bundle, with respect to the particle size and the bundle geometry. In the flooded tests, the effect of submergence were shown and the retention in the jet injection region were presented with respect to the Stokes number. The test results are planned to be used to constitute the aerosol retention model, specifically applicable for the analysis of the steam generator tube rupture accident in Korean nuclear power plants to evaluate realistic fission product behavior.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 1994년도 추계학술발표회 초록집
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• pp.135-140
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• 1994

An improved steam generator model has been developed for the DSNP simulation of normal operational transient behavior of CANDU nuclear power plant. For more realistic prediction of steam generator behavior during transient, tube bundle region is divided into two separate control volumes, subcooled region and saturated region, and the variation of thermal hydraulic properties in the control volume is accounted for more realistic estimates of outlet enthalpy of each control volume. Test results for typical CANDU operational transient case show reasonable transient behavior of steam generator with overall CANDU operation and improved operational characteristics of steam generator with power variation.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2019년도 춘계학술대회
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• pp.201-203
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• 2019

Google Play에 새로운 콘텐츠들이 나오고 경쟁함으로써 앱과 게임의 크기는 지속적으로 증가하고 있다. 앱과 게임의 크기가 커질수록 Google Play 스토어를 통한 앱 설치가 줄어들고 있다. 본문은 기존 지원 모델인 APK에 대한 구조 및 한계에 대해 이야기하고 새로운 지원 모델인 AAB(Android App Bundle) 구조에 대해 이야기한다. 추가로 향후 전망을 해보고자 한다.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.36-48
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• 2022

As a valid numerical method to obtain a high-resolution result of a flow field, computational fluid dynamics (CFD) have been widely used to study coolant flow and heat transfer characteristics in fuel rod bundles. However, the time-consuming, iterative calculation of Navier-Stokes equations makes CFD unsuitable for the scenarios that require efficient simulation such as sensitivity analysis and uncertainty quantification. To solve this problem, a reduced-order model (ROM) based on proper orthogonal decomposition (POD) and machine learning (ML) is proposed to simulate the flow field efficiently. Firstly, a validated CFD model to output the flow field data set of the rod bundle is established. Secondly, based on the POD method, the modes and corresponding coefficients of the flow field were extracted. Then, an deep feed-forward neural network, due to its efficiency in approximating arbitrary functions and its ability to handle high-dimensional and strong nonlinear problems, is selected to build a model that maps the non-linear relationship between the mode coefficients and the boundary conditions. A trained surrogate model for modes coefficients prediction is obtained after a certain number of training iterations. Finally, the flow field is reconstructed by combining the product of the POD basis and coefficients. Based on the test dataset, an evaluation of the ROM is carried out. The evaluation results show that the proposed POD-ROM accurately describe the flow status of the fluid field in rod bundles with high resolution in only a few milliseconds.

• Asia Marketing Journal
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• 제14권1호
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• pp.53-81
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• 2012

묶음제품의 매력도를 증가시키기 위해 소비자들이 번들 오퍼에서의 가격 제시 프레이밍(framing)에 민감하다는 것을 이해할 필요가 있다. 동일 가격을 할인하더라도 묶음제품 요소 중 어느 요소에 가격할인을 표시하느냐에 따라 소비자의 묶음제품에 대한 지각된 매력도를 바꿀 수 있기 때문이다. 선행연구는 더 중요한 제품 요소에 할인이 할당될 때 효용이 증가한다는 주장과 덜 중요한 제품 요소에 할인을 위치시키는 것이 선호를 증가시킨다는 주장을 동시에 보이고 있다. 본 연구는 선행연구를 보완하여 묶음제품 가격 할인 제시 프레이밍효과에 대한 새로운 기제를 제시한다. 그리고 선행연구에서 믹스드(mixed)된 결론을 보이는 이유를 분석하여 밝힌다. 본 연구는 현실적인 번들링 전략 사용 상황을 고려하였으며, 좀 더 리얼한 번들링 세팅을 이용하여 가격 할인 제시 프레이밍 효과를 조사하고, 순수번들 및 혼합번들을 포함한 다양한 묶음제품을 이용하여 품질 불확실성 지각에 따른 조절효과를 분석하였다. 본 연구 결과, 소비자들은 높은 소비 혜택(high consumption benefit)보다 낮은 소비 혜택(low consumption benefit) 요소에 가격 할인을 위치시키는 것을 더 선호하였다. 가격민감성(price sensitivity)이 주요혜택에서는 낮고, 낮은 혜택에서는 높기 때문에 동일 가격이 할인될 때 낮은 혜택을 할인한 매장 제품에 대한 평가가 더 높게 나타났다. 또한 구매 시점에서 품질의 불확실성(perceived uncertainty of product quality)이 높을수록 가격민감성이 혜택 지각에 가지는 효과가 더 커지고 있었다. 본 연구의 공헌은 소비 혜택 지각 및 가격민감성 기제와 지각된 품질 불확실성의 조절효과를 통해 선행연구를 통합하고, 가격 제시 형태의 프레이밍 효과를 명확하게 설명하였다는 점이다.

• 한국전산구조공학회논문집
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• 제24권6호
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• pp.645-654
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• 2011

복층거더 번들형 사장교의 대블럭 가설 중 내풍안정성 확보를 위해 잭업바지 위에 임시벤트를 설치하여 가설 구조계를 지지하는 방안이 검토되었다. 일반적으로 거스트 계수를 곱한 정적 항력으로 임시벤트를 설계하는 경우 거더의 버페팅력에 의해 발생되는 임시벤트의 축력 변동성분을 고려할 수 없으며, 이는 일부 설계기준에 제시된 정적 상향 풍력으로도 평가할 수 없다. 유용한 해결 방안으로 주파수영역 버페팅해석을 수행하고 임시벤트에 작용하는 거더의 반력을 산정하였다. 우선 임시벤트를 해석 모델에 포함하고 거더와의 동적 상호작용을 엄밀히 반영하는 해석을 수행하였으며, 그 결과를 임시벤트가 거더를 받치는 고정 지지점으로 간주하여 해석한 경우의 결과와 비교 검토하였다. 임시벤트의 강성을 고려하는 경우 산정된 임시벤트와 거더 간 작용력은 임시벤트를 고정 지지점으로 간주하여 얻은 반력에 비하여 작은 값을 보였다. 따라서 대상교량의 가설 구조물 내풍설계를 수행하는 경우 임시벤트가 포함된 해석 모델링의 필요성과 버페팅해석을 통한 동적내풍 설계의 유용성을 제시하였다.

• 대한기계학회논문집B
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• 제25권12호
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• pp.1831-1843
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• 2001

In this study, convective boiling tests were conducted for enhanced tube bundles. The surface geometry consists of pores and connecting gaps. Tubes with three different pore sizes (d$_{p}$ = 0.20, 0.23 and 0.27 mm) were tested using R-123 and R-l34a for the following range: 8 kg/m$^2$s G 26 kg/m$^2$s, 10 kW/m$^2$ q0 40 kW/m$^2$and 0.1 $\chi$ 0.9. The convective boiling heat transfer coefficients were strongly dependent on heat flux with negligible dependency on mass flux or quality. For the present enhanced geometry (pores and gaps), the convective effect was apparent. The gaps of the present tubes may have served routes for the passage of two-phase mixtures, and enhanced the boiling heat transfer. The convective effect was more pronounced at a higher saturation temperature. More bubbles will be generated at a higher saturation temperature, which will lead to enhanced convective contribution. The pore size where the maximum heat transfer coefficient was obtained was larger for R-l34a (d$_{p}$ = 0.27 mm) compared with that for R-123 (d$_{p}$ = 0.23 mm). This trend was consistent with the previous pool boiling results. For the enhanced tube bundles, the convective effect was more pronounced for R-134a than for R-123. This trend was reversed for the smooth tube bundle. Possible reasoning is provided based on the bubble behavior on the tube wall. Both the modified Chen and the asymptotic model predicted the present data reasonably well. The RMSEs were 14.3% for the modified Chen model and 12.7% for the asymptotic model.model.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4561-4569
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• 2023

A correct understanding of vibration-based degradation is crucial from the standpoint of maintenance for Steam Generators (SG) as crucial mechanical equipment in nuclear power plants. This study has established a novel approach to developing a model for investigating tube bundle degradation according to crack growth caused by two-phase Flow-Induced Vibration (FIV). An important step in the approach is to calculate the two-phase flow field parameters between the SG tube bundles in various zones using the porous media model to determine the velocity and vapor volume fraction. Afterward, to determine the vibration properties of the tube bundles, the Fluid-Solid Interaction (FSI) analysis is performed in eighteen thermal-hydraulic zones. Tube bundle degradation based on crack growth using the sixteen most probable initial cracks and within each SG thermal-hydraulic zone is performed to calculate useful lifetime. Large Eddy Simulation (LES) model, Paris law, and Wiener process model are considered to model the turbulent crossflow around the tube bundles, simulation of elliptical crack growth due to the vibration characteristics, and estimation of SG tube bundles degradation, respectively. The analysis shows that the tube deforms most noticeably in the zone with the highest velocity. As a result, cracks propagate more quickly in the tube with a higher height. In all simulations based on different initial crack sizes, it was observed that zone 16 experiences the greatest deformation and, subsequently, the fastest degradation, with a velocity and vapor volume fraction of 0.5 m/s and 0.4, respectively.