• Journal of computational fluids engineering
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• v.1 no.1
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• pp.35-46
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• 1996

원심형 임펠러 내부 유로등 큰 곡률을 수반하는 터보기계 요소의 유동해석을 위한 계산코드를 개발하였다. 이 코드에서는 곡선좌표계에 유도된 3차원 비압축성 Navier-Stokes의 운동 방정식을 SMAC 음해법으로 푼다. 이 코드를 이용하여 유로의 단면이 정사각형이고 90도로 굽은 덕트내부의 층류 입구유동을 해석하고, 굽은 관 특유의 유동현상을 수치모사하였다 또한 곡관부 입구에서 충분히 발달한 유동, 또는 발달중인 유동이 유입될 경우에 이것이 곡관부 내부의 유동에 미치는 영향을 상·하류의 계산영역이 서로 다를 몇몇 유동장에 대하여 조사하고, 본 계산에서 얻어진 결과와 실형결과와의 비교로 본 3차원 유동해석 코드의 유효성을 검토 하였다.

• Transactions of the Korean Society of Mechanical Engineers
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• v.16 no.10
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• pp.1915-1927
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• 1992

A three-dimensional Navier-Stokes code has been developed for analysis of viscous flows through turbomachinery blade rows or other internal passages. The Navier-Stokes equations are written in a cartesian coordinate system, then mapped to a general body-fitted coordinate system. Streamwise viscous terms are neglected and turbulent effects are modeled using the baldwin-Lomax model. Equations are discretized using finite difference method on the stacked C-type grids and solved using LU-ADI decomposition scheme. calculations are made for a two-dimensional cascade in a transonic wind-tunnel to see the infuence of the endwalls. The flow pattern of the three-dimensional flow near the endwall is found to be different from that of the two-dimensional flow due to the existence of the endwalls.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.567-572
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• 1997

범용 전산유체해석(Computational Fluid Dynamics) 코드인 CFX-F3D를 이용하여 봉 다발에서의 난류 유동 수치해석을 수행하였다 3$\times$3 봉으로 구성된 부수로 사이의 난류 횡류(Crossflow) 혼합유동과 평행한 4개의 봉으로 이루어진 벽 수로에서의 난류 유동구조를 수치적으로 분석하여 각각의 실험결과와 비교하였다. 부수로 횡류 혼합유동의 경우 예측된 주 유동방향 평균 속도분포는 실험결과와 잘 일치하였으나 벽면과 인접한 부수로에서의 난류강도 분포는 다소 큰 차이가 나타났다. 백수로의 경우 수로 중심선 근처의 주 유동방향의 속도변화는 크게 예측되었고 벽 전단응력은 유로가 협소해지는 영역에서 낮게 예측되었으나 전반적으로 실험결과와 유사한 유동특성을 나타냈다. 이 연구는 봉 다발에서의 난류 유동구조에 대한 이해를 증진시킴과 더불어 CFX-F3D 코드를 평가함으로써 향후 지지격자와 임계열유속 증진장치가 부착된 복잡한 형상의 핵연료 다발에서의 유동장 수치해석의 기반을 마련하였다.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.35 no.8
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• pp.677-684
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• 2007

In the Present Study, a 3-D viscous flow solver, based on unstructured hybrid meshses containing tetrahedra, prisms and pyramids, has been developed. A finite-volume discretization scheme is used for solving the compressible Navier-Stokes equations. A cell-vertex median dual volume is used for spatial discretization. The one-equation Spalart-Allmaras turbulence model has been adopted to evaluate the eddy viscosity. Validation were made by computing laminar and turbulent flows around a 3-D wing for steady flows and turbulent flows around an oscillating 3-D wing in harmonic motion for unsteady flows.

• Journal of the Korean Society of Propulsion Engineers
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• v.15 no.6
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• pp.38-46
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• 2011

In order to simulate the ignition-gas injection in the interior ballistics, a two-dimensional analytic code for two-phase flows has been developed. The Eulerian-Lagrangian approach and the low-dissipation simple high-resolution upwind scheme(LSHUS) have been adopted in the numerical code for the propellant combustion of the gun propelling charges. The ghost-cell extrapolation method has been used for the moving boundary in the chamber with the projectile movement. The calculation results of the developed code have been compared and verified through those of the dimensionless IBHVG2 code and the previous one-dimensional code. In comparison with the two-phase flows according to the drag models, the numerical analysis of the muzzle velocity has been affected by the drag model.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.463-468
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• 1998

수직 관다발형 비등관에서의 밀도파 진동 및 유동 폭주형 이상유동 불안정성을 해석하기 위하여 선형화 기법 및 D-partition 방법론에 근거한 해석 코드(ALFS)를 개발하고 기존 실험자료 분석을 통해 코드의 예측 성능을 평가하였다. 그 결과 이상유동이 평형상태에 있는 것으로 가정하는 가장 단순한 모델인 HEM은 전반적으로 유동 불안정성 발생 시점의 열출력을 실험치보다 약 20% 정도 낮게 예측하였으며, 이상 유동의 속도 및 온도의 비평형 상태를 고려하는DEM과 DNEM에 의한 예측 결과는 7∼15%의 평균 오차 범위에서 실험 자료를 예측하는 것으로 나타났다.

• Journal of the Korean Society of Propulsion Engineers
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• v.23 no.6
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• pp.59-71
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• 2019

The numerical analysis of ablative thermal protection systems (TPS) for solid rockets has been carried out with various in-house codes since the 1960s. However, the application scope of commercial codes has been expanded by adding subroutines and user-defined functions (UDF) to codes such as Fluent, Marc, and ABAQUS. In the past, the flow, thermal response and structural analysis of TPS have been performed using separate approaches. Recently, research has been conducted to interrelate them. In this paper, the thermal response characteristics of thermal protection materials, the in-house codes for thermal response analysis, and the research trends of flow-thermal-structure analysis of TPS using commercial codes were reviewed.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.579-584
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• 1997

HP Workstation 및 IBM PC에서 사용 가능한 부수로 해석 코드 MATRA $\alpha$-버전을 개발하였다. 이 코드는 정확도 향상 및 사용자 편리를 위해 COBRA-IV-I코드에 비해 여러가지 기능들이 추가되었으며, 코드의 적용 범위를 신형원자로의 비정방형 집합체 노심에 확장할 수 있도록 압력손실 모형 등이 개선되었다. 또한 이상 유동장에서의 예측 정확도 향상을 위하여 부수로 잔의 횡방향 전달 모형을 개선하였다. 코드의 예측 성능을 평가하기 위해 세 중류의 집합체 유동분포 및 엔탈피 분포 실험 자료와 비교하였으며, 그 결과 기존의 COBRA-IV-I코드보다 향상된 결과를 보였다.

• Journal of Energy Engineering
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• v.15 no.1 s.45
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• pp.1-7
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• 2006

The multi-dimensional two-phase flow models were developed for analyze the multi-dimensional behaviors or nuclear systems. To verify the simple turbulence model, The single phase mixing problem in a rectangular slab was calculated and compared with the commercial CFD code results. That result shows a good agreement with the CFD result. And the RPI Air-water experiments were simulated to assess the two-phase turbulence model in the multi-dimensional component. The first calculated distribution or void-fraction is highly dispersed and diffusive. It was revealed that the main reason is undesirable stratification force in a horizontal stratified flow regimes. Therefore the horizontally stratified flow regime is deleted because the stratified flow regime is not expected in multi-dimensional flow. With the modification of the flow regime, the predicted flow patterns and void fraction profiles are in good agreement with the measured data.

• Journal of Energy Engineering
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• v.23 no.4
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• pp.95-105
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• 2014

The CUPID code has been developed for a transient, three-dimensional, two-phase flow analysis at a component scale. It has been validated against a wide range of two-phase flow experiments. Especially, to assess its applicability to single- and two-phase flow analyses in the Calandria vessel of a CANDU nuclear reactor, it was validated using the experimental data of the 1/4-scaled facility of a Calandria vessel at the STERN laboratory. In this study, a preliminary thermal-hydraulic analysis of the CANDU reactor moderator tank using the CUPID code is carried out, which is based on the results of the previous studies. The complicated internal structure of the Calandria vessel and the inlet nozzle was modeled in a simplified manner by using a porous media approach. One of the most important factors in the analysis was found to be the modeling of the tank inlet nozzle. A calculation with a simple inlet nozzle modeling resulted in thermal stratification by buoyance, leading to a boiling from the top of the Calandria tank. This is not realistic at all and may occur due to the lack of inlet flow momentum. To improve this, a new nozzle modeling was used, which can preserve both mass flow and momentum flow at the inlet nozzle. This resulted in a realistic temperature distribution in the tank. In conclusion, it was shown that the CUPID code is applicable to thermal-hydraulic analysis of the CANDU reactor moderator tank using the cost-effective porous media approach and that the inlet nozzle modeling is very important for the flow analysis in the tank.