• 한국소음진동공학회논문집
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• 제12권11호
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• pp.864-872
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• 2002

In this study, the effect of planform curvature on the stability of coupled flow/structure vibration is examined in transonic and supersonic flow regions. The aeroelastic analysis for the frequency and time domain is performed to obtain the flutter solution. The doublet lattice method(DLM) in subsonic flow is used to calculate unsteady aerodynamics in the frequency domain. For all speed range, the time domain nonlinear unsteady transonic small disturbance code has been incorporated into the coupled-time integration aeroelastic analysis (CTIA). Two curved wings with experimental data have been considered in this paper MSC/NASTRAN is used for natural free vibration analyses of wing models. Predicted flutter dynamic pressures and frequencies are compared with experimental data in subsonic and transonic flow regions.

• 한국전산유체공학회지
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• 제4권1호
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• pp.53-61
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• 1999

Two-dimensional, unsteady, incompressible and compressible Navier-Stokes codes are developed for the computation of the viscous turbulent flow over high-lift airfoils. The compressible code involves a conventional upwind-differenced scheme for the convective terms and LU-SGS scheme for temporal integration. The incompressible code with pseudo-compressibility method also adopts the same schemes as the compressible code. Three two-equation turbulence models are evaluated by computing the flow over single and multi-element airfoils. The compressible and incompressible codes are validated by predicting the flow around the RAE 2822 transonic airfoil and the NACA 4412 airfoil, respectively. In addition, both the incompressible and compressible code are used to compute the flow over the NLR 7301 airfoil with flap to study the compressible effect near the high-loaded leading edge. The grid systems are efficiently generated using Chimera overlapping grid scheme. Overall, the κ-ω SST model shows closer agreement with experiment results, especially in the prediction of adverse pressure gradient region on the suction surfaces of high-lift airfoils.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.3154-3165
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• 2022

During a loss-of-coolant accident (LOCA) in the pressurized water reactor (PWR), there is a possibility that high temperature and internal pressure of the fuel rods lead to ballooning of the cladding, which causes a partial blockage of flow area in a subchannel. Such flow blockage would influence the core coolant flow, thus affecting the core heat transfer during a reflooding phase and subsequent severe accident. However, most of the system analysis codes simulate the accident process based on the assumed channel blockage ratio, resulting in the fact that the simulation results are not consistent with the actual situation. This paper integrates the developed core Fuel Rod Thermal-Mechanical Behavior analysis (FRTMB) module into the self-developed severe accident analysis code ISAA. At the same time, the existing flow blockage model is improved to make it possible to simulate the change of flow distribution due to fuel rod deformation. Finally, the ISAA-FRTMB is used to simulate the QUENCH-LOCA-0 experiment to verify the correctness and effectiveness of the improved flow blockage model, and then the effect of clad ballooning on core heat transfer and subsequent parts of core degradation is analyzed.

• 한국유체기계학회 논문집
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• 제4권1호
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• pp.38-45
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• 2001

A commercial CFD code is used to compute the 3-D viscous flow field within the impeller of a centrifugal pump. Several preliminary numerical calculations are carried out to determine the influence of the parameters such as the grid systems, the numerical schemes, the turbulence models and the shape of the vaneless diffusers at the design flow rate. The results of the preliminary study are used for the calculation of the off-design flow conditions. The circumferentially averaged results such as the radial and tangential velocities, the exit flow angle, the slip factor, the static pressure and the total pressure are compared with the experimental data at the impeller exit to discuss the influence of the prescribed parameters.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2000년도 유체기계 연구개발 발표회 논문집
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• pp.305-311
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• 2000

A commercial CFD code is used to compute the 3-D viscous flow field within the impeller o( a centrifugal pump. Several preliminary numerical calculations are carried out to determine the influence of the parameters such as the grid systems, the numerical schemes, the turbulence models and the shape of the vaneless diffusers at the design flow rate. The results of the preliminary study are used for the calculation of the off-design flow conditions. The circumferentially averaged results such as the radial and tangential velocities, the exit flow angle, the slip factor, the static pressure and the total pressure are compared with the experimental data at the impeller exit to discuss the influence of the prescribed parameters.

• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2005년도 춘계 학술대회논문집
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• pp.153-158
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• 2005

Numerical simulations of two-dimensional steady incompressible lid-driven flow in a square cavity are presented to verify the validity of a new solution code(PowerCFD) with unstructured grids. The code uses the non-staggered(collocated) grid approach which is very popular for incompressible flow analysis because of its numerical efficiency on the curvilinear or unstructured grids. Solutions are obtained for configurations with a Reynolds number as high as 10,000 with both rectangular and hybrid types of unstructured grid mesh. Interesting features of the flow are presented in detail and comparisons are made with benchmark solutions found in the literature. It is found that the code is capable of producing accurately the nature of the lid-driven cavity flow at high Reynolds numbers.

• Nuclear Engineering and Technology
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• 제17권4호
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• pp.256-266
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• 1985

냉각재 유량상실 사고가 가압경수형 원자로인 고리 1호기에 대하여 해석되었다. 냉각재 유량 상실 사고는 그 심각도에 따라 다음과 같이 3가지로 분류된다. 즉, 일부 유량 상실사고, 완전 유량 상실 사고, 그리고 펌프 축 고착 사고이다. 사고 해석은 계통 과도 현상 및 평균 노심분석, DNBR 계산, 그리고 고온점 분석의 3단계로 수행된다. 원자로 계통과도 현상 코드인 KTRAN이 본 사고를 빠른 시간에 모사할 수 있도록 개발되었다. DNBR계산을 위해서는 열수력학 코드인 SCAN및 COBRA IV-I가 채택되었으며, 고온점 분석을 위해서는 연료봉 과도 현상 코드인 LTRAN이 쓰였다. 이러한 전산코드 시스템은 과도 현상 해석에 빨리 응답하여야 한다. 왜냐하면 사고가 발생한 후 수 초안에 심각한 상태에 이르기 때문이다. 불행히도 KTRAN코드에 의하여 이러한 목적은 충족되지 않았다. 그러나 다른 계통 해석 코드에 비하여 잔은 계산 시간에도 불구하고 KTRAN에 의한 계산 결과는 FSAR의 결과와 전반적으로 잘 일치함으로써 KTRAN코드가 사고 해석에 유용함이 밝혀졌다.

• Nuclear Engineering and Technology
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• 제46권5호
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• pp.641-654
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• 2014

A new computer code, named CORONA (Core Reliable Optimization and thermo-fluid Network Analysis), was developed for the core thermo-fluid analysis of a prismatic gas cooled reactor. The CORONA code is targeted for whole-core thermo-fluid analysis of a prismatic gas cooled reactor, with fast computation and reasonable accuracy. In order to achieve this target, the development of CORONA focused on (1) an efficient numerical method, (2) efficient grid generation, and (3) parallel computation. The key idea for the efficient numerical method of CORONA is to solve a three-dimensional solid heat conduction equation combined with one-dimensional fluid flow network equations. The typical difficulties in generating computational grids for a whole core analysis were overcome by using a basic unit cell concept. A fast calculation was finally achieved by a block-wise parallel computation method. The objective of the present paper is to summarize the motivation and strategy, numerical approaches, verification and validation, parallel computation, and perspective of the CORONA code.

• 한국추진공학회지
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• 제15권6호
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• pp.38-46
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• 2011

점화제 주입 특성을 모사할 수 있는 2차원 이상유동의 강내탄도 해석코드 개발하였다. 장약인 추진제의 연소 해석을 위해 Eulerian-Lagrangian 접근법과 LSHUS 기법을 적용하였다. 탄자의 이동에 따른 이동경계면의 해석을 위해 Ghost Cell Extrapolation method를 사용하였다. 개발된 2차원 강내탄도 해석코드는 무차원 강내탄도 해석 코드인 IBHVG2와 기존에 개발된 1차원 강내탄도 해석코드와 비교 검증하였다. 항력식에 따른 이상유동의 비교에서 항력식이 탄자탈출속도의 수치적 해석에 영향을 주는 것을 확인하였다.

• 한국컴퓨터정보학회논문지
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• 제16권6호
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• pp.51-59
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• 2011

국내에는 바이너리 코드에 대한 분석 기술이 많이 부족한 상태이다. 일반적으로 컴퓨터에 설치되는 실행 파일은 소스 코드 없이 단지 바이너리로 된 실행 파일만 주어지는 경우가 대부분이다. 따라서 위험하거나 알 수 없는 동작이 수행되는 경우가 발생할 수 있다. 따라서 이 논문에서는 바이너리 수준에서 정적으로 프로그램 분석을 수행할 수 있는 프레임워크를 설계 및 구현한다. 이 논문에서는 바이너리 실행 파일로부터 실행 순서 및 제어 흐름 등의 정보를 표현할 수 있는 제어 흐름 그래프를 작성하여 실행 흐름과 위험한 함수의 호출 여부를 동시에 파악하고 개발된 프레임워크를 통해 바이너리 파일에 대한 분석을 용이하게 한다.