• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 추계학술대회 논문집 전기기기 및 에너지변환시스템부문
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• pp.30-32
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• 2001

There are many difficult problems in analyzing the flow characteristics in a high voltage circuit breaker such as shock wave and complex geometries, which may be either static or in relative motion. Although a variety of mesh generation techniques are now available, the generation of meshes around complicated, multi-component geometries like a gas circuit breaker is still a tedious and difficult task for the computational fluid dynamics. This paper presents the CFD program for analyzing the compressible flow fields in a high voltage gas circuit breaker using the Cartesian cut-cell method based on the CFD-CAD integration, which can achieve the accurate representation of the geometry designed by a CAD tools. This technique is frequently satisfied, and it will be almost universally so in the future, as the CFD-CAD traffic increase.

• Spatial Information Research
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• 제15권4호
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• pp.363-370
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• 2007

본 연구는 지형참조항법(TRN; Terrain Referenced Navigation)에 근거하는 헬리콥터 항법 시스템을 위한 기본 알고리즘을 개발하기 위해 수행되었다. 현재 본 연구에 위성 항법장치(GPS; Global Positioning System)로부터의 정보(X, Y, Z 좌표)는 비행체가 항로를 비행하는 중 매 92.8m의 수평거리로 환산하여 수신되는 것으로 가정하였다. 비행체는 3차원 직교 좌표 체계(Cartesian coordinate system)로 표현되는 수치지형모델(DTM; Digital Terrain Model)상에서 시점(Origination)-종점(Destination) 분석 기법에 의해 항로를 결정한다. 본 시스템은 우선 조종사에게 지형의 사전 인식을 위해 시점-종점 주변 3차원 지형도와 항로의 종단면도를 보여준다. 본 시스템은 직접적인 지상 충돌을 피하기 위해 지형 여유 층면(terrain clearance floor)의 개념을 도입, 기복 지형 표면에 일정 높이의 완충 공간을 설정한다. 만약 비행체가 항행 중 완충 공간에 접근하게 되면 본 시스템은 실시간으로 즉시 경고음과 메시지를 발한다(Matlab 메뉴를 사용하였음). 물론 헬리콥터의 이착륙 시에는 불필요한 경고를 발생시키지 않기 위해 완충 공간 조정은 가능하다. 수치지형모델은 (주)첨성대가 확보하고 있는 3초 간격의 DTM을 채택, 작성하였다.

• 대한기계학회논문집B
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• 제28권4호
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• pp.433-440
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• 2004

Since the numerical analysis was adopted in the mold design, lots of computational methods have been proposed for the simulations of casting processes for the various shaped molds. Today, it is possible to simulate the filling and solidification processes of most casts using the VOF technique. Though the three-dimensional numerical model based on the Cartesian coordinate system can be applied to any shape of cast, it becomes very inefficient when the three-dimensional model is applied to the cast of axi-symmetrical shape since the control volume includes at least 11 of the physical model. In addition, the more meshes should be distributed along the circumferential boundaries of curved shape in the Cartesian coordinate system fur the better results, while such curved circumferential boundary does not need to be considered in the two-dimensional cylindrical coordinate system. This motivates the present study i.e. developing a two-dimensional numerical model for the axi-symmetrically shaped casts. The SIMPLER algorithm, the VOF method, and the equivalent specific heat method have been adopted in the combined algorithm for the flow calculation, the free surface tracking, and the phase change heat transfer, respectively. The numerical model has been applied to the casting process of a pulley, and it was proven that the mesh and time effective calculation was accomplished comparing to the calculation using three-dimensional model.

• 대한토목학회논문집
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• 제26권2A호
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• pp.319-326
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• 2006

본 논문에서는 가정응력장과 수정된 형상함수를 이용한 새로운 8절점 hybrid/mixed 평면응력요소를 제시하였다. 가정응력장은 비적합 변위모드로부터 유도하였으며, 이는 요소의 찌그러짐에 대한 민감도를 완화시켜준다. 그리고 Cartesian 좌표계에서 9절점 등매개변수 요소와 동일한 조건하에서 2차 변위를 정확히 보간하도록 수정한 형상함수를 사용하였다. 제시한 8절점 hybrid/mixed 평면응력요소(HQ8-$14{\beta}$)의 수치해석에 대한 정확성과 효율성을 검증하기 위해 기존의 참고문헌들과 비교, 분석하였다. 그 결과 본 논문에서 제시한 요소는 요소가 왜곡된 경우를 포함하여 우수한 성능을 보였다.

• Journal of Mechanical Science and Technology
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• 제18권6호
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• pp.1026-1035
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• 2004

An immersed boundary method for solving the Navier-Stokes and thermal energy equations is developed to compute the heat transfer over or inside the complex geometries in the Cartesian or cylindrical coordinates by introducing the momentum forcing, mass source/sink, and heat source/sink. The present method is based on the finite volume approach on a staggered mesh together with a fractional step method. The method of applying the momentum forcing and mass source/sink to satisfy the no-slip condition on the body surface is explained in detail in Kim, Kim and Choi (2001, Journal of Computational Physics). In this paper, the heat source/sink is introduced on the body surface or inside the body to satisfy the iso-thermal or iso-heat-flux condition on the immersed boundary. The present method is applied to three different problems : forced convection around a circular cylinder, mixed convection around a pair of circular cylinders, and forced convection around a main cylinder with a secondary small cylinder. The results show good agreements with those obtained by previous experiments and numerical simulations, verifying the accuracy of the present method.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1347-1360
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• 2009

A multi-dimensional component for the thermal-hydraulic system analysis code, MARS, was developed for a more realistic three-dimensional analysis of nuclear systems. A three-dimensional and two-fluid model for a two-phase flow in Cartesian and cylindrical coordinates was employed. The governing equations and physical constitutive relationships were extended from those of a one-dimensional version. The numerical solution method adopted a semi-implicit and finite-difference method based on a staggered-grid mesh and a donor-cell scheme. The relevant length scale was very coarse compared to commercial computational fluid dynamics tools. Thus a simple Prandtl's mixing length turbulence model was applied to interpret the turbulent induced momentum and energy diffusivity. Non drag interfacial forces were not considered as in the general nuclear system codes. Several conceptual cases with analytic solutions were chosen and analyzed to assess the fundamental terms. RPI air-water and UPTF 7 tests were simulated and compared to the experimental data. The simulation results for the RPI air-water two-phase flow experiment showed good agreement with the measured void fraction. The simulation results for the UPTF downcomer test 7 were compared to the experiment data and the results from other multi-dimensional system codes for the ECC delivery flow.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1079-1087
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• 2021

NTP-ERSN is a package developed for solving the multigroup form of the discrete ordinates, characteristics and collision probability of the Boltzmann transport equation in one-dimensional cartesian geometry, by combining pin cells. In this work, C5G7 MOX benchmark is used to verify the accuracy and efficiency of NTP-ERSN package, by treating reactor core problems without spatial homogenization. This benchmark requires solutions in the form of normalized pin powers as well as the vectors and the eigenvalue. All NTP-ERSN simulations are carried out with appropriate spatial and angular approximations. A good agreement between NTP-ERSN results with those obtained with OpenMC calculation code for seven energy groups. In addition, our studies about angular and mesh refinements are carried out to produce better quality solution. Moreover, NTP-ERSN GUI has also been updated and adapted to python 3 programming language.

• 대한전자공학회논문지TC
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• 제45권12호
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• pp.58-65
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• 2008

본 논문에서는 MANET(Mobile Ad hoc Network)에서 가상 위치 기반 라우팅을 위한 GDHT(Geographic Distributed Hash Table)를 적용하는 방법을 제안한다. 기존의 GDHT는 저장하고자할 데이터를 가상 2차원 직교좌표계에 균일하게 매핑 하였다. 그러나, 위치 기반 라우팅을 사용하는 네트워크에서 노드의 분포는 기존 GDHT의 가상 공간과 다르게 분포한다. 따라서, 기존의 GDHT를 바로 적용할 경우, 많은 데이터들이 네트워크의 외곽 또는 특정 노드에 위치하게 된다. 이는 데이터 또는 서비스 검색 거리 및 시간을 늘리는 문제를 발생시킨다. 또한, BVR(Beacon Vector Routing)이나 LCR(Logical Coordinate Routing) 좌표 요소 사이에는 서로 연관관계가 있기 때문에 일반적인 해쉬 함수를 적용할 경우, 존재할 수 없는 좌표에 매핑 될 가능성이 높아진다. 이러한 문제를 해결하기 위하여, 데이터들의 분포를 제어할 수 있도록 하고 좌표 요소 사이의 연관관계가 반영될 수 있는 "Geographic 해쉬 함수"를 제안한다. 분석과 시뮬레이션을 통하여 제안하는 방법이 데이터 분포를 제어할 수 있고, 데이터 검색 성능을 향상시킴을 보인다.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2230-2245
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• 2023

KANT (KAIST Advanced Nuclear Tachygraphy) is a PWR core simulator recently developed at Korea Advance Institute of Science and Technology, which solves three-dimensional steady-state and transient multigroup neutron diffusion equations under Cartesian geometries alongside the incorporation of thermal-hydraulics feedback effect for multi-physics calculation. It utilizes the standard Nodal Expansion Method (NEM) accelerated with various Coarse Mesh Finite Difference (CMFD) methods for neutronics calculation. For thermal-hydraulics (TH) calculation, a single-phase flow model and a one-dimensional cylindrical fuel rod heat conduction model are employed. The time-dependent neutronics and TH calculations are numerically solved through an implicit Euler scheme, where a detailed coupling strategy is presented in this paper alongside a description of nodal equivalence, macroscopic depletion, and pin power reconstruction. For validation of the steady, transient, and depletion calculation with pin power reconstruction capacity of KANT, solutions for various benchmark problems are presented. The IAEA 3-D PWR and 4-group KOEBERG problems were considered for the steady-state reactor benchmark problem. For transient calculations, LMW (Lagenbuch, Maurer and Werner) LWR and NEACRP 3-D PWR benchmarks were solved, where the latter problem includes thermal-hydraulics feedback. For macroscopic depletion with pin power reconstruction, a small PWR problem modified with KAIST benchmark model was solved. For validation of the multi-physics analysis capability of KANT concerning large-sized PWRs, the BEAVRS Cycle1 benchmark has been considered. It was found that KANT solutions are accurate and consistent compared to other published works.

• Nuclear Engineering and Technology
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• 제25권1호
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• pp.51-62
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• 1993

입자수송방정식의 각분할해석법에서 입자흐름방향을 묘사하는 각방향에 대한 각분할집합이 고정된 값이 아니고 각입자속으로 조종되는 각요소법에 근거하여 방사선차폐해석 목적의 전산프로그램(TDET)를 2차원직각좌표계에 대해서 개발하였다. 산란선원항의 각의존성은 Spherical Harmonics Series Expansion으로 해석하였고 입자의 에너지 의존성은 다중에너지군으로 처리하였다. 3 종류의 Benchmark 시험을 통해서 TDET 프로그램을 검증하였다. 평판형 등방적 선원을 가진 사방흡수체에 대한 해석에서 TDET 해석결과가 MORSE-CG 해석결과에 잘 일치하고. 각분할법으로 해석할때 나타나는 Ray effect를 DOT 4.3 보다 잘 치 유하고 있다. 차폐체 내에 좁은 Vacuum duct가 있는 문제의 해석에서 TDET는 MORSE-CG와 마찬가지로 duct를 통한 streaming leak-age에 대해서 분명하고 현저한, 그리고 DOT 4.3보다 매우 훌륭한 해석결과를 보여주고 있다. 원자로차폐구조물 규모에 대해, 2 에너지군, 등방적 산란 및 선형 비등방 산란의 경우에 대해서 해석한 결과 각분할법으로 계산하여 제시하고 있는 기준치에서는 여러 mesh들에 걸쳐 넓은 규모의 Ray effect를 나타내고 있는데, TDET에 의한 해석결과에서는 이웃 mesh들 간에 미세한 Ray effect를 나타내고 있다.