• 에너지공학
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• 제24권4호
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• pp.159-165
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• 2015

본 논문에서는 EMP 차폐를 위한 WBC 배열이 설치된 대형 비상발전기 연도의 최적형상을 결정하는 것을 목표로 연구를 진행하였다. 시뮬레이션은 WBC 배열의 외부관경이 800, 850, 900, 1050mm 및 1250mm를 대상으로 하였으며 기본연도와의 접속길이를 150, 300, 450 mm, 연도의 유속은 15, 20, 25m/s로 하였다. EMP 차폐를 위한 WBC 배열을 연도에 설치하는 경우 WBC 배열의 외부관경, Main 연도와의 접속길이가 배기가스 흐름에 큰 영향을 미치는 것으로 나타났다. WBC 배열의 외부관경이 1050, 1250mm이고 접속길이가 300, 450mm이면 도파관 배열에서 배기가스의 평균속도와 최고속도를 만족시키는 것으로 나타났다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2001년도 ICCAS
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• pp.147.4-147
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• 2001

This work presents the robust controller and the LQG/LTR controller for the stewart platform. To simplify the dynamics we combine equation of the stewart platform and linearized one of hydraulic actuators not considered condensability of the fluid. Through the connection of two dynamic equations we can omit force feedback process of actuators and design controllers for the whole system. We applied two controllers on the stewart platform and show the adequacy controllers through the result of simulation and experiment.

• Steel and Composite Structures
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• 제26권6호
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• pp.793-808
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• 2018

In this study, the seismic performance of the connections between L-shaped columns composed of concrete-filled steel tubes (L-CFST columns) and H-beams used in high-rise steel frame structures was investigated. Seven full-scale specimens were tested under quasi-static cyclic loading. The variables studied in the tests included the joint type, the axial compression ratio, the presence of concrete, the width-to-thickness ratio and the internal extension length of the side plates. The hysteretic response, strength degradation, stiffness degradation, ductility, plastic rotation capacity, energy dissipation capacity and the strain distribution were evaluated at different load cycles. The test results indicated that both the corner and exterior joint specimens failed due to local buckling and crack within the beam flange adjacent to the end of the side plates. However, the failure modes of the interior joint specimens primarily included local buckling and crack at the end plates and curved corners of the beam flange. A design method was proposed for the flexural capacity of the end plate connection in the interior joint. Good agreement was observed between the theoretical and test results of both the yield and ultimate flexural capacity of the end plate connection.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4373-4391
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• 2022

Marine reactor systems experience platform movement, and therefore, the system thermal-hydraulic analysis code needs to reflect the motion effect on the fluid to evaluate reactor safety. A moving reactor model for MARS-KS was developed to simulate the hydrodynamic phenomena in the reactor under motion conditions; however, its applicability does not cover the MULTID component used in multidimensional flow analyses. In this study, a moving reactor model is implemented for the MULTID component to address the importance of multidimensional flow effects under dynamic motion. The concept of the volume connection is generalized to facilitate the handling of the junction of MULTID. Further, the accuracy in calculating the pressure head between volumes is enhanced to precisely evaluate the additional body force. Finally, the Coriolis force is modeled in the momentum equations in an acceleration form. The improvements are verified with conceptual problems; the modified model shows good agreement with the analytical solutions and the computational fluid dynamic (CFD) simulation results. Moreover, a simplified gravity-driven injection is simulated, and the model is validated against a ship flooding experiment. Throughout the verifications and validations, the model showed that the modification was well implemented to determine the capability of multidimensional flow analysis under ocean conditions.

• International Journal of Control, Automation, and Systems
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• 제3권3호
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• pp.493-501
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• 2005

A power plant simulation tool ('PowerSim') has been developed with 10 years experience from the development of a plant simulator for efficient modeling of a power plant. PowerSim is the first developed tool in Korea for plant simulation with various plant component models, instructor station function and the Graphic Model Builder (GMB). PowerSim is composed of a graphic editor using general purpose design software, a netlist converter, component models, the scheduler, Instructor Station and an executive. The graphic editor generates a netlist that shows the connection status of the various plant components from the Simdiagram, which is drawn by Icon Drag method supported by GUI environment of the PowerSim. Netlist Converter normalizes the connection status of the components. Scheduler makes scheduling for the execution of the device models according to the netlist. Therefore, the user makes Simdiagram based on the plant Pipe and Instrument Drawing (P&ID) and inputs the plant data for automatic simulating execution. This paper introduces Graphic Model Builder (GMB), instructor station, executive and the detailed introduction of thermal-hydraulic modeling. This paper will also introduce basic ideas on how the simulation Diagram, based on netlist generated from general purpose design software, is made and how the system is organized. The developed tool has been verified through the simulation of a real power plant.

• 한국가스학회지
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• 제9권3호
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• pp.32-37
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• 2005

LP가스나 도시가스시설의 저압 호스 체결에서 견고함과 기밀성을 높이기 위해 호스밴드를 사용한다. 본 연구에서는 호스밴드의 성능 파악과 안전한 체결 거리의 제시를 위하여 호스밴드에 대한 내압강도와 당김력을 측정하였다. 호스밴드의 체결력은 스프링밴드 보다는 귀형밴드에서 높게 나타났으며 최적의 호스밴드 체결거리는 호스접속 끝단부로부터 1${\~}$2 mm일 때에 우수한 것으로 파악되었다.

• Advances in Energy Research
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• 제5권2호
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• pp.91-105
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• 2017

Thermal hydraulic (TH) analysis of nuclear power reactors is utmost important. In this way, the numerical codes that preparing TH data in reactor core are essential. In this paper, a subchannel analysis of a Russian pressurized water reactor (WWER1000) core with enhanced numerical code is carried out. For this, in fluid domain, the mass, axial and lateral momentum and energy conservation equations for desired control volume are solved, numerically. In the solid domain, the cylindrical heat transfer equation for calculation of radial temperature profile in fuel, gap and clad with finite difference and finite element solvers are considered. The dependence of material properties to fuel burnup with Calza-Bini fuel-gap model is implemented. This model is coupled with Isotope Generation and Depletion Code (ORIGEN2.1). The possibility of central hole consideration in fuel pellet is another advantage of this work. In addition, subchannel to subchannel and subchannel to rod connection data in hexagonal fuel assembly geometry could be prepared, automatically. For a demonstration of code capability, the steady state TH analysis of a the WWER1000 core is compromised with Thermal-hydraulic analysis code (COBRA-EN). By thermal hydraulic parameters averaging Fuel Assembly-to-Fuel Assembly method, the one sixth (symmetry) of the Boushehr Nuclear Power Plant (BNPP) core with regular subchannels are modeled. Comparison between the results of the work and COBRA-EN demonstrates some advantages of the presented code. Using the code the thermal modeling of the fuel rods with considering the fission gas generation would be possible. In addition, this code is compatible with neutronic codes for coupling. This method is faster and more accurate for symmetrical simulation of the core with acceptable results.

• 한국수자원학회:학술대회논문집
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• 한국수자원학회 2017년도 학술발표회
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• pp.329-329
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• 2017

In this study attempted to evaluate the stability of the protection methods by examining hydraulic characteristics of the area around the point in which marine cable protector is installed such as surf zone occurrence point of shore-end submarine cables suitable for coastal marine environmental conditions, flow rate t the tope of the protector and maximum wave height, and to provide basic data for the selection of the optimal protection method. In performing hydraulic model experiments, the topography of submarine cable installation location was reproduced in 2-D sectional channel, and models appropriate for experimental scale and similitude law were produced and installed for each condition of submarine cables and protectors. Since the topography and submarine cable protectors were reproduced and installed in 2-D sectional channel, the exact reproduction of surf and transformation in shallow water zone was possible, and thus the physical properties could be clearly analyzed. For stability review, an experiment to examine the stability was conducted using a wave maker with 50-year frequency design waves as target, and wave height and cycles were applied based on the approximate lowest low water level(Approx. L.L.W), which is the most dangerous in submarine cable protection methods. As for experimental time, typhoon passing time in summer (about 3 hours) was applied, and wave patterns and deviation ratio of the submarine cable protector were investigated after making irregular waves corresponding to design waves. In addition, current meter and wave height meter were installed at the installation location of the submarine cable protector, and the flow rates and wave height at the top of the protector were measured and analyzed to review hydraulic properties.

• 지질공학
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• 제16권1호
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• pp.69-83
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• 2006

본 연구는 지하유류저장공동 굴착 시 조사된 단열체계 및 수리 인자를 토대로 투수성구조영역과 수리암반영역으로 세분화하여 연구지역의 불규칙하고 복잡한 지하수유동체계를 해석해 보고자 하였다. 지하공동 내에서 확인된 단열분포특성과 지하공동굴착과 동시에 지표관측공 28개를 통해 측정된 지하수위 및 수평수벽공 95개와 수직수벽공 63개에 의해 일별로 계측된 압력 및 주입량을 통해 연구지역은 지하수의 방벽역할을 하는 3개의 투수성구조영역과 4개의 수리암반영역으로 구분이 가능하였다. 공동심도에 발달된 투수성 구조는 국지적 큰 규모 단열대인 NE-1과 2개의 국지규모 단열대로 구성되고 있으나, 수리암반영역은 국지규모 단열대에 의하여 4개 영역으로 구분된다. FZ-2 구조대와 인접한 수리암반영역 Domain-A와 B는 수평수벽공의 초기압이 최대 약 $15kg/cm^2$까지 높으며, 지하공동 굴착 시 상 하부의 지하수위변화의 차이가 $10\sim40m$로 상 하부의 수리적 연결성이 양호한 것으로 평가된다. 반면, FZ-1 구조대와 인접한 Domain-C와 D는 이중수위측정 시설 설치시 상부와 하부의 지하수위차는 최대 약 120 m로 매우 크게 나타났으며, 상부 지하수는 공동굴착 시 수위 가 크게 변화하지 않았다. Domain C, D의 하부암반의 수리 전도도$(7.2X10^{-10}m/sec)$는 상대적으로 낮은 지하수 함양량의 원인을 제공하고 있으며, 연속체개념 의 지하수유동모델링을 통해 계산된 4개 영역의 함양량은 연구지역의 20년간 평균 강수량(1,356 mm/year)의 2%로 계산되었다.

• 한국지반환경공학회 논문집
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• 제21권4호
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• pp.19-30
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• 2020

본 연구는 하천 보축제체 내부를 관통하여 설치되는 배수통문 구조물 연결부에서 누수가 발생하는 경우 구조물 측면의 침투 특성을 파악하고 이러한 측면 침투 거동에 따른 파이핑 등이 제체 안정에 미치는 영향을 분석한 수치해석적 연구이다. 측면 침투 거동을 고려하기 위해 동일한 모델에 대해 2차원 및 3차원 수치해석을 수행하였다. 그리고 측면 침투의 영향을 분석하고 수치 해석의 타당성을 평가하고자 하였다. 연구 결과, 제외지에 수문이 위치한 조건에서 누수가 발생하고 측면 침투를 고려하는 경우 구조물 누수지점 인근의 최대간극수압은 누수가 발생하지 않는 정상적인 침투 상태에 비해 절반 정도로 감소하였다. 특히 측면 침투를 고려하지 않는 경우 구조물 하부에서 과도한 간극수압 변화를 보였다. 구조물 상부와 하부의 동수경사는 고수위로 수위가 상승하면서 한계동수경사보다 큰 동수경사를 나타내고 있어 장기간 파이핑에 취약할 것으로 판단된다. 제내지에 수문이 위치하고 측면침투를 고려하지 않는 경우 동수경사와 침투유속 등 침투수의 영향은 측면침투를 고려하는 경우에 비해 과소하게 해석되었다. 수문이 제외지에 위치하고 누수가 발생하여 파이핑 발생 또는 제체 재료 유실이 우려되는 경우 측면 침투를 무시하게 되면 최대 동수경사는 상대적으로 작게 나타났다. 그리고 한계동수경사를 초과하는 기간도 짧은 시간대로 해석되었다. 결과적으로 측면 침투를 무시하게 되면 파이핑 발생 가능성을 과소하게 평가할 수 있어 주의해야 할 것으로 판단된다.