• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.158-158
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• 1998

• 정보처리학회논문지:소프트웨어 및 데이터공학
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• 제3권2호
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• pp.65-72
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• 2014

변경 결합도는 두 요소들 사이의 향후 변경 연관성을 알려준다. 만약, 소스 파일들이 자주 함께 변경된다면, 그 소스 파일들의 변경 결합도는 높다고 볼 수 있으며, 나중에 다시 함께 변경될 확률이 높다. 일반적으로 소스 파일들 사이의 변경 결합도는 공통 변경 횟수에 기반하여 정의되었다. 그런데 연관성이 낮은 변경들이 일괄적으로 함께 커밋되는 경우, 즉 뒤얽힌 변경(tangled change)과 같은 경우들이 빈번히 발생한다. 따라서 함께 변경된 횟수만으로 소스 파일의 변경 결합도를 결정하는 것은 한계가 있다. 본 논문에서는 기존의 방법을 보완하기 위해, 소스 파일의 변경 시간뿐 아니라 소스 코드 변경 유형의 유사성을 함께 고려하는 것을 제안하였다. 이를 위하여, 우선 추출된 변경 유형 정보를 이용하여 변경 유형 빈도 벡터를 정의하고, 다음에 코사인 유사도 측정을 통해서 각 소스 파일 버전에서 적용된 코드 변경 유사성을 계산한다. 이후 Eclipse 프로젝트인 JDT와 CDT에 대한 사례 연구를 통해 제안된 방법의 효용성을 보였다.

• 콘크리트학회논문집
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• 제28권2호
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• pp.187-196
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• 2016

KBC2009에 의하면 특수전단벽과 연결되는 폭이 좁고 춤이 높은 연결보는 대각선 다발철근 보강을 실시해야 한다. 그러나 대각선 다발 철근의 사용은 시공성과 경제성에 부정적인 영향을 미칠 것으로 예상된다. 이에 본 연구에서는 4개의 서로 다른 상세를 갖는 연결보를 대상으로 주기하중 재하 실험을 실시하여 각각의 성능을 평가하였다. 또한 그 실험결과를 바탕으로 하여 특수전단벽과 연결보로 이루어진 병렬전단벽 구조시스템을 구성하여 FEMA P695에 따른 방법론으로 내진성능평가를 실시하였다.

• 한국자동차공학회논문집
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• 제11권6호
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• pp.51-58
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• 2003

A cycle simulation method is developed by coupling a commercial code, Ricardo's WAVE, with the SENKIN code from CHEMKIN packages to predict combustion characteristics of an HCCI engine. By solving detailed chemical kinetics the SENKIN code calculates the combustion products in the combustion chamber during the valve closing period, i.e. from IVC to EVO. Except the combustion chamber during the valve closing period the WAVE code solves thermodynamic status in the whole engine system. The cycle simulation of the complete engine system is made possible by exchanging the numerical solutions between the codes on the coupling positions of the intake port at IVC and of the exhaust port at EVO. This method is validated against the available experimental data from recent literatures. Auto ignition timing and cylinder pressure are well predicted for various engine operating conditions including a very high ECR rate although it shows a trend of sharp increase in cylinder pressure immediate after auto ignition. This trend is overpredicted especially for EGR cases, which may be due to the assumption of single-zone combustion model and the limit of the chemical kinetic model for the prediction of turbulent air-fuel mixing phenomena. A further work would be needed for the implementation of a multi-zone combustion model and the effect of turbulent mixing into the method.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3133-3150
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• 2021

This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for a full-core pin-by-pin burnup calculation for the ninth operating cycle of the Temelín II VVER-1000 plant, which starts from a fresh core, are presented and assessed using experimental data. A good agreement is found comparing the critical boron concentration and a set of pin-level neutron flux profiles against measurements. In addition, the calculated axial and radial power distributions match closely the values reported by the core monitoring system. To demonstrate the modeling capabilities of the three-code coupling, pin-level neutronic, thermalhydraulic and thermomechanic results are shown as well. These studies are encompassed in the final phase of the EU Horizon 2020 McSAFE project, during which the Serpent-SUBCHANFLOW-TRANSURANUS system was developed.

• 한국전산유체공학회지
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• 제16권2호
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• pp.30-48
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• 2011

A three-dimensional thermal-hydraulic code, CUPID, has been developed for the analysis of transient two-phase flows at component scale. The CUPID code adopts a two-fluid three-field model for two-phase flows. A semi-implicit two-step numerical method was developed to obtain numerical solutions on unstructured grids. This paper presents an overview of the CUPID code development and assessment strategy. The governing equations, physical models, numerical methods and their improvements, and the systematic verification and validation processes are discussed. The code couplings with a system code, MARS, and, a three-dimensional reactor kinetics code, MASTER, are also presented.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2002년도 봄 학술발표회 논문집
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• pp.437-442
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• 2002

The purpose of this study is to investigate nonlinear behavior and estimate ultimate resistance of the wall structure against seismic loading. Experimental data for RC coupling elements are used for specifying the strength deterioration and stiffness degradation factor of hysteretic model. Modified coupling element models are used in the push over analysis and time history analysis. In the time history analysis, three earthquake waves are used in the analysis and their peak ground accelerations are changed to be 0.2g. The conclusions of this study are as follows : (1) In the push over analysis, yielding of coupling elements occurred at lower story with small story drift ratio as 0.3%. (2) In the time history analysis, the story drift ratio is sufficient for the requirement of Korean Code, But coupling elements at most stories of the buildings occurred yielding. i. e. the earthquake resistant capacity of shear wall structures is not sufficient at 0.2g.

• Nuclear Engineering and Technology
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• 제51권7호
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• pp.1776-1783
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• 2019

To accurately analyze the accidents in nuclear reactors, a thermohydraulic-neutronic coupling calculation is required to solve fluid dynamics and nuclear reactor kinetics equations in fine cells simultaneously and evaluate the local effects of neutronic and thermohydraulic parameters on each other. In the present study, a 3D thermohydraulic-neutronic coupling model is developed, validated and then applied for Isfahan MNSR (Miniature Neutron Source reactor) safety analysis. The proposed model is developed using FLUENT software and user defined functions (UDF) are applied to simulate the neutronic behavior of MNSR. The validation of the proposed model is first evaluated using 1mk reactivity insertion experiment into Isfahan MNSR core. Then, the developed coupling code is applied for a design basis accident (DBA) scenario analysis with the insertion of maximum allowed cold core reactivity of 4 mk. The results show that the proposed model is able to predict the behavior of the reactor core under normal and accident conditions with a good accuracy.

• 한국지진공학회논문집
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• 제17권6호
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• pp.271-278
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• 2013

The hysteretic behavior of diagonal reinforced coupling beams is excellent during earthquakes. However, construction of the diagonal reinforced coupling beams is difficult due to complex reinforcement details required by current code procedures (ACI 318-11). Due to the detail requirement, reinforcement congestion and interference among transverse reinforcement always occur during construction field. When the aspect ratio of the beam is large, the interference of reinforcement becomes more serious. The objective of this paper is to simplify the reinforcement details of slender coupling beams by reducing transverse reinforcement around the beam perimeter. For this purpose, high- performance fiber reinforced cementitious composites are used for making coupling beams. Experiments were conducted using three specimens having aspect ratio 3.5. Test results showed that HPFRCC coupling beams with half the transverse reinforcement required by ACI 318-11 provided identical seismic capacities to the corresponding coupling beams having requirement satisfying the requirement specified in ACI 318-11.

• 한국정보과학회논문지:소프트웨어및응용
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• 제37권10호
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• pp.773-778
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• 2010

국제 웹 어플리케이션 보안 연구 단체(OWASP)는 2007년에 이어 2010년에도 취약점 대부분이 사용자의 외부 데이터 입력에 기인한 것으로 발표했다. 이러한 오염된 입력 데이터는 실행 시점에서 결정되기 때문에 동적인 취약점 분석이 필요하다. 동적 분석 방법은 주로 실행 시점의 데이터 분석이나 경로 흐름 분석을 위해 인스트루먼트를 코드 내에 삽입 한다. 하지만 직접적인 코드의 삽입은 관리와 확장이 어려워 분석 범위와 대상이 증가할 때 마다 코드 조각들이 흩어지게 된다. 게다가 인스트루먼트 모듈과 시험 대상 모듈 간의 결합도가 높아진다. 따라서 개발이나 유지보수 단계에서 삽입한 분석 코드를 수정하거나 확장하는데 많은 노력이 필요하게 된다. 본 논문은 이러한 문제점을 해결하기 위해 AOP를 이용하여 취약점을 하나의 관심사로 분류함으로써 결합도의 증가 없이 삽입, 삭제와 유연한 확장이 용이한 방법을 제안한다.