• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2005년도 봄학술 발표회 논문집(I)
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• pp.479-482
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• 2005

The concrete box girder members are extensively used as a superstructure in bridge construction. The load carrying capacity of concrete box girders in lateral direction is generally influenced by the sizes of haunch and web. The internal upper decks are restrained by the webs and exhibit strength enhancement due to the development of aching action. The current codes do not have generally consider the arching action of deck slab in the design because of complexity of the behavior. However, there are significant benefits in utilizing the effects of arching action in the design of concrete members. The main objective of this paper is to propose a rational method to predict the ultimate load of deck slab by considering various haunch sizes and web restraint effect of concrete box girder bridges. To this end, a comprehensive experimental program has been set up and seven large-scale concrete box girders have been tested. A transverse analysis model of concrete box girders with haunches is proposed and compared with test data. The results of present study indicate that the ultimate strength is significantly affected by haunch dimension. The increase of strength due to concrete arcing action is reduced with an increase of prestressing steel ratio in laterally prestressed concrete box girders and increases with a larger haunch dimension. The proposed theory allows more realistic prediction of lateral ultimate strength for rational design of actual concrete box girder bridges.

• 한국컴퓨터정보학회논문지
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• 제19권2호
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• pp.151-159
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• 2014

본 연구에서는 Haskell의 모나드 기법을 이용한 명령형 언어의 컴파일러 구현에 대해 논의한다. 이 컴파일러는 한 생성 룰이 입력 스트링의 파싱을 실패할 때 다른 생성 룰로써 파싱하는 backtracking 기능의 비 결정적 Recursive Descent Parser를 포함한다. Haskell은 파싱에 필요한 우수한 기능들을 가지고 있다. Haskell의 대수적 타입은 추상구문트리를 자연스럽게 표현할 수 있으며, 모나드 파싱을 적용한 프로그램 코드는 매우 간결하여 가독성이 좋고, 타 언어에 의해 구현된 것에 비해 코드의 양이 획기적으로 감소된다. 이 컴파일러의 목적 코드는 스택 머신을 기반으로 한 Stack-Assembly 언어로서 이것을 위한 코드 생성과 어셈블러 실행 환경에 대해서도 논의한다.

• 한국전산구조공학회논문집
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• 제21권1호
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• pp.59-71
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• 2008

본 논문에서는 지진하중하의 대형구조물의 시뮬레이션을 위해 실험과 해석을 병합한 분산공유 하이브리드 해석 및 실험소프트웨어 framework를 개발하였다. 제안된 소프트웨어 framework은 별도의 동적 그리고 정적 해석을 위한 프로그램의 개발이 필요 없기 때문에 일반 범용 유한요소해석 프로그램을 개발된 해석 및 실험 제어 프로그램과 interface API를 이용하여 사용할 수 있는 장점이 있다. 본 논문에서 개발된 소프트웨어 framework은 독자적 기능을 가진 module로 구성이 되어 있을 뿐만 아니라 개체지향형 프로그램 개념을 바탕으로 개발되었다. 예제를 통하여 개발된 시스템의 기능과 분산공유하이브리드 해석 및 실험에서의 유용성을 증명하였다.

• Journal of Radiation Protection and Research
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• 제10권2호
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• pp.148-154
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• 1985

KSC-1 핵연료 수송용기에 대한 방사선차폐해석을 QAD-CG, ANISN-KA, DOT 3.5등의 전산코드와 DLC-23/CASK의 핵단면적 자료를 사용하여 수행하였다. 운반물인 사용후 핵연료집합체로 부터 방출되는 중성자 및 감마선의 방사선원항은 ORIGEN-79 전산코드를 이용하여 평가하였다. 방사선차폐해석 결과, 1개의 가압경수로 사용후 핵연료집합체를 운반할 수 있는 KSC-1 핵연료수송용기는 정상적인 수송조건에서 뿐만 아니라 가상적인 사고수송조건하에서도 관련 법령에서 정하는 기준을 만족하고 있어 방사선차폐해석의 관점에서 볼 때, 그 안전성이 입증된다.

• 한국안전학회지
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• 제27권6호
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• pp.14-19
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• 2012

The Helium cooled ceramic reflector(HCCR) test blanket module(TBM) has been designed and developed to participate the ITER(International Thermonuclear Experimental Reactor) test blanket program in Korea. The TBM was one of the main objectives for developing ITER for proving the tritium self-sufficiency and the heat transfers to produce the electricity with the breeding blanket concept. Among the TBM components, the first wall(FW) was the most important component in safety since it was directly faced a high level of a heat and fast neutrons from the plasma side and could protect the others components inside TBM. In this paper, the FW has been designed through the thermo-mechanical analysis considering ITER operation conditions. With the developed simple models, the stress limit analysis based on RCC-MR code which is the nuclear power plant design codes in France was evaluated for the allowable design criteria. The results showed that the designed FW model satisfied $1.5S_m$ or $3S_m$ of the allowable stress($S_m$) in RCC-MR code at the maximum stress region in the FW.

• Journal of Pharmaceutical Investigation
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• 제37권6호
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• pp.377-395
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• 2007

Near infrared(NIR) spectral data have been used for the noninvasive analysis of various biological samples. Nonetheless, absorption bands of NIR region are overlapped extensively. It is very difficult to select the proper wavelengths of spectral data, which give the best PCR(principal component regression) models for the analysis of constituents of biological samples. The NIR data were used after polynomial smoothing and differentiation of 1st order, using Savitzky-Golay filters. To find the best PCR models, all-possible combinations of available principal components from the given NIR spectral data were derived by in-house programs written in MATLAB codes. All of the extensively generated PCR models were compared in terms of SEC(standard error of calibration), $R^2$, SEP(standard error of prediction) and SECP(standard error of calibration and prediction) to find the best combination of principal components of the initial PCR models. The initial PCR models were found by SEC or Malinowski's indicator function and a priori selection of spectral points were examined in terms of correlation coefficients between NIR data at each wavelength and corresponding concentrations. For the test of the developed program, aqueous solutions of BSA(bovine serum albumin) and glucose were prepared and analyzed. As a result, the best PCR models were found using a priori selection of spectral points and the final model selection by SEP or SECP.

• 한국컴퓨터정보학회논문지
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• 제6권4호
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• pp.6-11
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• 2001

국어의 로마자 표기법 기본원칙을 모르더라도 웹 상에서 한글단어, 문장, 문서를 문자열(String)로 입력받아 자동변환이 가능하게 설계하였다. 특히 표음 중심의 전사(Transcription) 표기법의 기계적 변환을 위해 알고리즘(algorithm)화된 음운법칙을 적용하여 소리글자로 자동 변환 후 정부 표준안인 국어 로마자 표기법 레이블에서 대응 글자를 참조하여 기계화 코드 변환이 가능토록 자동변환 알고리즘 설계하였으며, 아스키(ASCII)테이블에서 잘 쓰이지 않는 코드를 반달표(ˇ)와 어깻점(´)등 특수부호로 할당하여 글꼴을 제작하였다. 또한 예외어 사전관리를 통한 예외 처리 문제에 대한 해결 방안을 제시하였으며, UML표기와 C++ 언어를 이용하여 사용자 편리성과 구현에 대한 모델을 제안하였다.

• Nuclear Engineering and Technology
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• 제39권4호
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• pp.287-298
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• 2007

As part of the $AP1000^{TM}$ pressurized water reactor design certification program, a series of integral systems tests of the nuclear steam supply system was performed at the APEX-1000 test facility at Oregon State University. These tests provided data necessary to validate Westinghouse safety analysis computer codes for AP1000 applications. In addition, the tests provided the opportunity to investigate the thermal-hydraulic phenomena expected to be important in AP1000 small-break loss of coolant accidents (SBLOCAs). The APEX-1000 facility is a 1/4-scale pressure and 1/4-scale height simulation of the AP1000 nuclear steam supply system and passive safety features. A series of eleven tests was performed in the APEX-1000 facility as part of a U.S. Department of Energy contract. In all, four SBLOCA tests representing a spectrum of break sizes and locations were simulated along with tests to study specific phenomena of interest. The focus of this paper is the SBLOCA tests. The key thermal-hydraulic phenomena simulated in the APEX-1000 tests, and the performance and interactions of the passive safety-related systems that can be investigated through the APEX-1000 facility, are emphasized. The APEX-1000 tests demonstrate that the AP1000 passive safety-related systems successfully combine to provide a continuous removal of core decay heat and the reactor core remains covered with considerable margin for all small-break LOCA events.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.489-504
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• 2013

Software safety for nuclear reactor protection systems (RPSs) is the most important requirement for the obtainment of permission for operation and export from government authorities, which is why it should be managed with well-experienced software development processes. The RPS software is typically modeled with function block diagrams (FBDs) in the design phase, and then mechanically translated into C programs in the implementation phase, which is finally compiled into executable machine codes and loaded on RPS hardware - PLC (Programmable Logic Controller). Whereas C Compilers are fully-verified COTS (Commercial Off-The-Shelf) software, translators from FBDs to C programs are provided by PLC vendors. Long-term experience, experiments and simulations have validated their correctness and function safety. This paper proposes a behavior-preserving translation from FBD design to C implementation for RPS software. It includes two sets of translation algorithms and rules as well as a prototype translator. We used an example of RPS software in a Korean nuclear power plant to demonstrate the correctness and effectiveness of the proposed translation.

• Architectural research
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• 제22권4호
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• pp.105-112
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• 2020

The purpose of this study is to establish a method for assessing a building's risk against disaster, tentatively named the Korean integrated disaster evaluation simulator (K-IDES). Based on previous studies, FEMA's risk management series and FEMA IRVS are selected as case studies for developing a frame work of K-IDES, through the comparative analysis of domestic building design guides, codes, and special acts related to disasters, in order to develop a risk assessment methodology for quantitative results. The assessment method consists of a classification system and calculating risk, and a simulation applying the developed checklist in K-IDES to similar types of high-rise buildings will be conducted to validate its accuracy. The final goal is to systemize an integrated risk management in a high-rise building against disasters for the purpose of recognizing vulnerable areas from the beginning of the design process and reinforcing it from potential threats after construction.