• Title/Summary/Keyword: Program Codes

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Lateral ultimate behavior of prestressed concrete box girder bridges (프리스트레스트 콘크리트 박스거더의 횡방향 극한거동 실험 연구)

  • Oh, Byung-Hwan;Choi, Young-Cheol;Lee, Seung-Cheol
    • Proceedings of the Korea Concrete Institute Conference
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    • 2005.05a
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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.

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Implementation of Nondeterministic Compiler Using Monad (모나드를 이용한 비결정적 컴파일러 구현)

  • Byun, Sugwoo
    • Journal of the Korea Society of Computer and Information
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    • v.19 no.2
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    • pp.151-159
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    • 2014
  • We discuss the implementation of a compiler for an imperative programming language, using monad in Haskell. This compiler involves a recursive-descent parser conducting nondeterministic parsing, in which backtracking occurs to try with other rules when the application of a production rule fails to parse an input string. Haskell has some strong facilities for parsing. Its algebraic types represent abstract syntax trees in a smooth way, and program codes by monad parsing are so concise that they are highly readable and code size is reduced significantly, comparing with other languages. We also deal with the runtime environment of the assembler and code generation whose target is the Stack-Assembly language based on a stack machine.

Distributed Hybrid Simulation and Testing System using General-Purpose Finite Element Analysis Program (범용 유한요소해석 프로그램을 이용한 분산 공유 하이브리드 해석 및 실험 시스템)

  • Yun, Gun-Jin;Han, Bong-Koo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.21 no.1
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    • pp.59-71
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    • 2008
  • In this paper, a software framework that integrates computational and experimental simulation has been developed to simulate and test a large-scale structural system under earthquake loading. The proposed software framework does not need development of the computer codes for both dynamic and static simulations. Any general-purpose software can be utilized with a main control module and interface APIs. This opens up a new opportunity to facilitate use of sophisticated finite elements into hybrid simulation regime to enhance accuracy and efficiency of simulations. The software framework described in the paper is modular and uses object oriented programming concepts. A series of illustrative examples demonstrate that the system is fully-functional and is capable of running any number of experimental and/or analytical components.

Radiation Shield Analysis for Spent Fuel Shipping Cask (핵연료 수송용기의 방사선 차폐해석)

  • Cho, Kun-Woo;Kim, Hee-Won;Kwon, Seog-Kun;Kwak, Eun-Ho;Moon, Philip-S.
    • Journal of Radiation Protection and Research
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    • v.10 no.2
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    • pp.148-154
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    • 1985
  • Radiation shield design for a shipping cask, KSC-1, was evaluated to verify that the cask can be used in the transportation of a spent fuel assembly discharged from KNU 5 & 6. Radiation source term of the spent fuel assembly was calculated with the computer program ORIGEN-79, QAD-CG, ANISN-KA and DOT 3.5 codes Were used in the shielding calculations and the nuclear cross section data needed was extracted from the DLC-23/CASK library. It is concluded that KSC-1 shipping cask satisfies the requirements specified in the relevant regulations under normal conditions of transport and under accident conditions in transport.

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First Wall Design of ITER Test Blanket Module(TBM) based on RCC-MR Code (RCC-MR 코드에 기반한 ITER 시험증식블랑켓 일차벽 설계)

  • Shin, Kyu In;Lee, Dong Won
    • Journal of the Korean Society of Safety
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    • v.27 no.6
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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.

Algorithm for Finding the Best Principal Component Regression Models for Quantitative Analysis using NIR Spectra (근적외 스펙트럼을 이용한 정량분석용 최적 주성분회귀모델을 얻기 위한 알고리듬)

  • Cho, Jung-Hwan
    • Journal of Pharmaceutical Investigation
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    • v.37 no.6
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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.

Design of automatic translation system for hangul's romanization Based on the World Wide Web (웹 기반하의 국어의 로마자 표기 자동 변환 시스템 설계)

  • 김홍섭
    • Journal of the Korea Society of Computer and Information
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    • v.6 no.4
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    • pp.6-11
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    • 2001
  • After automatic translation system for hangul's romanization based on the World Wide Web converting korean-word. sentence, document to Transliteration letters by applying algorithm based phonological principles. even though a user do not know the basic principles of the usage of Korean-to-Romanization notations. It refers to corresponding character table that has been currently adopted the authority's standard proposition for Korean-to-Romanization notation rule concurrently, add to make possible to convert a machinized code as well. It Provides font for toggling Korean-English mode, insert-edit mode by assigning ASCII codes are hardly used to them. This program could be made in C++ programming language and Unified Modeling Language to implement various font. font-expanding and condensing, alternative printing.

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SIMULATED AP1000 RESPONSE TO DESIGN BASIS SMALL-BREAK LOCA EVENTS IN APEX-1000 TEST FACILITY

  • Wright, R.F.
    • Nuclear Engineering and Technology
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    • v.39 no.4
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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.

A BEHAVIOR-PRESERVING TRANSLATION FROM FBD DESIGN TO C IMPLEMENTATION FOR REACTOR PROTECTION SYSTEM SOFTWARE

  • Yoo, Junbeom;Kim, Eui-Sub;Lee, Jang-Soo
    • Nuclear Engineering and Technology
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    • v.45 no.4
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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.

A Study on a Risk Assessment Method and Building Simulation for the Development of a Korean Integrated Disaster Evaluation Simulator (K-IDES) for High-rise Buildings

  • Kim, Tae-Young;Han, Gi-Sung;Kang, Boo-Seong;Lee, Kyung-Hoon
    • Architectural research
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    • v.22 no.4
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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.