• 제목/요약/키워드: Structural Analysis Program

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PC용 객체지향 구조해석 프로그램의 개발 (Development of Object-Oriented Structural Analysis Program for PC)

  • 신영식;서진국;박영식;최희욱
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 1992년도 가을 학술발표회 논문집
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    • pp.105-111
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    • 1992
  • A computer program for matrix structural analysis by object-oriented programming technique using $C^{++}$ language has been developed. Object, class, method and inheritance which are used in object-oriented programming are illustrated using a graphical representation. The matrix operations and the structural analysis by matrix displacement method were satisfactorily performed by the proposed program. Numerical tests demonstrate that this proposed program can be widely used for the matrix structural analysis for personal computers.s.

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지역별 단동비닐하우스 자동설계프로그램 개발 (Development of Automatic Design Program for Small Scale Vinyl House by Regions)

  • 이석건;이종원;이현우
    • 한국농공학회:학술대회논문집
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    • 한국농공학회 2003년도 학술발표논문집
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    • pp.327-330
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    • 2003
  • The objectives of this study are to develope the automatic design programs to offer the data when constructing a small scale vinyl-house by region. This program consists of four subroutines. The first is an automatic greenhouse modeling program, the second is a calculating design load program by region, the third is a structural analysis program and the last is a optimum shape design program. The structural analysis can be conducted by simple date input and considering the design load of the install regions into account. The shape of input data is very simple, and the program reflects the design load by region. The output data can be obtained from the automatical calculation processing after structural analysis. The program was verified by compared with outputs of a common use structural analysis program and the results are the same. It was concluded that the developed program could be used efficiently in optimum design of small scale vinyl house.

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Hydraulic and Structural Analysis for APR1400 Reactor Vessel Internals against Hydraulic Load Induced by Turbulence

  • Kim, Kyu Hyung;Ko, Do Young;Kim, Tae Soon
    • International Journal of Safety
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    • 제10권2호
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    • pp.1-5
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    • 2011
  • The structural integrity assessment of APR1400 (Advanced Power Reactor 1400) reactor vessel internals has been being performed referring the US Nuclear Regulatory Commission regulatory guide 1.20 comprehensive vibration assessment program prior to commercial operation. The program is composed of a hydraulic and structural analysis, a vibration measurement, and an inspection. This paper describes the hydraulic and structural analysis on the reactor vessel internals due to hydraulic loads caused by the turbulence of reactor coolant. Three-dimensional models were built for the hydraulic and structural analysis and then hydraulic loads and structural responses were predicted for five analysis cases with CFX and ANSYS respectively. The structural responses show that the APR1400 reactor vessel internals have sufficient structural integrity in comparison with the acceptance criteria.

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Development of a new CVAP structural analysis methodology of APR1400 reactor internals using scaled model tests

  • Jongsung Moon;Inseong Jin;Doyoung Ko;Kyuhyung Kim
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.309-316
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    • 2024
  • The U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.20 provides guidance on the comprehensive vibration assessment program (CVAP) to be performed on reactor internals during preoperational and startup tests. The purpose of the program is to identify loads that could cause vibration in the reactor internals and to ensure that these vibrations do not affect their structural integrity. The structural vibrational analysis program involves creating finite element analysis models of the reactor internals and calculating their structural responses when subjected to vibration loads. The appropriateness of the structural analysis methodology must be demonstrated through benchmarks or any other reasonable means. Although existing structural analysis methodologies have been proven to be appropriate and are widely used, this paper presents the development of an improved new structural analysis methodology for APR1400 reactor internals using scaled model tests.

PC용 객체지향 구조해석 프로그램의 개발 (Development of Object-Oriented Structural Analysis Program for PC)

  • 신영식;서진국;최희욱;박영식
    • 전산구조공학
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    • 제5권4호
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    • pp.125-132
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    • 1992
  • 본 연구에서는 C++언어를 이용한 객체지향 프로그래밍 기법으로 매트릭스 연산과 평면뼈대 구조물의 해석이 가능한 PC용 구조해석 프로그램을 개발하였다. 객체지향 프로그래밍에서의 주요 개념인 객체, 클래스, 처리방식, 상속성 및 다형성을 도식화하여 설명하였으며, 매트릭스 연산과 평면뼈대 구조해석에 대한 예제 해석 결과는 이 프로그램의 효율성과 타당성을 보여 주었다. 따라서 본 연구는 객체지향 프로그래밍기법의 특징인 프로그램의 확장성과 재사용성 및 다양한 GUI의 구현가능성을 이용하여 앞으로의 객체지향 유한요소 프로그램 개발에 활용될 것이다.

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Visual Basic을 이용한 구조해석 프로그램 개발에 관한 연구 (A study on the Development of Structural Analysis Program using Visual Basic)

  • 이상갑;장승조
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 1995년도 가을 학술발표회 논문집
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    • pp.215-222
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    • 1995
  • The objective of this paper is to develop a finite element structural analysis program using VB(Visual Basic) which has been recently getting popular as development tools of application program for Windows. VB provides several functions to develop an application program easily by supporting event-driven programming method and graphic object as control data type. This system is an integrated processor including preprocessor, solver and postprocessor. Automatic mesh generation is available at preprocess stage, and graphic presentation of deformation and stress is also represented at postprocess one.

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동적효과를 고려한 연쇄붕괴해석 프로그램의 개발 (Development of Progressive Collapse Analysis Program considering Dynamic Effects)

  • 김진구;박준희;안다운;김현수
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 2007년도 정기 학술대회 논문집
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    • pp.771-776
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    • 2007
  • Widespread propagation of failure can be triggered by localized damage to a structure because of fires, impact and explosion etc. In this paper, the progressive collapse analysis program is developed to automatically check the failed members and construct the modified structural model at each step. OpenSees, that is widely used in many research groups, was used for the developed progressive collapse analysis control program. The control program developed in this study automatically computes the damage indices of all the structural members and performance a progressive collapse analysis after the first failed member is selected. Using the developed program, we compared the progressive collapse behaviors of the example structures considering dynamic effects or not, and the difference of progressive collapse mechanism according to the modeling method of the failed members.

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블록화기법을 이용한 대형구조물의 해석방법 (An Analysis Method of Large Structure Using Matrix Blocking)

  • 정성진;이민섭
    • 한국구조물진단유지관리공학회 논문집
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    • 제18권2호
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    • pp.30-37
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    • 2014
  • 본 연구에서는 개인 컴퓨터의 플래시 메모리가 충분하지 않을 경우 대용량의 플래시 메모리를 필요로 하는 구조해석을 컴퓨터 프로그램으로 수행하는 방법론을 연구하였다. 이러한 문제점의 해결방안으로 강성행렬의 블록화기법 -강성행렬이 몇 개의 블록으로 나뉘고 각각의 블록에 대하여 행렬분해가 수행되는 방법- 을 제안하였으며 제안된 방법론을 바탕으로 컴퓨터 프로그래밍이 가능한 알고리즘을 제시하였다. 끝으로, 본 연구를 바탕으로 구조해석 프로그램을 개발하였으며 몇 가지 기초적인 구조해석 예제를 통하여 개발 알고리즘의 정합성 및 효율성을 확인할 수 있었다.

APR1400 원자로내부구조물 종합진동평가프로그램 진동 및 응력해석 방법론 검증 (Validation of Vibration and Stress Analysis Methodology for APR1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program)

  • 김규형;고도영;김성환
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2012년도 추계학술대회 논문집
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    • pp.300-305
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    • 2012
  • The vibration and stress analysis program of comprehensive vibration assessment program (CVAP) is to verify theoretically the structural integrity of reactor vessel internals (RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the verification of the vibration and stress analysis methodology of APR1400 RVI CVAP. The analysis methodology was developed to use 3-dimensional hydraulic and structural models with ANSYS and CFX. To validate the methodology, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the calculated and measured data in the OPR1000 RVI CVAP. Since the results predicted with this methodology were close to the measured values considerably, it was confirmed that the analysis methodology was developed properly.

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원자로냉각재펌프 맥동에 대한 APR1400 원자로내부구조물의 진동 및 응력 해석 (Vibration and Stress Analysis for Reactor Vessel Internals of Advanced Power Reactor 1400 by Pulsation of Reactor Coolant Pump)

  • 김규형;고도영;김성환
    • 한국소음진동공학회논문집
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    • 제21권12호
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    • pp.1098-1103
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    • 2011
  • The structural integrity of APR1400 reactor vessel internals has been being assessed referring the US Nuclear Regulatory Commission regulatory guide 1.20, comprehensive vibration assessment program. The program is composed of a vibration and stress analysis, a vibration and stress measurement, and an inspection. This paper covers the vibration and stress analysis on the reactor vessel internals by the pulsation of reactor coolant pump. 3-dimensional models to calculate the hydraulic loads and structural responses were built and the pressure distributions and the structural responses were predicted using ANSYS. This paper presents that APR1400 reactor vessel internals have enough structural integrity against the pulsation of reactor coolant pump as the peak stress of the reactor vessel internals is much lower than the acceptance limit.