• 제목/요약/키워드: structural integrity evaluation

검색결과 360건 처리시간 0.025초

격자형 유닛 상세를 가진 단면증설공법으로 보강된 철근콘크리트 기둥의 구조성능평가 (An Evaluation of Structural Performance of Reinforced Concrete Column Retrofitted with Grid Type Unit Details of Jacketing Method)

  • 문홍비;이정인;이영학
    • 한국공간구조학회논문집
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    • 제22권1호
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    • pp.41-49
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    • 2022
  • In the case of columns in buildings with soft story, the concentration of stress due to the difference in stiffness can damage the columns. The irregularity of buildings including soft story requires retrofit because combined load of compression, bending, shear, and torsion acts on the structure. Concrete jacketing is advantageous in securing the strength and stiffness of existing members. However, the brittleness of concrete make it difficult to secure ductility to resist the large deformation, and the complicated construction process for integrity between the existing member and extended section reduces the constructability. In this study, two types of Steel Grid Reinforcement (SGR), which are Steel Wire Mesh (SWM) for integrity and Steel Fiber Non-Shrinkage Mortar (SFNM) for crack resistance are proposed. One reinforced concrete (RC) column with non-seismic details and two columns retrofitted with each different types of proposed method were manufactured. Seismic performance was analyzed for cyclic loading test in which a combined load of compression, bending, shear, and torsion was applied. As a result of the experiment, specimens retrofitted with proposed concrete jacketing method showed 862% of maximum load, 188% of maximum displacement and 1,324% of stiffness compared to non-retrofitted specimen.

Investigation of a management framework for condition assessment of concrete structures based on reusable knowledge and inspection

  • Moodi, Faramarz
    • Computers and Concrete
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    • 제7권3호
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    • pp.249-269
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    • 2010
  • Managing and reusing knowledge in engineering and construction sectors can lead to greater competitive advantage, improved designs, and more effective management of constructed facilities. The use of Information Technology (IT) in design and construction can exploit strategic opportunities for new ways of integration, sharing and facilitating information and knowledge in any field of engineering. The integrating of separate areas of IT can be used to bring a group of experts and specialists in any field of engineering closer together by allowing them to communicate and exchange information and expertise that facilitate knowledge capture, sharing, and reuse. A lack of an advisory management system and a need to marshal all available data in a common format has indicated the need for an integrated engineering computing environment to investigate concrete repair problems. The research described in this paper is based upon an evaluation management system (EMS) which comprising a database management system (REPCON) alongside visualisation technologies and evaluation system (ECON) is developed to produce an innovative platform which will facilitate and encourage the development of knowledge in educational, evolution and evaluation modes of concrete repair. This allows us to create assessment procedures that will allow the current condition of the concrete structure and its components to be expressed numerically using a confidence level (CL) so as to take the best course of action in the repair and maintenance management. The explained rating system, which is related to structural integrity and serviceability of the structure, allows the confidence level to be determined by visual inspection and the descriptive information and pictures taken from an available REPair of CONcrete (REPCON) database.

선박용 대형 계류장비의 개발과 강도 평가 (A Study on the Development and Strength Evaluation of the Mooring Fittings with Big Capacity)

  • 김영식;김을년;김미희;김경연
    • 대한조선학회 특별논문집
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    • 대한조선학회 2017년도 특별논문집
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    • pp.1-7
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    • 2017
  • It has been developed large mooring fittings having the capacity of 160 tons and 180 tons installed on 170K LNG FSRU. The finite element analysis for the mooring fittings was carried out in order to check the structural integrity and to confirm satisfaction of the rule requirements. The 3 kinds of mooring fittings such as chock, bollard and universal fairlead are selected for FE analysis and load test. According to the FE analysis results, all the stress levels satisfied the acceptance criteria guided by the IACS UR A2, ISO standard, ship rules and OCIMF. As test results under design load, no structural defects were found.

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APR1000 원자로용기의 환경피로 평가 (Environmental Fatigue Evaluation of APR1000 Reactor Vessel)

  • 김종민;김용환
    • 한국전산구조공학회논문집
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    • 제26권3호
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    • pp.207-212
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    • 2013
  • APR1000(Advanced Power Reactor 1000)은 기존의 OPR1000(Optimized Power Reactor 1000)에 60년 설계수명, 국부주파수제어운전, 0.3g 안전정지지진하중 적용 등의 향상된 설계특성(Advanced Design Feature)을 적용하여 개선한 수출형 1000MW 원전이다. 이 논문에서는 Reg. Guide 1.207에서 요구하는 원자로냉각재 환경을 고려한 피로 평가를 원자로용기에 대하여 평가하였다. 원자로용기에서 비교적 누적사용계수가 높은 출구노즐을 대상으로 평가를 수행하였으며 출구노즐은 구조적 건전성을 만족하는 것으로 평가되었다.

PVRC 감쇠를 고려한 밀림관의 시간이력해석 (Time History Analysis of Surge Line Considering PVRC Damping)

  • 김태형;전장환;김종민;윤기석;김인용
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 2006년도 정기 학술대회 논문집
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    • pp.1025-1032
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    • 2006
  • The PVRC(Pressure Vessel Research Council) damping is for the response spectrum analysis of the piping system. In this study, the possibility to apply it to the time history analysis is evaluated to reduce the higher conservatism for the structural integrity. The evaluation was performed for the surge line connecting the pressurizer to the hot-leg, and the whole mode includes the RCS and the building structures with the surge line. The analyses were performed using ANSYS code. The first modal analysis shows the modes of the surge line are isolated from those of the other structures. The composite modal damping was calculated with PVRC damping for the surge line and RG 1.60 damping for the other structures by using ANSYS routines. Of the calculated composite modal damping values, the composite modal damping values related to the modes of the surge line were replaced with the PVRC damping values with respect to its frequencies. With this replacement, the composite modal damping values of the other structures were not changed. Based on this decouple characteristics, the time history analyses for the seismic events with PVRC damping for the surge line were performed. And the results show the resultant loads can be reduced by up to 50%.

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딤플 튜브형 EGR Cooler 구조건전성 및 열효율 평가 (Evaluation of Structural Integrity and Heat Exchange Efficiency for Dimpled Tube Type EGR Cooler)

  • 서영호;이현민;박중원;구태완;김정;강범수
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회A
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    • pp.554-559
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    • 2008
  • Most of vehicle manufacturers have applied exhaust gas recirculation (EGR) system to the development of diesel engines in order to obtain the high thermal efficiency without $NO_X$ and Particulate Matter (PM) emitted from the engine. EGR system, which reflow a cooled exhaust gas from vehicles burning diesel as fuel to a combustion chamber of engine, has been used to solve this problem. In order to confirm the safety of the EGR system, finite element analysis was carried out. The safety of EGR system against temperature variation in the shell and tubes was evaluated through the thermal and structural analysis, and the modal analysis using ANSYS was also performed. Finally, the performance of EGR system was verified through the experiment and numerical simulation using effectiveness-NTU method. Program for the estimation of the heat exchange efficiency of the EGR system with regard to the dimpled tube shape was developed.

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Probabilistic behavior of semi-active isolated buildings under pulse-like earthquakes

  • Oncu-Davas, Seda;Alhan, Cenk
    • Smart Structures and Systems
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    • 제23권3호
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    • pp.227-242
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    • 2019
  • Seismic isolation systems employ structural control that protect both buildings and vibration-sensitive contents from destructive effects of earthquakes. Structural control is divided into three main groups: passive, active, and semi-active. Among them, semi-active isolation systems, which can reduce floor displacements and accelerations concurrently, has gained importance in recent years since they don't require large power or pose stability problems like active ones. However, their seismic performance may vary depending on the variations that may be observed in the mechanical properties of semi-active devices and/or seismic isolators. Uncertainties relating to isolators can arise from variations in geometry, boundary conditions, material behavior, or temperature, or aging whereas those relating to semi-active control devices can be due to thermal changes, inefficiencies in calibrations, manufacturing errors, etc. For a more realistic evaluation of the seismic behavior of semi-active isolated buildings, such uncertainties must be taken into account. Here, the probabilistic behavior of semi-active isolated buildings under historical pulse-like near-fault earthquakes is evaluated in terms of their performance in preserving structural integrity and protecting vibration-sensitive contents considering aforementioned uncertainties via Monte-Carlo simulations of 3-story and 9-story semi-active isolated benchmark buildings. The results are presented in the form of fragility curves and probability of failure profiles.

Seismic responses of nuclear reactor vessel internals considering coolant flow under operating conditions

  • Park, Jong-beom;Lee, Sang-Jeong;Lee, Eun-ho;Park, No-Cheol;Kim, Yong-beom
    • Nuclear Engineering and Technology
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    • 제51권6호
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    • pp.1658-1668
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    • 2019
  • Nuclear power generates a large portion of the energy used today and plays an important role in energy development. To ensure safe nuclear power generation, it is essential to conduct an accurate analysis of reactor structural integrity. Accordingly, in this study, a methodology for obtaining accurate structural responses to the combined seismic and reactor coolant loads existing prior to the shutdown of a nuclear reactor is proposed. By applying the proposed analysis method to the reactor vessel internals, it is possible to derive the seismic responses considering the influence of the hydraulic loads present during operation for the first time. The validity of the proposed methodology is confirmed in this research by using the finite element method to conduct seismic and hydraulic load analyses of the advanced APR1400 1400 MWe power reactor, one of the commercial reactors. The structural responses to the combined applied loads are obtained using displacement-based and stress-based superposition methods. The safety of the subject nuclear reactor is then confirmed by analyzing the design margin according to the American Society for Mechanical Engineers (ASME) evaluation criteria, demonstrating the promise of the proposed analysis method.

비상디젤발전기의 회전체 및 구조물 해석적 건전성 평가에 관한 연구 (A Study of Analytical Integrity Estimations for the Structure and Rotor System of an Emergency Diesel Generator)

  • 김재실;최헌오;정훈형
    • 한국소음진동공학회논문집
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    • 제24권2호
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    • pp.79-86
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    • 2014
  • 이 논문에서는 비상디젤발전기의 구조물 및 내부 회전체에 대한 건전성 평가를 위한 해석적 방법을 제시한다. 비상발전기는 원자력발전소 안전과 관련된 매우 중요한 기기로써 지진과 같은 비상사태에 원전의 안전 정지를 위한 관련 기기에 비상 전원을 공급한다. 비상발전기의 회전기 부분 또한 지진과 같은 충격에도 안전성을 확보해야 한다. 비상발전기 본체에 대한 모달 해석을 하여 공진 주파수가 지진 주파수 영역에 있는지를 확인하여 응력 해석의 방법을 정했다. 회전체 부분의 안전성은 저널 베어링의 필름 두께와 임계 회전수를 계산하여 최소 유막 요구치와 운전속도와 비교하여 안전성을 판단하였다. 계산된 응력해석의 최대치는 허용치보다 작았으며, 저널 베어링의 유막과 회전수 또한 안전한 범위에 들었다. 이 논문에서는 저널 베어링의 안전해석에 지진하중을 정적 하중으로 보았으나 향후 연구에 있어서는 지진하중의 동적 특성을 회전체에 적응하는 새로운 해석적 방법의 개발이 필요할 것으로 사료된다.

원자력발전소 고강도 앵커 볼트의 파괴역학적 건전성평가 (Structural Integrity Assessment of High-Strength Anchor Bolt in Nuclear Power Plant based on Fracture Mechanics Concept)

  • 임은모;허남수;심희진;오창균;김현수
    • 대한기계학회논문집A
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    • 제37권7호
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    • pp.875-881
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    • 2013
  • 증기발생기 수직 지지대를 고정하고 있는 고강도 앵커 볼트의 응력부식균열에 대한 건전성 평가는 원자력발전소 기기 건전성 유지와 관련하여 중요한 현안 가운데 하나이다. 이에 따라 미국 EPRI에서는 고강도 앵커 볼트의 건전성 평가를 위한 기준균열계수 개념 기반의 평가 절차를 제시한 바 있으며, 본 연구에서는 EPRI에서 제시한 절차에 입각하여 증기발생기 수직 지지대 고정용 앵커 볼트의 응력부식균열 및 취성 파괴에 대한 건전성 평가를 수행하였다. 이를 위해 볼트 예비하중과 운전하중을 고려한 3차원 유한요소 응력해석을 수행하여 볼트 단면에 작용하는 공칭응력을 결정하였으며, 결정된 볼트 응력과 EPRI 절차를 이용하여 앵커 볼트의 균열 건전성을 평가하였다. 또한 3차원 탄성 유한요소 파괴역학 해석을 수행하여 EPRI에서 제시한 기준균열계수의 정확성을 검증하였다.