• 제목/요약/키워드: Mechanical Integrity

검색결과 789건 처리시간 0.025초

Wireless sensor networks for permanent health monitoring of historic buildings

  • Zonta, Daniele;Wu, Huayong;Pozzi, Matteo;Zanon, Paolo;Ceriotti, Matteo;Mottola, Luca;Picco, Gian Pietro;Murphy, Amy L.;Guna, Stefan;Corra, Michele
    • Smart Structures and Systems
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    • 제6권5_6호
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    • pp.595-618
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    • 2010
  • This paper describes the application of a wireless sensor network to a 31 meter-tall medieval tower located in the city of Trento, Italy. The effort is motivated by preservation of the integrity of a set of frescoes decorating the room on the second floor, representing one of most important International Gothic artworks in Europe. The specific application demanded development of customized hardware and software. The wireless module selected as the core platform allows reliable wireless communication at low cost with a long service life. Sensors include accelerometers, deformation gauges, and thermometers. A multi-hop data collection protocol was applied in the software to improve the system's flexibility and scalability. The system has been operating since September 2008, and in recent months the data loss ratio was estimated as less than 0.01%. The data acquired so far are in agreement with the prediction resulting a priori from the 3-dimensional FEM. Based on these data a Bayesian updating procedure is employed to real-time estimate the probability of abnormal condition states. This first period of operation demonstrated the stability and reliability of the system, and its ability to recognize any possible occurrence of abnormal conditions that could jeopardize the integrity of the frescos.

정지궤도복합위성 추진계 배관망 구조해석 (Stress Analysis of the GEO-KOMPSAT-2 Tubing System)

  • 정규;임재혁;채종원;전형열
    • 항공우주시스템공학회지
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    • 제12권1호
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    • pp.47-56
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    • 2018
  • 본 논문에서는 정지궤도복합위성 추진계 배관망의 독자적인 구조해석을 실시하였고, AIRBUS의 구조해석결과와 비교분석을 통해 추진계 배관망의 구조적 건전성 및 해석방법의 신뢰성을 평가하였다. 추진계 배관망의 구조적 신뢰성 확보는 정지궤도복합위성 추진계의 매우 중요한 핵심요소이다. 따라서 CAE 프로그램을 통해 직접 추진계 배관망 모델링을 수행하였고, 발사환경에서 구조해석을 실시하여 응력을 도출하였다. 내압응력해석, 조립정렬해석, 정현파진동해석, 랜덤진동해석의 하중조건에 따라 Hoop stress, Axial stress, Bending stress, Torsion stress를 구하였고, 이를 모두 고려한 von Mises 응력 계산 후 안전여유 결과 값을 도출함으로써 추진계 배관망의 구조적 건전성을 판단하였다.

Passive seismic protection systems with mechanical metamaterials: A current review

  • Guevara-Corzo, Jeffrey J.;Begambre-Carrillo, Oscar J.;Garcia-Sanchez, Jesus A.;Sanchez-Acevedo, Heller G.
    • Structural Engineering and Mechanics
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    • 제82권4호
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    • pp.417-434
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    • 2022
  • In this work, a review of mechanical metamaterials and seismic protection systems that use them is carried out, focusing on passive protection systems. During the last years, a wide variety of classical systems of seismic protection have demonstrated to be an effective and practical way of reducing the seismic vulnerability of buildings, maintaining their health and structural integrity. However, with the emergence of metamaterials, which allow obtaining uncommon mechanical properties, new procedures and devices with high performance have been developed, reducing the seismic risk through novel approaches such as: seismic shields and the redirection of seismic waves; the use of stop band gaps and the construction of buried mass resonators; the design of pentamodal base isolators. These ideas are impacting traditional areas of structural engineering such as the design and building of highly efficient base isolation systems. In this work, recent advances in new seismic protection technologies and researches that integrate mechanical metamaterials are presented. A complete bibliometric analysis was carried out to identify and classify relevant authors and works related with passive seismic protection system based on mechanical metamaterial (pSPSmMMs). Finally, possible future scenarios for study and development of seismic isolators based on mechanical metamaterials are shown, identifying the relevant topics that have not yet been explored, as well as those with the greatest potential for future application.

부식 손상된 파이프라인의 잔존 수명 예측 (Prediction of Remaining Life for Corroded Pipelines)

  • 진영준
    • 한국산업융합학회 논문집
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    • 제7권4호
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    • pp.411-417
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    • 2004
  • Recently, researchers and engineers from, the development of reliability engineering and probability fracture mechanics, have begun to take seriously the reliability analysis and the integrity for a corroded pipeline. Pressurized pipelines containing active corrosion defects increase gradually both in extent, and depth with increased periods of exposure. This causes a reduction of the remaining strength and the carrying capacity of a pipeline; and creates uncertainty about the future capacity. The steps that are necessary in order to assess the integrity of corroded pipelines will be discussed in this paper utilizing results from an actual model.

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DVD-RAM 기판의 복굴절, Radial-tilt 및 전사성 향상을 위한 사출압축성형공정 최적화 (An Optimum Design of Replication Process to Improve Birefringence, Radial-tilt and Land-Groove Structure in DVD-RAM Substrates)

  • 이남석;성기병;강신일
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집C
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    • pp.438-444
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    • 2001
  • The objective of this study is to provide a simple methodology to find optimum processing conditions to fabricate sub-micron structured DVD-RAM substrates with superb optical and geometrical properties. It was found that the birefringence, which is regarded as one of the most important optical properties for an optical disk, was very sensitive to the mold wall temperature history. Also, the integrity of the replication, represented by the land-groove structure and the radial tilt were influenced by the mold temperature and the compression pressure. A set of optimum conditions were obtained by applying Design of Experiment and the objective functions composed of three different objectives.

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원자력 발전소용 블레이드링 건전성 평가 (Integrity Assessment of Stationary Blade Ring for Nuclear Power Plant)

  • 박정용;정용근;박종진;강용호
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 추계학술대회
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    • pp.85-89
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    • 2004
  • The inner side between HP stationary blades in #1 turbine of Nuclear Power Plant A is damaged by the FAC(flow assisted corrosion) which is exposed to moisture. For many years the inner side is repaired by welding the damaged part, however, FAC continues to deteriorate the original material of the welded blade ring. In this study, we have two stages to verify the integrity of stationary blade ring in nuclear power plant A. In the stage I, replication of blade ring is performed to survey the microstructure of blade ring. In the stage II, the stress analysis of blade ring is performed to verify the structural safety of blade ring. Throughout the two stages analysis of blade ring, the stationary blade ring had remained undamaged.

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리드 핀 제조용 펀치 금형의 홈 가공에 관한 연구 (A Study on Slot Grinding for Lead Pin Punching Die)

  • 이용찬;정상철;정해도
    • 한국정밀공학회지
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    • 제17권4호
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    • pp.106-113
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    • 2000
  • One of the recent changes in machining technology is rapid application of micro- and high precision grinding processes. A fine groove generation is necessary for the fabrication of optics, electronics and semiconductor parts. Slot grinding is very efficient for the generation of micro ordered groove with hard and brittle materials. In the process of slot grinding, chipping at the sharp edges and microcracks of the ground grooves are inevitable defects. Chipping should be reduced for the improvement of surface integrity. Mechanical contact with diamond grits causes microcracks at the grooves. This damage resides subsurface, and can be the cause of failure of the punch die. This paper deals with chipping generation at the sharp edges, surface integrity of side groove and fracture strength is related to the microcracks in the slot grinding.

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가압중수로형원전의 중대사고 대응능력 연구 (A Study on Severe Accident Management Capabilities and Strategies for CANDU Reactor)

  • 최영;박종호
    • 한국안전학회지
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    • 제29권5호
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    • pp.160-165
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    • 2014
  • The realistic cases causing severe core damage should be analyzed and arranged systematically for preparing an accident management of the specific nuclear power plant. The objective of this paper is to establish basic technical information for reactor safety and reactor building integrity management strategies in CANDU reactor severe accident. For the development of severe accident management strategies, plant specific features and behaviors must be studied by detailed analysis works. This analysis scope will serve to cover overall methods and analyzing results to understand the reactor building integrity status in the most likely severe accident sequences that could occur at CANDU reactor. Also analysis results could help prevent or mitigate severe accidents for the identification of any plant specific vulnerabilities to severe accidents using the probabilistic safety assessment (PSA) quantified results.

결함발생 시점을 고려한 CANDU 압력관 결함의 확률론적 건전성평가 (Probabilistic Integrity Assessment of CANDU Pressure Tube for the Consideration of Flaw Generation Time)

  • 곽상록;이준성;김영진;박윤원
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 추계학술대회논문집A
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    • pp.155-160
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    • 2001
  • This paper describes a probabilistic fracture mechanics (PFM) analysis based on Monte Carlo (MC) simulation. In the analysis of CANDU pressure tube, it is necessary to perform the PFM analyses based on statistical consideration of flaw generation time. A depth and an aspect ratio of initial semi-elliptical surface crack, a fracture toughness value, delayed hydride cracking (DHC) velocity, and flaw generation time are assumed to be probabilistic variables. In all the analyses, degradation of fracture toughness due to neutron irradiation is considered. Also, the failure criteria considered are plastic collapse, unstable fracture and crack penetration. For the crack growth by DHC, the failure probability was evaluated in due consideration of flaw generation time.

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국내 안전등급 배관에 대한 손상사례 분석 (Piping Failure Analysis In Domestic Nuclear Safety Piping System)

  • 최선영;최영환
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 춘계학술대회
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    • pp.617-621
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    • 2003
  • The purpose of this paper is to analyze piping failure trend of safety pipings In domestic nuclear power plants. First, database for the piping failure was constructed with 105 data fields. The database includes plant population data, event data, and service history data. 7 kinds of piping failures in domestic NPPs were investigated. Among the 7 cases, detailed root causes were investigated for 3 cases. The first one is pipe wall thinning in main feedwater pipings of Westinghouse 3 loop type plants. The root cause of the wall thinning was flow accelerated corrosion near welding area. The next one is leak event in chemical and volume control system(CVCS) due to vibration. Some cracks occurred in socket welding area. The events showed that the integrity or socket weld is very vulnerable to vibration. The last one is also a leak event in primary sampling line in Korean standard reactor due to thermal fatigue. Although the structural integrity was not maintained by the events, there was no effect on nuclear safety in the above 3 piping failure eases.

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