• Title/Summary/Keyword: earthquake safety

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Slope Stability Analysis of Filldams by Modified Seismic Intensity Method (수정진도법에 의한 댐사면 안정해석)

  • 신동훈;이종욱
    • Proceedings of the Korean Geotechical Society Conference
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    • 2000.11a
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    • pp.223-228
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    • 2000
  • The current slope stability analysis of a filldam is based on the limit equilibrium method, and in calculation of safety factor during earthquake, adopts the seismic intensity method in which it considers a uniform seismic force from dam foundation to crest. However the observed behaviour of filldam during earthquake shows some different behaviour in that at the crest the measured acceleration is usually several times the ground acceleration. In this study, slope stability calculations of a filldam are provided based on the modified seismic intensity method, which can take into account the amplification phenomena of acceleration in the upper part of dam. And also the results of calculations are compared with that of current seismic intensity method.

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Seismic vulnerability evaluation of a 32-story reinforced concrete building

  • Memari, A.M.;Motlagh, A.R. Yazdani;Akhtari, M.;Scanlon, A.;Ashtiany, M. Ghafory
    • Structural Engineering and Mechanics
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    • v.7 no.1
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    • pp.1-18
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    • 1999
  • Seismic evaluation of a 32-story reinforced concrete framed tube building is performed by checking damageability, safety, and toughness limit states. The evaluation is based on Standard 2800 (Iranian seismic code) which recommends equivalent lateral static force, modal superposition, or time history dynamic analysis methods to be applied. A three dimensional linearly elastic model checked by ambient vibration test results is used for the evaluation. Accelerograms of three earthquakes as well as linearly elastic design response spectra are used for dynamic analysis. Damageability is checked by considering story drift ratios. Safety is evaluated by comparing demands and capacities at the story and element force levels. Finally, toughness is studied in terms of curvature ductility of members. The paper explains the methodology selected and various aspects in detail.

Investigation of seismic safety of a masonry minaret using its dynamic characteristics

  • Basaran, Hakan;Demir, Ali;Ercan, Emre;Nohutcu, Halil;Hokelekli, Emin;Kozanoglu, Celalettin
    • Earthquakes and Structures
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    • v.10 no.3
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    • pp.523-538
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    • 2016
  • Besides their spiritual significance, minarets are humanity's cultural heritage to the future generations due to their historical and architectural attraction. Currently, many historical masonry minarets are damaged and destroyed due to several reasons such as earthquakes and wind. Therefore, safety of these religiously significant buildings needs to be thoroughly investigated. The utmost care must be taken into account while investigating these structures. Our study investigated earthquake behavior of historical masonry minaret of Haci Mahmut Mosque. Destructive and non-destructive tests were carried out to determine earthquake safety of this structure. Brick-stone masonry material properties of structure were determined by accomplishing ultrasonic wave velocity, Schmidt Hammer, uniaxial compression (UAC) and indirect tension (Brazilian) tests. Determined material properties were used in the finite element analysis of the structure. To validate the numerical analysis, Operational Modal Analysis was applied to the structure and dynamic characteristics of the structure were determined. To this end, accelerometers were placed on the structure and vibrations due to environmental effects were followed. Finite element model of the minaret was updated using dynamic characteristics of the structure and the realistic numerical model of the structure was obtained. This numerical model was solved by using earthquake records of Turkey with time history analysis (THA) and the realistic earthquake behavior of the structure was introduced.

A Study on the Probabilistic Safety Assessment and Sensitivity Analysis of Success Criteria of Large LOCA for APR+ (APR+ 확률론적 안전성평가 및 대형냉각재상실사고 성공기준과 파단크기 민감도 분석)

  • Moon, Horim;Kim, Han Gon
    • Journal of the Korean Society of Safety
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    • v.31 no.6
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    • pp.129-134
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    • 2016
  • Standard design of APR+(advanced power reactor plus) was certified at 2014 by Korea regulatory body. Based on the experience gained from OPR1000 and APR1400, the APR1400 was being developed as a 1,500MWe class reactor using Korean technologies for design code, reactor coolant pump, and man-machine interface system. APR+ has been basically designed to have the seismic design basis of safe shutdown earthquake (SSE) 0.3g, a 4-train safety concept based on N+2 design philosophy, and a passive auxiliary feedwater system (PAFS). Also, safety issues on the Fukushima-type accidents have been extensively reviewed and applied to enhance APR+ safety. APR+ provides higher reliability and safety against tsunami and earthquake. The purpose of this paper is to implement probabilistic safety assessment considering these design features and to analyze sensitivity of core damage frequency for large loss of coolant accident of APR+.

Assessment of Dam Seismic Safety using the Relationship between Acceleration and JMA Intensity (가속도와 JMA진도 관계를 이용한 댐 시설의 지진 안정성 평가)

  • Kang, Gi-Chun;Choi, Byoung-Seub;Cha, Kee-Uk;Cheung, Sang-In;Lee, Jong-Wook
    • Journal of the Earthquake Engineering Society of Korea
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    • v.18 no.6
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    • pp.271-278
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    • 2014
  • Seismic intensity deduced from instrumental data has been evaluated using the empirical relationship between intensity and peak ground acceleration (PGA) during an earthquake. The Japan Meteorological Agency (JMA) developed a seismic intensity meter, which can estimate the real-time seismic intensity from seismic motions observed at a local site to evaluate the damage during the earthquake more correctly. This paper proposes a practical application of the JMA intensity to dams during the 2013 earthquake in Yeongcheon, Korea. In the present paper, seismic intensity was estimated from the relationships between accelerations observed at Yeongcheon Dam. Estimated seismic intensities were in the range of 0 to 3, which was verified from the displacements of dams and the variation of the ground water level observed at Yeongcheon dam during the earthquake. The JMA intensity, which is determined by considering the frequency, duration of cyclic loading, etc., was 0 (zero) and there was no damage to Yeoncheon dam during the earthquake.

Forecasting probabilities of earthquake in Korea based on seismological data (지진 관측자료를 기반으로 한 한반도 지진 발생 확률 예측)

  • Choi, Seowon;Jang, Woncheol
    • The Korean Journal of Applied Statistics
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    • v.30 no.5
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    • pp.759-774
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    • 2017
  • Earthquake concerns have grown after a remarkable earthquake incident on September 12th, 2016 in Gyeongju, Korea. Earthquake forecasting is gaining in importance in order to guarantee infrastructure safety and develop protection policies. In this paper, we adopt a power-law distribution model to fit past earthquake occurrences in Korea with various historical and modern seismological records. We estimated power-law distribution parameters using empirical distributions and calculated the future probabilities for large earthquake events based on our model. We provide the probability that a future event has a larger magnitude than given levels, and the probability that a future event over certain levels will occur in a given period of time. This model contributes to the assessment of latent seismological risk in Korea by estimating future earthquake probabilities.

SHAKING TABLE TEST OF STEEL FRAME STRUCTURES SUBJECTED TO SCENARIO EARTHQUAKES

  • CHOI IN-KlL;KIM MIN KYU;CHOUN YOUNG-SUN;SEO JEONG-MOON
    • Nuclear Engineering and Technology
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    • v.37 no.2
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    • pp.191-200
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    • 2005
  • Shaking table tests of the seismic behavior of a steel frame structure model were performed. The purpose of these tests was to estimate the effects of a near-fault ground motion and a scenario earthquake based on a probabilistic seismic hazard analysis for nuclear power plant structures. Three representative kinds of earthquake ground motions were used for the input motions: the design earthquake ground motion for the Korean nuclear power plants, the scenario earthquakes for Korean nuclear power plant sites, and the near-fault earthquake record from the Chi-Chi earthquake. The probability-based scenario earthquakes were developed for the Korean nuclear power plant sites using the PSHA data. A 4-story steel frame structure was fabricated to perform the tests. Test results showed that the high frequency ground motions of the scenario earthquake did not damage the structure at the nuclear power plant site; however, the ground motions had a serious effect on the equipment installed on the high floors of the building. This shows that the design earthquake is not conservative enough to demonstrate the actual danger to safety related nuclear power plant equipment.

765kV Substations Earthquake Monitoring System and Preliminary Data Analysis (765kV 변전소 지진계측시스템 구축과 관측자료 예비분석)

  • Park, Dong-Hee;Yun, Kwan-Hee;Seo, Yong-Pyo;Kim, Byung-Chel
    • Proceedings of the Earthquake Engineering Society of Korea Conference
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    • 2006.03a
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    • pp.56-63
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    • 2006
  • Facilities of 76skV Substation(S/S) play an important role in electric power supply grids. Various power facilities of 765kV S/S might be damaged enormously if a strong earthquake occurs. In an effort to mitigate possible earthquake disasters, KEPRI (Korea Electric Power Research Institute) set forth plans to verify seismic safety of the facilities of 765kV S/S. To accomplish the task, an earthquake monitoring systems is constructed at four 765kV S/S sites(Shin-AnSung, Shin-TaeBaek, Shin-SeoSan and Shin-GaPyung). Data from these earthquake monitoring stations are being transmitted via satellite communication. Currently, KEPRI is operating an earthquake monitoring system in freefield of Shin-SeoSan S/S (NSS) tentatively, Also, the data from NSS is preliminarily analyzed using the horizontal to vertical (H/V) spectrum ratio method. The method of H/V spectrum ratio has been used to infer site amplification without previous knowledge of near surface geology. The results of data analysis shorts good S/N ratio and amplification of 20-25 Hz by site effect. In the near future, the accumulated data is expected to provide a basis for assessing and predicting any damages to integrity of 765kV S/S facilities by earthquakes.

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Evaluation of Seismic Design Force by Earthquake Response Analysis of Water Tanks Installed in RC Buildings (건축물에 설치된 물탱크의 지진응답해석을 통한 설계하중 평가)

  • Baek, Eun Rim;Oh, Ji Hyeon;Choi, Hyoung Suk;Lee, Sang Ho
    • Journal of the Earthquake Engineering Society of Korea
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    • v.23 no.4
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    • pp.221-229
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    • 2019
  • Several water tanks installed in the building were damaged during the Gyeongju earthquake (2016) and the Pohang earthquake (2017). Since a water tank for fire protection is very important component, seismic safety should be ensured. In this study, an interaction between a water tank and a building was studied by the dynamic analysis of the RC building with the water tank. In case the water tank was installed on the roof of the RC building, it was confirmed that it did not significantly affect the response of the building. Based on the result, dynamic response characteristics of the water tank in the building were studied using two SDOF models represented dynamic behavior of the water tanks under earthquake. An earthquake time-history analysis was carried out with variables of aspect ratio of the tank, story of the building, and installed location in the building using three kinds of earthquakes.

Development of An Optimum Model Using Safety-Related Equipment Qualification for the Air Conditioner in the Nuclear Power Plant (원자력 발전소에 사용되는 항온항습기의 안전관련 기기검증을 통한 최적 모델 개발)

  • Sur, Uk-Hwan;Lee, Yeong-Seop
    • Journal of the Korean Society of Safety
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    • v.21 no.1 s.73
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    • pp.1-5
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    • 2006
  • The damage of important equipments for the nuclear power plant by the earthquake brings the loss of human lives and economic losses. Therefore safety-related equipment of nuclear power plant must be proved that function must be designed and structural integrity so that it can be maintained also from accident condition of various kinds. In this study, the computer room air conditioner to be delivered at the nuclear power plant applied to this qualification, try to develop an optimum model. This model ended up with good results which were under suitably allowable conditions about structurally safe earthquake.