• Title/Summary/Keyword: Seismic Margin

검색결과 120건 처리시간 0.029초

멕시코만 Main Pass 해역의 중생대-신생대 퇴적층의 탄성파층서 (Seismic Stratigraphy of the post-Paleozoic Sedimentary Section in the Main Pass area, Northern Gulf of Mexico)

  • 서만철
    • 한국석유지질학회지
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    • 제4권1_2호
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    • pp.1-11
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    • 1996
  • 미국 멕시코만 Main Pass해역의 심부 다중탄성파단면도를 해석하여 이 지역의 층서와 퇴적사에 대한 연구를 수행하였다. 탄성파단면을 이용한 구조해석을 통하여 기반암과 과거의 대륙붕단 위치에 대한 새로운 정보를 밝힐 수 있었다. 기반암은 미시시피 대륙붕의 탄성파 측선 LSU-1 북단에서 $7.5{\cal}Km$ 깊이에 존재함이 밝혀졌다. 또한, 쥬라기 -백악기 초기에는 대륙붕단이 거의 같은 지점에 위치하였으나 신생대 올리고세에는 그보다 약 28 Km 대륙쪽에 위치함이 밝혀졌다. 중생대-신생대 퇴적층은 10개의 탄성파층서단위 (seismic stratigraphic sequence) 로 구분되며 , 멕시코만 주변의 다른 해역과 비교해볼 때 주된 광역부정합면은 중기 마이오세 (10.5 Ma), 중기올리고세 (30 Ma), 중기 백악기 (97 Ma) 와 쥬라기말 (131 Ma)에 형성되었음을 알 수 있다 연구해역은 퇴적사로 볼 때 3개의 현저한 시기로 나눌 수 있는바; (1)멕시코만 열림 -중기 백악기 사이의 천해퇴적 환경; (2)중기 백악기 -중기 올리고세 사이의 심해퇴적환경; (3)중기 을리고세 이후의 천해퇴적환경으로 구분된다. 멕시코만 북부해역에 위 치하는 Main Pdss해역과 동북부 해역에 위치하는 Destin Dome 지역에서 시추된 시추자료와 탄성파자료를 종합하여 해석한 결과 멕시코만 북부 퇴적분지가 후기백악기부터 육성기원의 쐐기 (wedge)형태로 발달되기 시작하였음을 알 수 있다.

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미국남동부 대륙주변부의 기원 : 화산성 혹은 비화산성? (The Origin of the Southeastern United States Continental Margin: Is it Volcanic or Non-Volcanic?)

  • 오진용
    • 자원환경지질
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    • 제27권6호
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    • pp.571-577
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    • 1994
  • 미국 대서양 대륙주변부는 북미와 아프리카 대륙의 중생대 분열의 산물로서 화산성 기원 혹은 비화산성 기원인가에 대해 논란이 있어 왔다. 이를 규명하기 위하여 미국 남동부 해안에서 채취한 다채널 탄성파 단면도에 나타난 기반암들의 영상을 조사하였다. 가장 핵심적인 탄성파 영상의 하나는 전체적으로 쐐기 형상을 보이는 해양방향의 경사반사층들(seaward-dipping reflectors; SDR)이다. 이들은 화산성 열개주변부의 상징적인 기반암 구조로 알려져 있다. 연구지역에는 2 개조의 해양경사층 쐐기구조가 존재하였다: 하나는 기반암 경첩대 (basement hinge zone) 부근이고 ('the hinge SDR wedge'라고 명명), 다른 하나는 미국 동해안 자기이상대 (the East Coast magnetic anomaly)의 바다 쪽에 위치한다 ('the outer SDR wedge'라고 명명). 또한, 기반암 경첩대의 동쪽 지각에서는 "7.2 km/s 층"으로 알려진 높은 속도의 하부지각층과 함께 원만한 기복의 모호 불연속면 등이 관찰되었다. 이러한 기반암 구조와 잘 알려진 화산성 기원의 대륙주변부의 지각구조를 비교해 보아 미국 남동부 대륙주변부를 화산성 기원의 대륙주변부로 특징지었다.

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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.

Aspect ratios of code-designed steel plate shear walls for improved seismic performance

  • Verma, Abhishek;Sahoo, Dipti R.
    • Steel and Composite Structures
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    • 제42권1호
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    • pp.107-121
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    • 2022
  • Past studies have shown that the aspect ratio (width-to-height) of a steel plate shear wall (SPSW) can significantly affect its seismic response. SPSWs with lower aspect ratio (narrow SPSW) may experience low lateral stiffness and flexure dominated drift response. As the height of the frame increases, the narrow SPSWs prove to be uneconomical and demonstrate inferior seismic response than their wider counterparts. Moreover, the thicker web plates required for narrow SPSWs exerts high inward pull on the VBEs. The present study suggests the limiting values of the aspect ratio for an SPSW system by evaluating the seismic collapse performance of 3-, 6- and 9-story SPSW systems using FEMA P695 methodology. For this purpose, nonlinear models are developed. These models are validated with the past quasi-static experimental results. Non-linear static analyses and Incremental dynamic analyses are then carried. The results are then utilized to conservatively suggest the limiting values of aspect ratios for SPSW system. In addition to the conventional-SPSW (Conv-SPSW), the collapse performance of staggered-SPSW (S-SPSW) is also explored. Its performance is compared with the Conv-SPSW and the use of S-SPSW is suggested in the cases where SPSW with lower than recommended aspect ratio is desired.

고강도 철근콘크리트 교각의 내진거동특성 (Characteristic Behavior of High-Strength Reinforced Concrete Bridge Column under Simulated Seismic Loading)

  • 나홍성;이경준;류효진;황선경;이진옥
    • 한국콘크리트학회:학술대회논문집
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    • 한국콘크리트학회 2004년도 춘계 학술발표회 제16권1호
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    • pp.22-27
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    • 2004
  • This experimental investigation was conducted to examine the seismic performance of reinforced concrete bridge columns. The columns were subjected to a constant axial load and a cyclic horizontal load-inducing reversed bending moment. The variables studied in this research are the volumetric ratio of transverse reinforcement (ps = 0.96, 1.44 per cent) and axial load ratio (0.05, 0.1, 0.2 P/Po) and strength $(350kgf/cm^2,\;600kgf/cm^2)$. Test results show that bridge columns with 50 per cent higher amounts of transverse reinforcement than that required by seismic provisions of ACI 318-02 showed ductile behaviour. For bridge columns with axial load ratio(P/Po) less than 0.2, the ratio of Mmax over Mad, nominal moment capacity predicted by ACI 318-02 provisions, is consistently greater than 1 with approximately a 20 percent margin of safty.

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Conceptual Safety Design Analyses of Korea Advanced Liquid Metal Reactor

  • Suk, S.D.;Park, C.K.
    • Nuclear Engineering and Technology
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    • 제31권6호
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    • pp.66-82
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    • 1999
  • The national long-term R&D program, updated in 1997, requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor(KALIMER), along with supporting R&D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R&D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of HAMMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation.

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반복 횡하중을 받는 철근콘크리트 교각의 내진성능에 관한 실험적 연구 (An Experimental Study on Seismic Performance of Reinforced Concrete Bridge Columns under Lateral Cyclic Load)

  • 이진옥;윤현도;황선경;류효진;나홍성;이경준
    • 한국콘크리트학회:학술대회논문집
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    • 한국콘크리트학회 2003년도 가을 학술발표회 논문집
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    • pp.161-164
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    • 2003
  • This experimental investigation was conducted to examine the seismic performance of reinforced concrete bridge columns. The columns were subjected to a constant axial load and a cyclic horizontal load-inducing reversed bending moment. The variables studied in this research are the volumetric ratio of transverse reinforcement ($P_s$ =0.96, 1.44 per cent) and axial load ratio (0.05, 0.1, 0.2 P/$P_o$). Test results show that bridge columns with 50 per cent higher amounts of transverse reinforcement than that required by seismic provisions of ACI 318-02 showed ductile behaviour. For bridge columns with axial load ratio(P/$P_o$) less than 0.2, the ratio of $M_{max}$ over $M_{aci}$, nominal moment capacity predicted by ACI 318-02 provisions, is consistently greater than 1 with approximately a 20 percent margin of safty.

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원자로구조물의 지진응답 민감도해석 (Sensitivity Analysis on the Seismic Responses of the Reactor Structures)

  • 이재한;김종범;구경회;김종인;유봉;최순
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 1993년도 봄 학술발표회논문집
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    • pp.183-190
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    • 1993
  • The seismic response of the reactor structures depends on the dynamic charact-eristics of the structures and the input earthquake loadings. The stuctural integ-rity of the reactor internal components can be verified by the dynamic response analyses to implement the effects of the design loadings like earthquakes. The sensitivity analyses of the dynamic characteristics for the analytical model of reactor structures considering the possible variations of the stiffnesses of the CSB upper flange and the snubber were performed to improve the dynamic characteri-stics of the structures against seismic loading. And to enhance the structural design margin of the reactor internal components the nonlinear time history analyses were attempted for the modified analytical model, and the results were compared between the reference model and the modified ones.

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횡하중에 대한 점성 및 점탄성감쇠기의 진동제어성능의 비교 (Comparison of Motion Control Capacity of Viscous and Viscoelastic Dampers for Lateral Loads)

  • 김진구;김유경
    • 한국구조물진단유지관리공학회 논문집
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    • 제5권2호
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    • pp.155-162
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    • 2001
  • In this study a structure with viscoelastic and viscous dampers with identical damping coefficient subjected to stationary seismic and wind load were analyzed in time and frequency-domain to compare motion control capability of viscous and viscoelastic dampers. The dampers were placed based on story drift and acceleration obtained from RMS responses. According to the analysis results, the motion control capability of viscous dampers turned out to be superior to that of the viscoelastic dampers for the case of seismic load. On the contrary, in case of wind load, the viscoelastic dampers were more effective in the mitigation of dynamic responses. However, it was also found that the differences were in a narrow margin.

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열화를 고려한 원자력발전소 철근콘크리트 보의 지진 취약도 해석 (Seismic Fragility Analysis of Deteriorated Reinforced Concrete Beams in Nuclear Power Plants)

  • 이명규;김문수;정연석;김인수;고성기
    • 한국콘크리트학회:학술대회논문집
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    • 한국콘크리트학회 2005년도 봄학술 발표회 논문집(I)
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    • pp.235-238
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    • 2005
  • The seismic fragility analyses of reinforced concrete propelled beam are performed to evaluate safety margin. The models were simulated by Latin Hyper-Cube (LHC) method considering various aging-related deterioration of RC beam. Fragility curves under various condition subjected to static load are compared. It is found that the 20$\%$ loss of top and bottom steel 15$\%$ lower than the undegraded beam in the ultimate strength. Seismic fragility analyses were performed to find out the effect of aging-related deterioration on the dynamic behaviour of RC beam.

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