• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 1989년도 봄 학술발표회 논문집
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• pp.22-27
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• 1989

This paper presents a study of soil-structure interaction problems using infinite elements. The infinite elements are formulated for homogeneous and layered soil media, based on approximate expressions for three components of propagating waves, namely Rayleigh, compressive and shear waves. The integration scheme which was proposed for problems with single wave component by Zienkiewicz is expanded to the multi-wave problem. Verifications are carried out on rigid circular footings which are placed on and embedded in elastic half space. Numerical analysis is performed for a containment structure of a nuclear power plant subjected seismic excitation.

• 한국농공학회지
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• 제38권3호
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• pp.82-91
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• 1996

This is a basic study for the static and dynamic analysis on the elasto-plastic and elasto-viscoplastic of an axi-symmetric shell. The objective of this study was to investigate the mechanical characteristics of a nuclear reinforced concrete containment structure, which was selected as a model, by a numerical analysis using a finite element method. The structure was modeled with discrete ring elements of 8-noded isoparametric element rotating against the symmetrical axis, and the interaction between the foundation and the structure was modeled by Winkler's model. Also, the meridional tendon was modeled with 2-node truss elements, and the hoop tendon was done with point elements in two degrees of freedom. The effect of the tendon was considered without the increasement in total degree of freedom as the stiffness matrix of modeled tendon elements was assembled on the stiffness matrix of ring elements linked with the tendon. The results obtained from the analysis of an example were summarized as follows : 1. The stresses in the hoop direction on the interior and exterior surfaces of the structure were shown in changes of similar trend, and high stresses appeared on the structure wall 2. The stresses in the meridional direction on the interior and exterior surfaces were shown in change of different trend. Especially, the stresses at the junctions between the dome and the wall and between the wall and the bottom plate of the structure were very high, compared with those at other parts of the structure. 3. The stress changes in the direction of thickness on the crown of the dome were much linearly distributed. However, as the amount of tendon increased, the stresses in the upper and lower parts of the wall established with the tendon were shown stress concentration. 4. The stress changes in the direction of thickness on the center of the structure wall was linearly distributed in the all cases, and special stress due to the use of the tendon was not shown.

• Computers and Concrete
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• 제13권1호
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• pp.1-16
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• 2014

To evaluate the behavior of the advanced unbonded pre-stressed concrete containment vessel (UPCCV) for one typical China nuclear power plant under Japan's March 11 earthquake, five nonlinear time history analysis and a nonlinear static analysis of a 1:10 scale UPCCV structure have been carried out with MSC.MARC finite element program. Comparisons between the analytical and experimental results demonstrated that the developed finite element model can predict the earthquake behavior of the UPCCV with fair accuracy. The responses of the 1:10 scale UPCCV subjected to the 11 March 2011 Japan earthquakes recorded at the MYG003 station with the peak ground acceleration (PGA) of 781 gal and at the MYG013 station with the PGA of 982 gal were predicted by the dynamic analysis. Finally, a static analysis was performed to seek the ultimate load carrying capacity for the 1:10 scale UPCCV.

• Structural Engineering and Mechanics
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• 제58권5호
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• pp.799-823
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• 2016

A finite element model for the non-linear dynamic analysis of a reinforced concrete (RC) containment shell of a nuclear power plant subjected to extreme loads such as impact and earthquake is presented in this work. The impact is modeled by using an uncoupled approach in which a load function is applied at the impact zone. The earthquake load is modeled by prescribing ground accelerations at the base of the structure. The nuclear containment is discretized spatially by using 20-node brick finite elements. The concrete in compression is modeled by using a modified $Dr{\ddot{u}}cker$-Prager elasto-plastic constitutive law where strain rate effects are considered. Cracking of concrete is modeled by using a smeared cracking approach where the tension-stiffening effect is included via a strain-softening rule. A model based on fracture mechanics, using the concept of constant fracture energy release, is used to relate the strain softening effect to the element size in order to guaranty mesh independency in the numerical prediction. The reinforcing bars are represented by incorporated membrane elements with a von Mises elasto-plastic law. Two benchmarks are used to verify the numerical implementation of the present model. Results are presented graphically in terms of displacement histories and cracking patterns. Finally, the influence of the shear transfer model used for cracked concrete as well as the effect due to a base slab incorporation in the numerical modeling are analyzed.

• 한국지진공학회논문집
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• 제19권1호
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• pp.1-11
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• 2015

In order to perform a soil-isolation-structure interaction analysis of seismically isolated nuclear power plant (NPP) structures, the nonlinear behavior of a seismic isolation system may be converted to an equivalent linear model used in frequency domain analysis. Seismic responses for seismically isolated NPP containment structures subjected to a simple artificial acceleration history and different site class earthquakes are evaluated for the equivalent-linear and nonlinear models that have been applied to lead-rubber bearing (LRB) modeling. It can be observed that the maximum displacements of the equivalent linear model are larger than that of the nonlinear model. From the floor response spectrum analysis for the top of NPP containment structures, it can be observed that the spectral acceleration of an equivalent linear model at about 0.5 Hz frequency is about 2~3 times larger than that of a nonlinear model.

• 한국콘텐츠학회논문지
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• 제9권6호
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• pp.25-36
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• 2009

본 논문에서는 RFID 시스템에서 많이 발생하는 경로 질의와 포함 관계 질의를 효과적으로 처리하기 위한 데이터 관리 기법을 제안한다. 제안하는 데이터 관리 기법은 다양한 포함 관계에 대한 경로 정보를 유연하게 표현함으로써 운송 도중 발생하는 포함 관계의 변경 및 개별 단위의 물품 경로까지 지원한다. 또한, 공급망의 구조 정보를 활용한 경로 정보의 압축으로 저장되는 데이터의 양을 감소시킬 수 있다. 기존 기법들과 비교 평가를 수행한 결과 저장 공간과 질의 처리 측면에서 성능이 향상됨을 확인할 수 있었다.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4179-4188
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• 2021

This study identifies efficient earthquake intensity measures (IMs) for seismic performances and fragility evaluations of the reactor containment building (RCB) in the advanced power reactor 1400 (APR1400) nuclear power plant (NPP). The computational model of RCB is constructed using the beam-truss model (BTM) for nonlinear analyses. A total of 90 ground motion records and 20 different IMs are employed for numerical analyses. A series of nonlinear time-history analyses are performed to monitor maximum floor displacements and accelerations of RCB. Then, probabilistic seismic demand models of RCB are developed for each IM. Statistical parameters including coefficient of determination (R²), dispersion (i.e. standard deviation), practicality, and proficiency are calculated to recognize strongly correlated IMs with the seismic performance of the NPP structure. The numerical results show that the optimal IMs are spectral acceleration, spectral velocity, spectral displacement at the fundamental period, acceleration spectrum intensity, effective peak acceleration, peak ground acceleration, A95, and sustained maximum acceleration. Moreover, weakly related IMs to the seismic performance of RCB are peak ground displacement, root-mean-square of displacement, specific energy density, root-mean-square of velocity, peak ground velocity, Housner intensity, velocity spectrum intensity, and sustained maximum velocity. Finally, a set of fragility curves of RCB are developed for optimal IMs.

• 한국전산구조공학회논문집
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• 제20권1호
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• pp.83-92
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• 2007

대형의 유체-구조물 연계시스템(FSI) 해석을 위해 많은 수치기법들이 있지만, 유체의 슬로싱에 의해 발생되는 집중적이고 불규칙한 동수압의 영향 때문에, 신뢰할 수 있는 수치 결과와 수치안정성을 확보하기 위해 매우 조밀한 메쉬를 필요로 한다. 그 결과, 신뢰할 수 있는 장기적인 시간 응답을 구하기 위한 수치해석은 상당히 많은 CPU 시간을 요구한다. 본 논문의 목적은 국부 상세 모델을 이용하여 LNG운반선의 화물창 시스템의 유탄성적 거동을 해석하기 위한 전역-국부 해석기법을 제시하고자 한다. 본 논문에서 제시한 해석기법의 타당성을 증명하고 이 기법을 통해 LNG운반선 화물창 시스템의 국부응답을 효율적으로 예측한 결과를 제시하였다.

• 한국가스학회지
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• 제11권4호
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• pp.85-90
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• 2007

본 논문에서는 유한요소법을 사용하여 댐핑안전 구조물을 설치한 완전밀폐식 LNG 저장탱크 시스템의 강도안전성에 대해 해석하였다. 내부탱크의 FEM 해석을 위해, 탱크에 저장된 LNG에 의한 유체정압, 초저온 온도하중, BOG 압력, LNG 자중량, 내부탱크의 코너 측벽면에 가해진 침하하중 등과 같은 모든 복합하중을 내부탱크 구조물에 적용하였다. FEM 계산결과에 의하면 기존의 내부탱크는 주어진 모든 하중 조건에 대하여 안전하지만, 압축 스프링과 같은 댐핑안전 구조물은 탱크시스템의 안전성을 확보하는데 대단히 유용한 구조물일 것이라는 사실이다. 따라서 스프링의 강점도를 높이고 최적의 설치위치를 찾으면 스프링 구조물에 의해 탱크시스템의 댐핑강도 안전성을 증가시킬 수 있는 중요한 설계요소가 될 것이다.

• 한국가스학회:학술대회논문집
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• 한국가스학회 2001년도 추계학술발표회 논문집
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• pp.122-129
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• 2001