• Magazine of the Korea Concrete Institute
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• v.16 no.1 s.78
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• pp.39-48
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• 2004

• Proceedings of the Korea Concrete Institute Conference
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• 2010.05a
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• pp.139-140
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• 2010

Combined analysis is required for the concrete dome and ring beam of containment structure due to the interaction in section forces. In this study, an efficient design procedure is proposed that can be used to determine the preliminary sections of the dome and ring beam as well as a proper level of prestress in the ring beam, prior to a detailed design. The procedure applies the membrane theory of the shell of revolution.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.14 no.3
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• pp.403-414
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• 1994

Nonlinear analysis of RC containment structure under thermal load and pressure is presented to trace the behaviour after an assumed LOCA. The temperature distribution varying with time through the wall thickness is determined by transient finite element analysis with the two time level scheme in time domain. The layered shell finite elements are used to represent the containment structures in nuclear power plants. Both geometric and material nonlinearities are taken into account in the finite element formulation. The constitutive relation of concrete is modeled according to Drucker-Prager yield criteria in compression. Tension stiffening model is used to represent the tensile behaviour of concrete including bond effect. The reinforcing bars are modeled by smeared layer at the location of reinforcements accounting elasto-plastic axial behaviors. The steel liner model under Von Mises yield criteria is adopted to represent elastic-perfect plastic behaviour. Geometric nonlinearity is formulated to consider the large displacement effect. Thermal stress components are determined by the initial strain concept during each time step. The temperature differential between any two consecutive time steps is considered as a load incremental. The numerical results from this study reveal that nonlinear temperature gradient based on transient thermal analysis will produces excessive large displacement. Nonlinear behavior of containment structures up to ultimate stage can be traced reallistically. The present study allows more realistic analysis of concrete containment structures in nuclear power plants.

• Journal of the Earthquake Engineering Society of Korea
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• v.10 no.6 s.52
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• pp.137-145
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• 2006

Recently, the interests in structural monitoring of civil infrastructures are increased. Especially, as the civil infrastructures such as bridges, tunnels and buildings become large-scale, it is necessary to monitor and maintain the safety state of the structures, which requires smart systems that can supply long-term monitoring during the service time of the structures. In this paper, we investigated the possibilities of fiber optic sensor application to the various structures. We investigate the possibility of using fiber optic Bragg grating sensors to joint structure. The sensors show good response to the structural behavior of the joint while electric gauges lack of sensitivity, durability and long term stability for continuous monitoring. We also apply fiber optic structural monitoring to the composite repaired concrete beam structure. Peel-out effects is detected with optical fiber Bragg grating sensors and the strain difference between main structure and repaired carbon sheets is observed when they separate each other. The real field test was performed to verify the behaviors of fiber Bragg grating sensors attached to the containment structure in Uljin nuclear power plant in Korea as a part of structural integrity test which demonstrates that the structural response of the non-prototype primary containment structures. The optical fiber Bragg grating sensor smart system which is the probable means for long term assessments can be applicable to monitoring of structural members in various civil infrastructures.

• Journal of the Earthquake Engineering Society of Korea
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• v.12 no.6
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• pp.55-63
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• 2008

This paper presents a seismic analysis technique for a 3D soil-structure interaction system in a frequency domain, based on the finite element formulation incorporating frequency-dependent infinite elements for the far field soil region. Earthquake input motions are regarded as traveling P, SV and SH waves which are incident vertically from the far-field soil region, and then equivalent earthquake forces are calculated using impedances of infinite soil by dynamic infinite elements and traction and displacement from free field response analysis. For verification and application, seismic response analyses are carried out for a multi-layered soil medium without structure and a typical nuclear power plant in consideration of soil-structure interaction. The results are compared with the free field response using a one-dimensional analytic solution, and a dynamic response of an example structure from another SSI package.

• Magazine of the Korea Concrete Institute
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• v.9 no.4
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• pp.155-165
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• 1997

Since the biggest time-dependent prestress loss of reactor containment structure is due to creep of concrete. the creep is one of important structural factors to be considered for the safety maintenance in the containment structure during design. construction and main enance. This paper is about the creep charactoristies of concrete for the reactor containment structure. In this paper, creep test was performed to show the creep characteristics of reactor containment concrete structure made of the type-V cement. Then, in order to evaluate the applicability of creep prediction equations of recently revised Korean Concrete Standard Specification(KSCE-96) and Japanes Concrete Standard Specification. ACI-209. CEB/FIP-90. and HANSEN, creep test results were compared with prediction results obtained from he equations. From the comparisons, it was shown that the equation of th KSCE-96 predicts creep for younger concrete than 1 year, better than the other equations and that all of the equations predicts creep, for older concrete than 1 year, smaller than test. From regression analysis. a creep prediction equation which effectively predicts creep of concrete due to loading after 1year was proposed.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.19 no.1 s.71
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• pp.93-103
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• 2006

It is absolutely essential that safety assessment of the containment buildings during service life because containment buildings are last barrier to protect radioactive substance due to the accidents. Therefore, this study describes an enhanced degenerated shell finite element(FE) which has been developed for nonlinear FE analysis of reinforced concrete(RC) containment buildings with elasto-plastic material model. For the purpose of the material nonlinear analysis, Drucker-Prager failure criteria is adapted in compression region and material parameters which determine the shape of the failure envelop are derived from biaxial stress tests. Reissner-Mindlin(RM) assumptions are adopted to develop the degenerated shell FE so that transverse shear deformation effects is considered. However, it is found that there are serious defects such as locking phenomena in RM degenerated shell FE since the stiffness matrix has been overestimated in some situations. Therefore, shell formulation is provided in this paper with emphasis on the terms related to the stiffness matrix based on assumed strain method. Finally, the performance of the present shell element to analysis RC containment buildings is tested and demonstrated with several numerical examples. From the numerical tests, the present results show a good agreement with experimental data or other numerical results.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.392-397
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• 1996

지반특성에 따라 지진발생시 면진구조물과 비면진 구조물의 응답특성이 어떠한가를 평가하기위해, 1940 El Centro 지진을 입력지진으로 하고, 면진구조물로는 가압경수형 원자로격납건물을 이용하여 수평(NS) 및 수직지진입력에 대한 시간이력해석을 수행하였다. 0.5Hz 수평면진 구조물의 경우 수평방향 가속도응답은 지반특성에 무관하게 거의 변화가 없으며, 또 2Hz 이상에서 비면진구조물의 수평지진가속도응답보다 현저히 낮은 가속도응답을 갖는다. 면진베어링의 수직방향 21Hz 고유진동수는 풍화암의 경우 수직방향 가속도응답에 영향을 주지 않으나. 경암의 경우 원자로지지점에서의 수직방향 가속도응답을 전반적으로 증가시킨다. 비면진 구조물의 경우 지반의 강성이 약할수록 가속도응답이 비교적 큰 폴라크레인위치에서 수평 및 수직방향 가속도응답이 감소되는 것으로 나타났으며, 특히 수직방향의 가속도응답이 크게 감소하는 것으로 나타났다.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.20 no.3
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• pp.353-364
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• 2007

In this paper, a nonlinear finite element analysis program NUCAS, which has been developed for assessment of ultimate pressure capacity and failure mode for nuclear containment building is described. Degenerated shell element with assumed strain method and low-order solid element with enhanced assumed strain method is adapted to microscopic material and elasto-plastic material model, respectively. Finally, the performance of the developed program is tested and demonstrated with several examples. From the numerical tests, the present results show a good agreement with experimental data or other numerical results.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.596-602
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• 1998

한국의 차세대 원자로 (Korean Next Generation Reactor; KNGR)에 처음 적용되는 격납건물내에 설치된 재장전수조 (In-Containment Refueling Water Storage Tank; IRWST)는 기존 재장전수조의 기능외에 주입모드에서 재순환 모드를 전환생략, 일차계통으로 방출된 고온, 고압 냉각수의 응축 및 냉각 격납용기 방사능 오염방지, 원자로 동공층수 등 여러 가지 추가 기능을 가진 한층 진보된 설계개념이다. 발전소 천이사고 시 발생하는 Pipe Clearing, 응축진동 현상(Condensation Oscillations), Chugging 등의 열수력 현상들이 방출증기의 유동 및 가속도와 관련해 항력과 응력, 압력진동 등을 일으켜 IRWST 구조물에 영향을 미칠 수 있기 때문에 IRWST를 처음으로 시도하는 우리 나라로서는 이와 관련된 제반현상에 대한 심도 깊은 연구가 요구된다. 따라서 본 연구에서는 원자력 발전소 과도로 인한 가압기 안전밸브(Pressurizer Safety Valve) 또는 안전감압밸브(Safety Depressurization Valve) 작동시 IRWST로 방출되는 유체로 야기되는 하중 예측 모델을 기존의 BWR의 응축수조(suppression Pool)에서 일어나는 각종 현상을 토대로 이론적으로 체계적으로 유도하여 이를 비교, 분석하였다.