• Proceedings of the Computational Structural Engineering Institute Conference
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• 2010.04a
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• pp.653-656
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• 2010

월성 1호기 격납건물에 대하여 극한내압하중에 대한 확률론적 취약도 평가를 수행하였다. 격납건물 성능의 불확실성은 가동중 검사 결과를 통해 얻어진 재료 물성치 중앙값과 텐던 긴장력 중앙값을 적용하여 고려하였다. 격납건물은 개구부를 고려하여 3차원 유한요소로 모델링하였으며, 확률론적 취약도 평가를 위하여 대규모의 비선형 유한요소 해석 모델을 적용하기에 적합한 효율적인 취약도 평가 기법을 개발하였다. 월성 1호기 격납건물에 대한 취약도 평가 결과, 벽체 중단부가 극한내압발생으로 인한 방사능물질 누출에 가장 취약한 것으로 나타났으며, 중앙값 성능은 약 55psi, 고신뢰도 저파괴 파괴확률값인 HCLPF(High Confidence Low Probability of Failure)는 약 29psi를 나타내었다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.20 no.2
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• pp.184-192
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• 2024

This paper evaluates the ultimate pressure capacity (UPC) of a prestressed concrete containment building, considering the loss of prestress. A three-dimensional finite element model with openings was utilized for the UPC evaluation, and material properties reflecting severe accident temperatures were applied. The failure criteria were established based on the strain of the liner plate in accordance with the regulatory guidelines. When the prestress was reduced by approximately 14% from its initial value, the UPC decreased by about 4%. This study acknowledges limitations in the determination of nonlinear material properties, realistic prestress losses, and failure criteria. Further research to address these limitations could enhance the accuracy of UPC evaluation.

• Proceedings of the Computational Structural Engineering Institute Conference
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• 2011.04a
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• pp.388-391
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• 2011

이 논문에서는 인도의 BARC에서 가압중수형 격납건물의 선형탄성 거동 및 균열의 발생형상과 극한내압 평가를 위해서 건설한 1/4 축소모델 격납건물에 대하여 실험한 결과와 유한요소 해석에 의한 결과를 비교 분석하였다. 유한요소 해석은 상용프로그램인 ABAQUS를 이용하였고 각각의 구조재료에 대한 수치 해석모델을 작성하여 내압해석을 수행하였다.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.24 no.4
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• pp.449-455
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• 2011

Recently, international collaborative research which was organized at Bhabha Atomic Research Centre in India, was conducted to develop for pressure capacity and nonlinear behavior of PHWR 1/4 scale nuclear containment building between experimental test and numerical code. In this paper, a nonlinear finite element analysis was carried out in order to predict ultimate pressure capacity and nonlinear behavior of the 1/4 scale containment building. The 1/4 scale containment building is consisted of basemat, cylinder wall, dome and 4-buttress. For the finite element analysis, commercial program ABAQUS was used. Finite element models including concrete, rebar and tendon have been developed for assessment of ultimate pressure capacity and failure mode for nuclear containment building. From the analysis results, first crack of the concrete, the yielding of the rebar and ultimate capacity pressure occurred at $1.6P_d$(design pressure), $3.36P_d$ and $4.0P_d$, respectively.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.27 no.2
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• pp.103-111
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• 2014

In this study, the probabilistic internal pressure fragility analysis was performed by using the non-linear finite element analysis method. The target structure is one of the containment buildings of typical domestic pressurized water reactors(PWRs). The 3-dimensional finite element model of the containment building was developed with considering the large equipment hatches. To consider uncertainties in the material properties and structural capacities, we performed the sensitivity analysis of the ultimate pressure capacity with respect to the variation of four important uncertain parameters. The results of the sensitivity analysis were used to the selection of the probabilistic variables and the determination of their probabilistic parameters. To reflect the present condition of the tendon pre-stressing force, the data of the pre-stressing force acquired from the in-service inspections of tendon forces were used for the determination of the median value. Two failure modes(leak, rupture) were considered and their limit states were defined to assess the internal pressure fragility of target containment building. The internal pressure fragilities for each failure mode were evaluated in terms of median internal pressure capacity, high confidence low probability of failure(HCLPF) capacity, and fragility curves with respect to the confidence levels. The HCLPF capacity was 115.9 psig for leak failure mode, and 125.0 psig for rupture failure mode.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.23 no.4
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• pp.445-452
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• 2010

In this paper an assessment of the internal pressure fragility of the CANDU type containment buildings is performed. The uncertainties of the performance of the containment buildings, material properties and tendon characteristics are referred from the in-service reports of Wolsung Unit 1. The containment buildings are modeled as a three-dimensional finite elements with considering the major opening and penetrations. A new method to evaluate the probabilistic fragility of the massive structural system is developed. The fragility curves of the target containment building are presented with repect to the failure modes and reliability levels. The center of wall is reveled as the most weak structural component of the containment building in the sense of the rupture and catastrophic rupture failure modes.

• Bulletin of the Society of Naval Architects of Korea
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• v.39 no.2
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• pp.75-82
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• 2002

잠수함 설계는, 내압(내압)성능 유지를 위해 효과적인 공간 활용이 어려운 원통형의 구조를 가질 뿐 아니라 제한된 공간에 다양한 장비들을 배치해야 하고,수 심 수백 미터의 극한 환경에서 3차원 운동을 하는 등의 환경 및 운용특성으로 인하여 수상 선박에 비해 많은 경험과 고난도의 기술들이 요구된다. 본문에서는, 해외의 유수한 대학 및 설계 기관과의 공동설계를 수행한 경험과 13년여에 걸친 장보고급 잠수함 건조기간 중에 수행한 수 차례의 역설계 과정 등을 통하여 습득한 설계 기술과 자료들을 바탕으로, 대우조선해양에서 자체 개발한 잠수함 기본설계 시스템(SUB-21)을 이용하여 수행한 중형잠수함 설계결과에 대해 간략하게 소개하고자 한다. 본 SUB-21의 개발은 잠수함 기본설계의 핵심 과정인 배치, 선형개발, 저항, 추진, 조종 및 압력선체 설계뿐만 아니라 디젤발전기-축전지-추진전동기로 구성되는 추진계통의 최적화 과정을 실시간으로 처리할 수 있기 때문에 기본설계에 소요되는 시간을 획기적으로 절감할 수 있으며 기본설계 결과의 신뢰성 제고에 크게 기여할 수 있을 것이다.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.29 no.6A
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• pp.577-585
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• 2009

A 9-node degenerated shell finite element(FE), which has been developed for assessment of ultimate pressure capacity and nonlinear analysis for nuclear containment building is described in this paper. Reissner-Midnlin(RM) assumptions are adopted to develop the shell FE so that transverse shear deformation effects is considered. Material model for concrete prior to cracking is constructed based on the equivalent stress-equivalent strain relationship. Tension stiffening model, shear transfer mechanism and compressive strength reduction model are used to model the material behavior of concrete after cracking. Niwa and Aoyagi-Yamada failure criteria have been adapted to find initial cracking point in compression-tension and tension-tension region, 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.

• 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.

• Journal of the Korea Concrete Institute
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• v.15 no.1
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• pp.60-68
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• 2003

Tension tests of six half-thickness concrete containment wall elements were conducted as a part of Korea Atomic Energy Research Institute (KAERI) program. The aim of the KAERI test program is to provide a test-verified analytical method for estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The data from the tests reported herein should be useful for benchmarking analytical method that require modeling of material behavior including concrete cracking behavior and reinforcement/concrete interaction exhibited by the test. Major test variable is compressive strength of concrete, and its effect on the behavior of prestressed concrete panel subjected to biaxial tension is investigated.