• Journal of the Korea Academia-Industrial cooperation Society
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• v.20 no.8
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• pp.362-370
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• 2019

The internal pressure capacity of a modular containment structure requires analysis to prevent the release of radioactive material in the case of an accident. To analyze the capacity, FEM models were prepared while considering the tendon arrangements and the contact surfaces between precast concrete modules, and then static analyses were carried out. The changing characteristics in the displacement and stress under step-wise loading were analyzed, along with the effects of selected parameters. For comparison, the capacity of a monolithic containment structure was also analyzed. Parametric analyses were done to suggest ranges of parameters such as the tendon force, tendon spacing, tendon location in concrete thickness direction, friction coefficient, and concrete thickness. The tendon force and frictional force provide a combined effect between contact surfaces of modules. The same level of internal pressure capacity can be secured even in the modular containment structure as in the monolithic containment structure by increasing the tendon force with additional tendons.

• 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.

• Proceedings of the Korean Society of Disaster Information Conference
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• 2023.11a
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• pp.303-304
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• 2023

확률론적 위험성 평가는 하중, 재료특성 등과 같은 불확실성 인자를 고려하여 구조물의 안전성을 평가하는 기법이지만 모든 불확실성을 고려하는 것은 현실적으로 불가능하다. 또한 원전 격납건물은 콘크리트, 철근, 라이너, 텐던이 복잡하게 결합되어 있다. 따라서 전역민감도 분석을 통해 격납건물의 불확실성 인자 검토하고 선정하는 작업은 필요하다. 따라서 본 연구는 대리모델을 기반으로 축소규모 원전 격납건물의 전역 민감도 분석을 수행하고 격납건물의 주요 영향인자를 분석하고자 한다. 유한요소 해석 모델을 기반으로 대리모델의 학습데이터를 생성하였으며 구축된 대리모델의 성능지표를 분석하였을 때 높은 회귀성능을 갖는 것으로 판단된다. 대리모델을 기반으로 전역 민감도 분석을 수행한 결과 콘크리트의 인장균열이 발생하는 내압수준에서 민감도 지수는 콘크리트의 압축강도가 높지만, 전체적인 내압 구간에서 민감도 지수는 텐던의 탄성계수 및 항복강도가 높은 것으로 나타났다.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.21 no.1
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• pp.409-416
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• 2020

The seismic performance of a containment structure should be secured to maintain the structural soundness of a containment structure under various earthquakes that occur globally. Therefore, an analysis of the seismic performance of a modular containment structure for a small modular reactor is also required. To analyze the seismic performance of modular containment, FEM models with contact surfaces between the modules and tendon were prepared and the modal and seismic analyses were performed. The displacement, stress, and gap size of modular containment under earthquake wave were analyzed. The effects of the tendon force, friction coefficient, and earthquake wave on the seismic performance were analyzed. The seismic performance of monolithic containment was also analyzed for comparison. In the 1st and 2nd natural modes, which most likely affect, the modular containment showed horizontal dynamic behavior, which is similar to monolithic containment, because of the combined effects of the tendon force and friction force between modules. When the combined effect is sufficient, the seismic performance of the modular containment is secured over a certain level. An additional increase in seismic performance is expected when some material with a larger friction coefficient is adopted on the contact surface.

• Nuclear Engineering and Technology
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• v.28 no.2
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• pp.129-136
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• 1996

Influence diagram method is applied to containment performance analysis of Young-Gwang 3&4 in an effort to overcome some drawbacks of current containment performance analysis method. Event tee methodology has been adopted as a containment performance analysis method. There are, however, some drawbacks on event tree methodology. This study is to overcome three major drawbacks of the current containment performance analysis method : 1) Event tree cannot express dependency between events explicitly. 2) Accident Progression Event Tree (APET) cannot represent entire containment system. 3) It is difficult to consider decision making problem. To resolve these problems, influence diagrams, is proposed. In the present ok, the applicability of the influence diagrams has been demonstrated for YGN 3&4 containment performance analysis and accident management strategy assessments of this study are in good agreement with those of YGN 3&4 IPE. Sensitivity analysis has been peformed to identify relative important variables for each early containment failure, late containment and basemat melt-though. In addition, influence diagrams are used to assess two accident management strategies : 1) RCS depressurization, 2) cavity flooding. It is shown that influence diagrams can be applied to the containment performance analysis.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.25 no.5
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• pp.381-388
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• 2012

In this study, a seismic risk analysis performed for an applicability assessment of steel fiber in containment structures. Steel fiber can increase tensile properties of concrete structures moreover compressive and shear capacity. But many of researches about steel fiber reinforced concrete structures are now only focused in axial load condition. Also it is very difficult to find an effort for application to containment structures in NPP. Therefore, in this study, seismic fragility assessment for a steel fiber reinforced concrete containment structure. As a result, a seismic fragility capacity improved according to increase of shear and ductile capacity of concrete. In the case of 1.0% of steel fiber volume fraction, seismic capacity increases as 10%. But very limited previous experimental results were used in this study, so various element tests were needed for more accurate investigation.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2003.05a
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• pp.371-376
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• 2003

원자력 발전소에서 격납건물 계통의 건전성 유지는 냉각재상실사고(Loss of Coolant Accident: LOCA) 및 주증기관 파단(Main Steam Line Break : MSLB) 사고와 같은 설계기준사고 시 격납건물의 최대 온도/압력을 평가하는 격납건물 성능 평가는 격납용기 내에 방사능 물질을 효율적으로 가두어 방사능 피해로부터 공공의 안전을 확보할 수 있느냐 하는 관건이다.(중략)

• 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 Earthquake Engineering Society of Korea
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• v.10 no.1 s.47
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• pp.63-74
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• 2006

The seismic fragility analysis method has been used as a quantitative seismic safety evaluation method for the NPP(Nuclear Power Plant) structures and equipments. The seismic fragility analysis gives a realistic seismic capacity excluding the convertism included in the design stage. The conservatism is considered as the probabilistic parameters related to the response and capacity in the seismic fragility analysis. In this study, the displacement based seismic fragility analysis method was proposed based on the nonlinear dynamic analysis results. In this study, the seismic safety of the prestressed concrete containment building of KSNP(Korean Standard Nuclear Power Plant) was evaluated for the scenario earthquakes, neat-fault, far-fault, design earthquake and probability based scenario earthquake, which can be occurred in the NPP sites.

• Proceedings of the Computational Structural Engineering Institute Conference
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• 2011.04a
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• pp.396-399
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• 2011

격납건물의 내압취약도 평가를 위하여 격납건물 구조재료 변수 각각의 재료특성 시험 결과를 분석하여 현재상태 중앙값 및 변동계수 값을 추정하였다. 추정된 값은 최근의 가동중 검사 결과와 큰 차이를 보이지는 않는 것으로 나타났다. 또한 추출된 구조재료 변수들의 재조합을 통해 상관성을 배제시키는 방법을 적용함으로서, 변수 간의 상관성이 격납건물 취약도 평가에 미치는 영향을 기존의 방법과 대비하여 분석하였다. 본 예제의 경우에는 의도치 않은 변수간 상관성에 의해 2%가량 내압성능이 작게 평가되는 결과가 발생하는 것으로 나타났다. 일반적인 문제의 경우 구조재료 변수의 특성과 추출된 변수의 임의성에 의해 영향이 증폭될 수 있기 때문에, 보다 합리적인 내압취약도 평가를 위해서는 상관관계 영향을 고려하는 것이 바람직하다고 할 수 있다.