• Journal of the Computational Structural Engineering Institute of Korea
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• v.18 no.4 s.70
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• pp.335-345
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• 2005

This paper concentrates on the nonlinear analysis of prestressed concrete (PSC) containment structures. Unlike a commercialized program which adopts the perfect bond assumption between concrete and tendon in the analysis of PSC structures, a numerical algorithm to consider the slip effect, simultaneously with the use of commercialized programs such as DIANA and ABAQUS, is introduced in this paper For bonded tendons, the apparent yield stress of an embedded tendon is determined from the bond slip relationship. And for unbonded tendons, Correction for the strength and stiffness of unbonded internal tendons is achieved on the basis of an iteration scheme derived from the slip behavior of tendon along the entire length. Finally, the developed algorithm is applied to two PSC containment structures of PWR and CANDU to verify its efficiency and applicability in simulating the structural behavior of large complex structures, and the obtained result shows that both containment structures represent the ultimate pressure capacity larger than about 3 times of the design pressure.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.399-404
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• 1996

1000MWt 급 가압경수로의 질량 및 에너지 방출량을 감소시키기 위한 방안으로 울진 3,4호기를 기준으로 안전주입계통의 형태 및 용량을 변화시키면서 원자로냉각재펌프 토출관 및 고온관 파단에 대한 질량 및 에너지 방출량 계산과 격납건물 첨두압력 및 온도의 민감도를 분석하여, 후속호기 설계에 활용하고자 한다. 분석한 여러 경우 중에서, 토출관 파단사고시 안전주입탱크 용량은 변화시키지 않고 고압안전주입펌프 용량을 l75%로 증가시키면서 저압안전주입펌프를 제거하였을 경우가 격납건물 첨두압력 및 온도가 61.98 psia (3.32 kg/$\textrm{cm}^2$A), 288.03 ℉ (142.24$^{\circ}C$)로써 가장 낮게 나타났다. 이러한 결과는 격납건물의 설계여유도를 기존보다 더 확보하므로 안전성이 향상 될 뿐만 아니라. 저압안전주입펌프를 안전주입계통에서 제외함으로써 발전소 운전에도 큰 도움이 될 것이다.

• 기계와재료
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• v.22 no.1
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• pp.76-83
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• 2010

원자력발전소의 구조건전성 및 안전성을 확보하는데 있어서 격납건물의 중요한 목적은 방사성물질의 유출을 방지하는 최후의 보루 역할을 한다는 것이다. 또한 원전의 격납건물 선설에 있어서 고려해야 될 가장 중요한 인자는 안전성과 경제성이다. 이러한 목표를 달성하기 위해, 최근 국내에서 첨단 CLP(Containment Liner Plate) 공법이 개발되어 신월성 원전 2호기에 적용되었다. 이 공법은 기존의 CLP 2단 모듈화 공법에서 한 단계 발전한 CLP 3단 모듈화 공법으로 건설기간 단축, 비용 절감 및 구조건전성을 확보하는 계기가 되었다. 그리고 이러한 공법을 바탕으로 국내건설 뿐만 아니라 원전 수출에 커다란 기여를 하게 되었다. 이 글에서는 국내 원자력발전소 CLP 설치에 있어서, 기존의 방법과 새로운 공법에 대한 비교/분석, 공정, 장/단점 등을 연구, 조사해 보았다.

• 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.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.26 no.5A
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• pp.901-908
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• 2006

The structural integrity of containment building in Nuclear Power Plants has to be verified by the ISI(In Service Inspection) because there are some variations on the structural behavior of it due to the change of the physical properties of concrete and tendon with the lapse of time. In this study, the program 'SAPONC-CANDU' which can monitor and analyze the structural behavior of the containment building with grouted tendon (CANDU-type, 'Wolsong unit-2, 3, and 4' in Korea) was developed. This program is based on the algorithm which can calculate the prediction values of the quantities of strain variation for the vibrating-wire strain gauges embedded into the concrete of the containment building under temperature and time dependent factors which are creep, shrinkage, and prestressing force. The readings of the strain gauges are used as input data for the operation of the program. And it finally provides graphically a prediction value, line and band of the quantity of strain variation for the respective strain gauges, therefore, it is thought that the site engineers are able to assess the structural integrity of the domestic containment building with grouted tendon with easy using this program.

• Computational Structural Engineering
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• v.4 no.1
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• pp.17-19
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• 1991

본 글에서는 ANS(American Nuclear Society)에서 규정하고 있는 Safety Class 구조물 중 격납건물의 내진해석모델에 대해 주로 언급하며, 기타 건물(Non-Nuclear Safety "NNS")은 일반건물과 차이점이 없음으로 언급하지 않는다. U.S. NRC(Nuclear Regulatory Commision)는 참고문헌[1]에 의해 원자력 발전소내 여러건물중 SSE(Safe Shutdown Earthquake)하중에도 견디도록 규정하여 정확한 동력학적 계산이 요구되어지나, 그 이외의 건물들은 대개 등가정적 방법에 의해 해석되어진다. 이 해석방법은 여러 빌딩규정들에서 제안된 것으로 지진에 의한 동적하중을 밑면적 단력 또는 각층에 작용하는 층전단력이라는 등가의 정적하중으로 바꿔 계산되며 이 때 사용되는 해석모델은 건물의 기본진동만을 표시할 수 있는 간단한 것이다.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.15 no.4
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• pp.567-578
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• 2002

The main purpose of this study is to investigate the dynamic behaviour of containment building in nuclear power plant excited by aircraft impact loading using a lower order 8-node solid element. The yield and failure surfaces for concrete material model is formulated on the basis of Drucker-Prager yield criteria and are assumed to be varied by taking account of the visco-plastic energy dissipation. The standard 8-node solid element has prone to exhibit the element deficiencies and the so-called B bar method proposed by Hughes is therefore adopted in this study. The implicit Newmark method is adopted to ensure the numerical stability during the analysis. Finally, the effect of different levels of cracking strain and several types of aircraft loading are examined on the dynamic behaviour of containment building and the results are quantitatively summarized as a future benchmark.

• Journal of the Korea Concrete Institute
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• v.17 no.4 s.88
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• pp.527-533
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• 2005

Axisymmetric modeling of the nuclear containment building has been often employed in practice to estimate structural behavior for the axisymmetric loadings, where the axisymmetric approximation is required for the actual non-axisymmetric tendon arrangements in the dome. In the preceding companion paper, some procedures are proposed for the domestic CANDU and KSNP type containments that can implement the actual 3-dimensional tendon stiffness and prestressing effect into the axisymmetric model. In this paper, the proposed schemes are verified through some numerical examples comparing the results of the actual 3-dimensional model with those of some axisymmetric models. The results of the proposed axisymmetric analyses show relatively good agreements with the actual structural behavior especially for the CANDU type. Also, it is shown that proper level of the prestressing in a hoop direction plays an important role to predict the actual prestressing effect in the axisymmetric dome modeling. Finally, correction factors are discussed that can revise some approximations introduced in the derivations.

• Journal of the Korea Concrete Institute
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• v.17 no.4 s.88
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• pp.521-526
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• 2005

Prestressing tendons in a nuclear containment building dome are non-axisymmetrically arranged in most cases. However, simple axisymmetric modeling of the containment has been often employed in practice to estimate structural behavior for the axisymmetric loadings such as an internal pressure. In this case, the axisymmetric approximation is required for the actual tendon arrangements in the dome. Some procedures are proposed that can implement the actual 3-dimensional tendon stiffness and prestressing effect into the axisymmetric model. Prestressing tendons, which are arranged in 3 or 2-ways depending on a containment type, are converted into an equivalent layer to consider the stiffness contribution in meridional and hoop directions. In order to reflect the prestressing effect, equivalent load method and initial stress method are devised and the corresponding loads or stresses are derived in terms of the axisymmetric model. In a companion paper, the proposed schemes are applied into CANDU and KSNP(Korean Standard Nuclear Power Plant) type containments and are verified through some numerical examples comparing the analysis results with those of the actual 3-dimensional model.

• 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.