• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2004년도 봄 학술발표회 논문집
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• pp.209-216
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• 2004

Numerical analysis is carried out to identify the appropriateness of the design codes that is available for the tensile design of fastening system at Nuclear Power Plant (NPP) in this study. This study is intended for the cast-in-place anchor that is widely used for the fastening of equipment in Korean NPPs. The microplane model and the elastic-perfectly plastic model are employed for the quasi-brittle material like concrete and for the ductile material like anchor bolt as constitutive model for numerical analysis and smeared crack model is employed for the crack and damage phenomena. The developed numerical model is verified on a basis of the various test data of cast-in-place anchor. The appropriateness of both ACI 349 Code and CCD approach of CEB-FIP Code is evaluated for the tensile design of cast-in-place anchor and it is proved that both design codes give a conservative results compared with real tensile capacity of cast-in-place anchor.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 1998년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Spring 1998
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• pp.335-342
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• 1998

A soil-structure interaction (SSI) experiment is being conducted in a seismically active region in Hualien, Taiwan. To obtain earthquake data for quantifying SSI effects and providing a basis to benchmark analysis methods, a 1/4-th scale cylindrical concrete containment model similar in shape to that of a nuclear power plant containment was constructed in the field where both the containment model and its surrounding soil, surface and sub-surface, are extensively instrumented to record earthquake data. In between September 1993 and May 1996, fifteen earthquakes with Richter magnitudes ranging from 4.2 to 6.2 were recorded. The recorded data were analyzed to provide information on the response characteristics of the Hualien soil-structure system, the SSI effects and the ground motion characteristics. The ground response data were analyzed for their variations with depth, with distance from the model structure, and at the same depths along downhole arrays. Variations of soil stiffness and soil-structure system frequencies were also evaluated against maximum ground motion. In addition, the site soil properties were derived based on correlation analysis of the recorded data and then correlated with those from the geotechnical investigation data.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2010년도 정기 학술대회
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• pp.766-769
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• 2010

본 논문은 콘크리트 구조물 중 원전구조물에서 열화요인에 따른 미세구조적 변화에 대해서 평가하였다. 이는 원전구조물의 경우 열화현상이 발생하게 되면 일반 구조물에 비해 심각한 영향을 초래하기 때문에 기존의 열화 평가 방법에 의존하기 보다는 미세구조적 관점에서 콘크리트의 열화를 재평가해야 한다. 그에 일환으로 열화 요인 중 동결 융해와 황산염에 대한 미세구조 평가를 실시하였다. 동결융해의 경우, 미세구조적 관점에서의 미세공극의 양이 증가하는 것을 확인하였으나 그 증가 폭이 크지 않음을 알 수 있었으며, 물리적 실험에서도 그 변화가 매우 작음을 확인할 수 있다. 그리고 황산염에서는 초지 침지 구간에서는 플라이 애쉬를 사용한 원전 콘크리트 배합이 콘크리트에 더 유리하게 작용함을 알 수 있다.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2010년도 정기 학술대회
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• pp.770-772
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• 2010

기존의 연구는 열화에 의한 물리적 평가 및 열화에 영향을 미치는 수화생성물의 존재여부에 대한 연구는 활발하게 이루어지고 있으나, 그에 따른 수화생성물의 정량화에 대한 연구는 미흡한 실정이다. 본 논문은 XRD 분석 기법을 이용하여 원전 콘크리트 구조물에 대해 열화요인 중 탄산화와 황산염에 대한 상대적 정량화에 대한 연구를 실시하였다. 두 열화인자는 콘크리트 내의 수산화칼슘과 반응하여 에트린가이트와 탄산칼슘을 생성하게 되는데, 본 연구에서 열화인자에 대한 노출기간이 증가할수록 열화에 영향을 미치는 수화 생성물이 증가하는 것을 확인 할 수 있었다. 그에 따른 수산화칼슘의 양이 감소하는 것도 확인 할 수 있었다.

• Earthquakes and Structures
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• 제15권3호
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• pp.295-306
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• 2018

Reinforced concrete containment (RCC) building has long been considered as the last barrier for keeping the radiation from leaking into the environment. It is important to quantify the performance of these structures and facilities considering extreme conditions. However, the preceding research on evaluating nuclear power plant (NPP) structures, particularly considering mainshock-aftershock seismic sequences, is deficient. Therefore, this manuscript serves to investigate the seismic fragility of a typical RCC building subjected to mainshock-aftershock seismic sequences. The implementation of the fragility assessment has been performed based on the incremental dynamic analysis (IDA) method. A lumped mass RCC model considering the tri-linear skeleton curve and the maximum point-oriented hysteretic rule is employed for IDA analyses. The results indicate that the seismic capacity of the RCC building would be overestimated without taking into account the mainshock-aftershock effects. It is also found that the seismic capacity of the RCC building decreases with the increase of the relative intensity of aftershock ground motions to mainshock ground motions. In addition, the effects of artificial mainshock-aftershock ground motions generated from the repeated and randomized approaches and the polarity of the aftershock with respect to the mainshock on the evaluation of the RCC are also researched, respectively.

• Structural Engineering and Mechanics
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• 제4권2호
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• pp.139-148
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• 1996

Vector algorithms and the relative importance of the four basic modules (computation of element stiffness matrices, assembly of the global stiffness matrix, solution of the system of linear simultaneous equations, and calculation of stresses and strains) of a finite element computer program for inelastic analysis of reinforced concrete shells are presented. Performance of the vector program is compared with a scalar program. For a cooling tower problem, the speedup factor from the scalar to the vector program is 34 for the element stiffness matrices calculation, 25.3 for the assembly of global stiffness matrix, 27.5 for the equation solver, and 37.8 for stresses, strains and nodal forces computations on a Gray Y-MP. The overall speedup factor is 30.9. When the equation solver alone is vectorized, which is computationally the most intensive part of a finite element program, a speedup factor of only 1.9 is achieved. When the rest of the program is also vectorized, a large additional speedup factor of 15.9 is attained. Therefore, it is very important that all the modules in a nonlinear program are vectorized to gain the full potential of the supercomputers. The vector finite element computer program for inelastic analysis of RC shells with layered elements developed in the present study enabled us to perform mesh convergence studies. The vector program can be used for studying the ultimate behavior of RC shells and used as a design tool.

• Computers and Concrete
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• 제32권3호
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• pp.313-326
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• 2023

The seismic safety of the shear wall structure can be assessed through seismic fragility analysis, which requires high computational costs in estimating seismic demands. Accordingly, machine learning methods have been applied to such fragility analyses in recent years to reduce the numerical analysis cost, but it still remains a challenging task. Therefore, this study uses the ensemble machine learning method to present an improved framework for developing a more accurate seismic demand model than the existing ones. To this end, a rank-based selection method that enables determining an excellent model among several single machine learning models is presented. In addition, an index that can evaluate the degree of overfitting/underfitting of each model for the selection of an excellent single model is suggested. Furthermore, based on the selected single machine learning model, we propose a method to derive a more accurate ensemble model based on the bagging method. As a result, the seismic demand model for which the proposed framework is applied shows about 3-17% better prediction performance than the existing single machine learning models. Finally, the seismic fragility obtained from the proposed framework shows better accuracy than the existing fragility methods.

• 한국전산구조공학회논문집
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• 제25권5호
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• pp.381-388
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• 2012

본 연구에서는 Steel Fiber를 원전 격납건물에 적용하기 위한 적용성 평가를 위해서 Steel Fiber가 삽입된 격납건물에 대한 지진위험도 평가를 수행하였다. Steel Fiber를 콘크리트에 삽입함으로써 콘크리트의 구조적 성능에서 취약점인 인장성능을 향상시킬 수 있고, 압축강도 및 전단강도도 증가시킬 수 있는 장점이 있기 때문이다. 그러나 아직까지 원전 격납건물에 Steel Fiber를 적용하기 위한 노력은 진행되고 있지 않다. 재료적 우수성에도 불구하고 원전에 적용하기 위해서는 좀 더 많은 사용경험과 성능검증이 이루어져야 가능할 것이다. 따라서 본 연구에서는 원자력발전소 격납건물에 Steel Fiber를 사용하였을 경우, 격납건물의 지진안전성의 변화를 살펴보기 위하여 기존의 실험자료를 이용하여 취약도 평가를 수행하였다. 분석결과 Steel Fiber의 함유로 인하여 전단성능과 연성능력이 증가하여 지진취약도의 향상으로 나타났다. Steel Fiber함유량이 1.0%인 경우 지진내력이 10%가량 증가하는 효과를 얻을 수 있었다. 그러나 본 연구의 결과는 제한된 기존의 실험결과를 이용한 예비해석이므로 Steel Fiber의 실제 적용성을 적확하게 분석하기 위해서는 Steel Fiber가 함유된 다양한 콘크리트 부재실험을 통하여 그 물성의 변화를 파악하여야 할 것이다.

• 방사선산업학회지
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• 제17권4호
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• pp.509-518
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• 2023

The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.

• 한국구조물진단유지관리공학회 논문집
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• 제21권2호
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• pp.87-94
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• 2017

원자력발전소에서 철판이나 폴리머 라이너 판은 가스나 액체가 격남건물 외부로 누설되지 않도록 하기 위하여 채택되었다. 만일 어떤 사고가 발생하여 이 판이 손상을 입는 다면 콘크리트는 안전성 요구 측면에서 최후의 보루가 되어야 한다. 그 능력을 구명하기 위하여 본 논문에서는 시공이음의 유 무와 습윤조건 및 하중상태가 콘크리트의 누설저항성에 미치는 영향을 검토하기 위한 연구가 수행되었다. 실험결과로부터, 습윤상태에 시공이음이 있는 경우, 가스의 누설은 압력이 $1kg/cm^2$부터 시작되었으나 시공이음이 없는 경우는 $2kg/cm^2$부터 누설이 시작됨을 알 수 있었다. 또한, 기건 및 무재하 상태에는 시공이음의 유 무에 관계없이 콘크리트에 존재하는 가스의 통로가 일정하므로 누설량이 일정한 경향을 가지고 증가하였다. 최종적으로 재하상태에는 Okamoto et al.(1995)의 연구에서설명하는 바와 같이 누설량이 벽체의 두께에 반비례하므로 실제 발전소에 설치되는 벽체 두께를 고려하면 시공이음에 있어도 가스의 밀봉에는 문제가 없을 것으로 판단된다.