• Nuclear Engineering and Technology
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• 제8권2호
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• pp.101-116
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• 1976

고리 1호기 및 2호기 원자로의 발전단가에 대한 해석을 시도했다. 해석의 편의상 발전단가를 우선 건설, 운전 및 관리, 운전자금 및 핵연로 등에 관련된 비용성분으로 나누고, 이 중 첫 세성분에 대한 cost는 POWERCO-50 계산코오드를, 그리고 핵연료 비는 MITCOST-II를 써서 계산했다. 중요한 계산결과로서는 다른 세가지 핵연료 주기에 대한 고리 2획의 핵연료 주기비, 고리 1호 및 2호기의 발전단가 및 발전단가계산에 사용된 코스트 자료의 변화에 따른 발전단가의 민감도 등이다. 제래식 화력발전단가와 비교함으로써 원자력발전이 보다 경제적으로 유리하다는 사실을 알아내었지만 고리 2 호기의 건설비가 다른 PWR 발전에 비해 다소 고가임을 지적했다. 때문에 원자력발전을 유리하게 하기 위해서는 장차 도입될 원자력발전로의 경우 고리 2호기와 같은 turnkey 계약이 지양되어야 함을 지적했다. 또한 발전단가가 발전소 가동율의 변화에 따라 민감하게 변동한다는 사실로부터 발전소를 최대한 가동시킬 수 있도록 노력이 경주되어야 한다고 결론을 내렸다.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2352-2366
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• 2024

Reinforced concrete (RC) shear walls with precast steel-concrete composite modular (PSCCM) are strongly recommended in the structural design of nuclear power plants due to the need for a large number of process pipeline crossings and industrial construction. However, the effect of the PSCCM on the mechanical behavior of the whole RC shear wall is still unknown and has received little attention. In this study, three 1:3 scaled specimens, one traditional shear wall specimen (TW) and two shear wall specimens with the PSCCM (PW1, PW2), were designed and investigated under cyclic loadings. The failure mode, hysteretic curve, energy dissipation, stiffness and strength degradations were then comparatively investigated to reveal the effect of the PSCCM. Furthermore, numerical models of the RC shear wall with different PSCCM distributions were analyzed. The results show that the shear wall with the PSCCM has comparable mechanical properties with the traditional shear wall, which can be further improved by adding reinforced concrete constraints on both sides of the shear wall. The accumulated energy dissipation of the PW2 is higher than that of the TW and PW1 by 98.7 % and 60.0 %. The failure of the shear wall with the PSCCM is mainly concentrated in the reinforced concrete wall below the PSCCM, while the PSCCM maintains an elastic working state as a whole. Shear walls with the PSCCM arranged in the high stress zone will have a higher load-bearing capacity and lateral stiffness, but will suffer a higher risk of failure. The PSCCM in the low stress zone is always in an elastic working state.

• 한국지진공학회논문집
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• 제22권6호
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• pp.333-343
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• 2018

In this paper, we study the existing results of the structure-soil-structure interaction (SSSI) effect on seismic responses of structures and summarize important parameters. The parameters considered in this study are a combination of buildings in the power block of a nuclear power plant, the characteristics of earthquake ground motions and its direction, and the characteristics embedded under the ground. Based on these parameters, the seismic analysis model of the structures in the power block of the nuclear power plant is developed and the structure-soil-structure interaction analyses are performed to analyze the influence of the parameters on the seismic response. For all analyses, the soil-structure interaction (SSI) analysis program CNU-KIESSI, which was developed to enable large-sized seismic analysis, is used. In addition, the SSI analyses is performed on individual structures and the results are compared with the SSSI analysis results. Finally, the influence of the parameters on the seismic response of the structure due to the SSSI effect is reviewed through comparison of the analysis results.

• 한국지진공학회논문집
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• 제21권6호
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• pp.265-275
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• 2017

In order to improve the seismic performance of structures, friction pendulum system (FPS) is the most commonly used seismic isolation device in addition to lead rubber bearing (LRB) in high seismicity area. In a nuclear power plant (NPP) with a large self weight, it is necessary to install a large number of seismic isolation devices, and the position of the center of rigidity varies depending on the arrangement of the seismic isolation devices. Due to the increase in the eccentricity, which is the difference between the center of gravity of the nuclear structure and the center of stiffness of the seismic isolators, an excessive seismic response may occur which could not be considered at the design stage. Three different types of eccentricity models (CASE 1, CASE 2, and CASE 3) were used for seismic response evaluation of seismically isolated NPP due to the increase of eccentricity (0%, 5%, 10%, 15%). The analytical model of the seismic isolation system was compared using the equivalent linear model and the bilinear model. From the results of the seismic response of the seismically isolated NPP with increasing eccentricity, it can be observed that the effect of eccentricity on the seismic response for the equivalent linear model is larger than that for the bilinear model.

• 플랜트 저널
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• 제12권4호
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• pp.37-43
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• 2016

원자력발전소의 사고 대처 부하에 전력을 공급하는 전원계통은 다양한 조건에서도 일정 전압이 유지됨을 분석을 통하여 입증한다. 이를 위하여 발전소를 일정부하 운전 상태로 유지하고, 대용량 전동기(원자로냉각재펌프(RCP), 기기냉각수펌프(CCWP))를 각각 기동하여 기동 전 후 안전관련 모선의 전압을 측정하였다. 현장 시험으로 확보된 자료(예, 전압, 전류, 역율 등)는 기존 전력계통해석 모델의 운전 조건으로 재입력하고 재분석을 수행하였다. 이는, 기존 전력계통분석에 사용된 분석기법과 가정들을 실질적인 측정과 결과 분석으로 입증하는 과정이다. 결국, 두 경우의 전압 강하는 발전소 안전에 중요한 기기의 전압이 허용전압 이하로 저하되지 않음과 두 값의 비교 결과가 요구되는 제한치 이내임을 검증한다.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2021년도 가을 학술논문 발표대회
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• pp.156-157
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• 2021

Since concrete is contaminated or radioactive during operation of nuclear power plants, it is the most important radioactive waste generated during the dismantling of a nuclear power plant. The amount of waste is different depending on the pollution state of each facility and the applied technology is different, so there is a big difference. We aim to reduce the amount of waste and increase the value of recyclability through technology to remove radionuclides attached to the surface. For this purpose, laser scabbling, which exfoliates the surface of concrete by irradiating a laser, and a facility system for controlling dust and dust are used in parallel. The purpose of this study is to evaluate the efficiency of laser scabbling by manufacturing simulated concrete for nuclear facilities, and to review the optimal mixing design conditions for nuclear facility structures.

• 한국건설순환자원학회지
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• 제16권3호
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• pp.34-38
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• 2021

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1431-1441
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• 2017

The Fukushima accident reveals the vulnerability of existing active nuclear power plant (NPP) design against prolonged loss of external electricity events. The passive safety system is considered an attractive alternative to cope with this kind of disaster. Also, the passive safety system enhances both the safety and the economics of NPPs. The adoption of a passive safety system reduces the number of active components and can minimize the construction cost of NPPs. In this paper, reflecting on the experience during the development of the APR+ design in Korea, we propose the concept of an innovative Power Reactor (iPower), which is a kind of passive NPP, to enhance safety in a revolutionary manner. The ultimate goal of iPower is to confirm the feasibility of practically eliminating radioactive material release to the environment in all accident conditions. The representative safety grade passive system includes a passive emergency core cooling system, a passive containment cooling system, and a passive auxiliary feedwater system. Preliminary analysis results show that these concepts are feasible with respect to preventing and/or mitigating the consequences of design base accidents and severe accidents.

• 기술사
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• 제34권3호
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• pp.41-45
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• 2001

The nuclear power plant(NPP) construction is a mammoth project, which requires a huge construction budget and the long construction duration of about 7 years. Recently there is a trend to shorten the construction period, to save the construction cost and to ensure the competitiveness through adopting the open top construction method. In this method, the major equipment are moved into the building through its top, and the internal works of the reactor building are being in process without installation of a dome roof.

• Nuclear Engineering and Technology
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• 제46권5호
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• pp.569-580
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• 2014

Seismic isolation is a viable strategy for protecting safety-related nuclear structures from the effects of moderate to severe earthquake shaking. Although seismic isolation has been deployed in nuclear structures in France and South Africa, it has not seen widespread use because of limited new build nuclear construction in the past 30 years and a lack of guidelines, codes and standards for the analysis, design and construction of isolation systems specific to nuclear structures. The funding by the United States Nuclear Regulatory Commission of a research project to the Lawrence Berkeley National Laboratory and MCEER/University at Buffalo facilitated the writing of a soon-to-be-published NUREG on seismic isolation. Funding of MCEER by the National Science Foundation led to research products that provide the technical basis for a new section in ASCE Standard 4 on the seismic isolation of safety-related nuclear facilities. The performance expectations identified in the NUREG and ASCE 4 for seismic isolation systems, and superstructures and substructures are described in the paper. Robust numerical models capable of capturing isolator behaviors under extreme loadings, which have been verified and validated following ASME protocols, and implemented in the open source code OpenSees, are introduced.