• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.486.1-486
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 1999.05a
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• pp.431-431
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• 1999

• Journal of the Korea Institute of Building Construction
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• v.15 no.4
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• pp.425-431
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• 2015

Since the construction of Kori 1 was completed in 1978, the construction projects for nuclear power plant are increasingly expanded into domestic and foreign sites. However, some of construction sites of nuclear power plant have the problems of process delay and cost loss due to lack of ability of risk management. The construction of reactor containment building in nuclear power plant is especially dotted with many risk factors because it needs professional skills and large-scale resources due to long duration compared with different construction phase. Therefore, it needs the study that analyzes risk factors expected in construction of reactor containment building and suggests way of stable performance of projects. So, this study assesses risk factors of construction of reactor containment building. For the objectives, this study uses survey for group of minority specialists of 36 experts. The risks of 24 factors is classified by criterions of process, cost, safety, and quality and the results of assessment is analyzed by analytic hierarchy process. As the results, the importance and priority of risk factors classified by each criterion were calculated and the applicability of analytic hierarchy process was identified to analyze risk factors of nuclear power plant construction. These will be baseline data for risk management in construction phase of reactor containment building.

• Particle and aerosol research
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• v.10 no.4
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• pp.137-154
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• 2014

Prediction of the behavior of radioactive aerosol particles in a containment is of importance for the assessment of the consequences of nuclear power plant severe accidents because most radioactive air pollutants are emitted as aerosol particles upon severe accident. The performance of engineering safety features (ESFs) is also influenced by the characteristics of the aerosol particles. In this article, the characteristics of aerosol particles in reactor containments reported by previous studies were reviewed. The results of the experiments for postulated accidents in test reactors, for aerosol behavior analysis using artificial test aerosols, and for ESF performance evaluation were summarized. The summary of this article will be of use in designing and performance-evaluating ESFs.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.34 no.6
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• pp.385-392
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• 2021

Interest in the seismic performance of nuclear facilities under strong earthquakes has increased because their nonlinear response is important. In this paper, we proposed appropriate parameters for the nonlinear finite element analysis of a concrete material model, for a reinforced concrete (RC) shear wall in nuclear facilities: maximum tensile strength, dilation angle, and damage parameter. The study of the effects of the important parameters, on the nonlinear behavior and shear failure mode of the RC shear wall having low aspect ratio, was conducted using ABAQUS finite element analysis program. Based on the study results the nonlinear response of a nuclear reactor containment building (RCB) subjected to a strong earthquake was evaluated using nonlinear time-history analysis.

• Nuclear industry
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• v.37 no.1
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• pp.7-14
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• 2017

작년 경주 지진으로 원자력 안전에 대한 시민들의 촉각이 예민해져 있는 가운데 최근 대전 지역에서 원자력연구원의 하나로 원자로 건물 외벽 내진 보강 공사 방식에 대한 검증을 요구하는 여론이 일고 있다. 그 동안 원자력연구원에서 진행한 하나로 건물 내진 보강 공사 배경과 주요 일정, 설계 개념, 구조 성능 검증 실험, 공사 현황, 건물 성능 점검, 안전 관리, 정보 공개 및 검증, 향후 계획 등을 정리하여 종합했다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.520-525
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• 1997

액체금속로의 안전성과 경제성을 향상시키는데 중요한 요소로 부각된 면진설계기술을 개발하기 위하여 고감쇠 면진베어링의 축소모델을 제작하고, 성능확인을 위한 다양한 시험을 실시하였다. 면진베어링의 성능을 나타내는 전단강성, 감쇠특성, 항복하중특성값, 전단변형능력 등에 대한 시험결과 전단강성은 목표값에 비하여 작았지만 감쇠값과 전단변형은 목표값에 근접하였다. 이를 이용한 면진 원자로건물의 지진응답을 분석한 결과 면진베어링은 건물의 지진응답 가속도를 대폭 줄여주는 것으로 나타났다.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.19 no.1
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• pp.587-595
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• 2018

Countries that have been banned from building nuclear plants are becoming more tolerant in response to global warming and climate change. Thus, the construction of future nuclear plants will increase, and the competition will also intensify. A nuclear power plant has a long construction period compared with conventional construction projects. In order to gain a competitive advantage in nuclear power plant construction, the construction period must be decreased. Therefore, the purpose of this study is to develop an exterior wall form for a reactor containment building to reduce the construction time by increasing the height of the form. The structural safety, constructability, and economic feasibility were analyzed to assess the applicability of the proposed form. The proposed form was determined to be structurally safe. Furthermore, the construction period was shortened by reducing the duration of the construction units, and the total construction cost and interest were also reduced. Therefore, the proposed form could contribute to reducing the construction period for nuclear power plants.

• Journal of Radiation Protection and Research
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• v.34 no.3
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• pp.121-128
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• 2009

During the maintenance period at Korean nuclear power plants, internal exposure of radiation workers occurred by the inhalation of $^{131}I$ released to the reactor building when primary system was opened. The internal radioactivity of radiation workers contaminated by $^{131}I$ was immediately measured using a whole body counter and the whole body counting was performed again after a few days. In this study, the intake estimated from the record history of entrance to radiation control areas and the measurement results of air sampling for $^{131}I$ in those areas, were compared with that from the results of whole body counting. As a result, it was concluded that the intake estimation using whole body counting and air sampling showed similar results.

• Journal of the Korean Society for Precision Engineering
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• v.28 no.2
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• pp.233-238
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• 2011

In piping design of nuclear power plant facilities, the load stress according to self-weight is important for design values in test run(shutdown and starting). But sometimes it needs more studies, such as seismic analysis of an earthquake of power plant area and fatigue life and stress of thermal expansion and anchor displacement in operating run. In this paper, seismic evaluations were performed to nuclear piping system of Shin-Kori NO. 3&4 being built in Pusan lately. Results of seismic analysis are evaluated on basis of KEPIC MN code. The structural integrity on RCB piping system was proved.