• Title/Summary/Keyword: 원자로 건물

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The Open Top Construction Method for the PHWR Reactor Building (중수로형(重水爐形) 원자로 건물의 Open Top시공공법)

  • 이수득
    • Journal of the Korean Professional Engineers Association
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    • v.34 no.3
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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.

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연구용 원자로 1, 2호의 폐로 계획

  • 서두환
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.05b
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    • pp.937-941
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    • 1995
  • 한국원자력연구소는, 지금까지 연구로 1호(250 ㎾)는 33년째, 연구로 2호(2 ㎿)는 23년째 운전하고 있다 그러나 이들 연구로는 노후하였고, 새로운 연구로 하나로(30 ㎿)가 금년 4월에 준공하였으며, 현재의 연구로 1, 2호가 있는 부지와 건물은 한국전력공사의 소유물이라는 이유로, 금년 말까지 연구로 1, 2호는 폐로할 계획으로 있다 이 논문에는 연구로 1,2호기에 대한 1)폐로 계획의 배경, 2)연구로의 이력, 3)폐로 계획 등을 기술하고 있다.

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Analysis Model on Risk Factors of RCB Construction in Nuclear Power Plant (원자력 발전 플랜트 RCB 시공의 리스크 요인에 관한 분석 모델)

  • Shin, Dae-Woong;Shin, Yoonseok;Kim, Gwang-Hee
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2014.11a
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    • pp.212-213
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    • 2014
  • The purpose of this study is to suggest analysis model of RCB construction in nuclear power plant. For the objective, This study drew the risk factors of RCB construction from existing literature. The results of the study proposed analysis model made hierarchy in rebar, form, and concrete work. These will be baseline data for risk management in construction project of nuclear power plant.

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Characteristics of Radioactive Aerosol Particles in Nuclear Power Plant Containments (원자로건물 내부 방사성 에어로졸 입자의 특성)

  • Kim, Min Young;Park, Sung Hoon
    • 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.

Evaluation of Nonlinear Seismic Response of RC Shear Wall in Nuclear Reactor Containment Building (원자로건물의 철근콘크리트 전단벽 비선형 지진응답 평가)

  • Kim, Dae Hee;Lee, Kyung Koo;Koo, Ji Mo
    • 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.

Chemical Effects on Head Loss across Containment Sump Strainer under Post-LOCA Environment (LOCA이후 환경에서 원자로건물집수조 여과기의 수두손실에 대한 화학적 영향)

  • Ku, Hee-Kwon;Jung, Bum-Young;Hong, Kwang;Jeong, Eun-Sun;Jung, Hyun-Jun;Park, Byung-Gi;Rhee, In-Hyoung;Park, Jong-Woon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.10 no.11
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    • pp.3260-3268
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    • 2009
  • A test apparatus has been fabricated to simulate chemical effect on head loss through a strainer in a pressurized water reactor (PWR) containment water pool after a loss of coolant accident (LOCA). Tests were conducted under condition of same ratio of strainer surface area to water volume between the test appratus and the containment sump. A series of tests have been performed to investigate the effects of spray, existence of calcium-silicate with tri-sodium phosphate (TSP), and composition of materials. The results showed that head loss across the chemical bed with even a small amount of calcium-silicate insulation instantaneously increased as soon as TSP was added to the test solution. Also, the head loss across the test screen is strongly affected by spray duration and is increased rapidly at the early stage, because of high dissolution and precipitation of aluminum and zinc. After passivation of aluminum and zinc by corrosion, the head loss increase is much slowed down and is mainly induced by materials such as calcium, silicon, and magnesium leached from NUKONTM and concrete. Furthermore, it is newly found that the spay buffer agent, tri-sodium phosphate, to form protective coating on the aluminum surface and reduce aluminum leaching is not effective for a large amount of aluminum and a long spray.

액체금속로용 축소규모 면진베어링 특성시험고찰 및 적용예

  • Yoo, Bong;Lee, Jae-Han;Koo, Kyung-Hoe
    • 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.

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