• 제목/요약/키워드: Isolation Accident

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도림천에서 발생한 고립 및 실족사고의 원인분석을 통한 개선방안 도출에 관한 연구 (Cause Analysis and Improvement Suggestion for Flood Accident in Dorimcheon - Focused on the Tripping and Isolation Accidents)

  • 이경수;전종형;김태훈;김현주
    • 한국산학기술학회논문지
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    • 제22권4호
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    • pp.25-36
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    • 2021
  • 본 연구는 도림천에서 발생한 고립 및 실족과 같은 수난사고의 근본적인 원인을 분석하고, 법·제도적인 개선방안을 제시하였다. 원인분석을 위하여 현장확인, 관계자 인터뷰, 관련자료 검토, 강우량과 하천 횡단면의 수위와의 관계, 자동경보 발령 기준수위의 적정성 및 진·출입 통제에 따른 대피시간 확보 가능여부 등을 평가 하였다. 도림천은 전형적인 도시하천의 특성을 띄고 있어 치수적으로 불리하며, 사망사고가 발생한 구간은 급만곡부를 형성하고 있는 등 고립사고 발생 위험이 높다. 고립 및 실족사고는 홍수주의·경보 발령 전 단계인 둔치주의·대피 단계에서 발생하고 둔치대피 발령은 둔치턱까지 수위가 상승해서야 발령되기 때문에 있기 때문에 강우예보에 따른 수위상승에 대한 즉각적인 대응이 중요하다. 또한, 수위 상승속도가 신림3교와 관악도림교에서 최대 2.62 cm/min임을 고려하였을 때 둔치경보 발령 후 충분한 대피시간을 확보하고 있지 못하다. 사망사고는 둔치주의 발령 기준수위보다 0.46 m이하에서 발생한 점을 보았을 때, 하천의 진·출입 등 통제가 사고 예방을 위해서는 매우 중요하다. 이러한 분석결과를 바탕으로 4건의 개선방안을 제시하였으며, 고립 및 실족과 같은 수난사고를 예방하는데 크게 기여할 수 있을 것으로 기대한다.

EVALUATION OF PLANT OPERATIONAL STATES WITH THE CONSIDERATION OF LOOP STRUCTURES UNDER ACCIDENT CONDITIONS

  • MATSUOKA, TAKESHI
    • Nuclear Engineering and Technology
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    • 제47권2호
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    • pp.157-164
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    • 2015
  • Nuclear power plants have logical loop structures in their system configuration. This paper explains the method to solve a loop structure in reliability analysis. As examples of loop structured systems, the reactor core isolation cooling system and high-pressure core injection system of a boiling water reactor are considered and analyzed under a station blackout accident condition. The analysis results show the important role of loop structures under severe accidents. For the evaluation of the safety of nuclear power plants, it is necessary to accurately evaluate a loop structure's reliability.

RNN-based integrated system for real-time sensor fault detection and fault-informed accident diagnosis in nuclear power plant accidents

  • Jeonghun Choi;Seung Jun Lee
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.814-826
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    • 2023
  • Sensor faults in nuclear power plant instrumentation have the potential to spread negative effects from wrong signals that can cause an accident misdiagnosis by plant operators. To detect sensor faults and make accurate accident diagnoses, prior studies have developed a supervised learning-based sensor fault detection model and an accident diagnosis model with faulty sensor isolation. Even though the developed neural network models demonstrated satisfactory performance, their diagnosis performance should be reevaluated considering real-time connection. When operating in real-time, the diagnosis model is expected to indiscriminately accept fault data before receiving delayed fault information transferred from the previous fault detection model. The uncertainty of neural networks can also have a significant impact following the sensor fault features. In the present work, a pilot study was conducted to connect two models and observe actual outcomes from a real-time application with an integrated system. While the initial results showed an overall successful diagnosis, some issues were observed. To recover the diagnosis performance degradations, additive logics were applied to minimize the diagnosis failures that were not observed in the previous validations of the separate models. The results of a case study were then analyzed in terms of the real-time diagnosis outputs that plant operators would actually face in an emergency situation.

전기동력 자동차 구동부와 제어부 간 절연고장 검출 방법 (The Method for detecting ground fault between power part and controller part of a electricity vehicle)

  • 박현석;조세봉;전윤석
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2007년도 추계학술대회 논문집
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    • pp.174-176
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    • 2007
  • Because of accident or leak of electricity, high voltage electricity can be conducted to vehicle chassis and damage human. Therefore the unit for detecting ground fault is necessary to minimize loss of life or equipment damage. Isolation resistance must be monitored for detecting ground fault. GFD(Ground Fault Detection) unit continually generate the pulse voltage between high voltage network and chassis. This will be sensing the returned current, calculate the isolation resistance and make decision the ground fault. This paper describes the method detecting ground fault.

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화학사고의 일차 대응을 위한 피해영향범위 산정 개선 방안 (Improvement of Damage Range Calculation for First Response to Chemical Accidents)

  • 이덕재;안재현;송창근
    • 한국안전학회지
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    • 제32권2호
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    • pp.59-65
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    • 2017
  • Calculation of the damage impact of chemical accidents is an important element in site, and the initial isolation distance and the protective action distances are significant factors in coping the chemical accident. In this study, three major cities that represent each Province were selected, and the safety distances were calculated considering regional climate conditions. The results were compared with the prescribed values in Emergency Response Guidebook. It is concluded that the regional meteorological conditions such as temperature, vapour pressure, relative humidity, wind speed, and cloud cover should be reflected in estimating the initial isolation distance and the protective action distance.

3차원 면진장치를 이용한 URANUS 액체금속로의 지진응답감소 (Reduction in Seismic Response of URANUS Liquid Metal Reactor by Using Three-Dimensional Seismic Isolator)

  • 이국희;김윤재;류강묵;황일순;유봉
    • 한국압력기기공학회 논문집
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    • 제7권3호
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    • pp.30-39
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    • 2011
  • URANUS (Ubiquitous, Robust, Accident-forgiving, Non-proliferating, Ultra-lasting and Sustainer) has been developed with 35MWe (100MWth) operating without primary coolant pump, capitalizing on natural circulation capability of lead-bismuth eutectic (LBE) for long-life small and robust power units. To ensure the structural integrity, the large safety margin against Safe Shutdown Earthquake, 0.3g, and furthermore the cost effectiveness for URANUS, three-dimensional seismic base isolation design has been developed. The analytical model has been developed and seismic time history analyses have been carried out. The advantage for using three-dimensional seismic base isolation for URANUS has been discussed.

대규모의 냉각재 상실 사고시 노심내 냉각재 양의 추정과 운전원 시간마진 예측을 위해 제안된 방법 (Proposed Method to Predict Core Inventory history and Operator Time Margin during Small Break Accident)

  • Hee Cheon No
    • Nuclear Engineering and Technology
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    • 제15권4호
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    • pp.219-228
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    • 1983
  • 릴리프 밸브의 차단까지 TMI-2 사고의 blowdown history를 검토하고 TMI-2 사고와 같은 소규모의 냉각제 상실 사고 동안 노심 파괴를 막기 위해 더 가산해야할 측정 기구에 대하여 논의하였다. 가산된 기구를 이용하여 어떻게 노심의 uncovered level과 operator time margin을 계산하는 가를 검토하였으며, TMI-2 사고에 대해 uncovered level과 operator time margin을 결정하기 위한 샘플 계산을 수행하였다. 이 방법을 이용해서 측정되는 변수들의 함수로써 uncovered level과 operator time margin을 보여주는 도표를 작성하였다.

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면진장치 적용을 고려한 원전구조물 생애주기 분석 (Life-Cycle Analysis of Nuclear Power Plant with Seismic Isolation System)

  • 김선용;이홍표;조명석
    • 한국전산구조공학회논문집
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    • 제26권6호
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    • pp.415-421
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    • 2013
  • 본 논문에서는 면진시스템이 원전에 적용될 경우 원전구조물의 생애주기 성능에 미치는 영향을 소개한다. 최근 내진설계와 더불어 강진발생 예상 지역에 적용을 목적으로 개발되는 면진시스템은 구조물을 장주기화하여 응답가속도를 줄이고 상대변위를 늘려줌으로써 구조물의 안전성을 증진시키는 것으로 알려져 있다. 따라서, 구조물의 안전성이 중요시되는 원전구조물에 면진시스템을 적용하기 위한 연구가 국내에서 진행 중에 있다. 본 연구에서는 원전구조물의 생애주기 성능분석에 있어서 특징을 분석하고, 면진시스템이 적용될 경우 원전구조물의 생애주기성능에 있어서 미치는 영향을 평가함으로써, 도출된 결과를 면진시스템 적용의 정량적인 타당성 평가에 활용할 수 있다.

Conceptual Safety Design Analyses of Korea Advanced Liquid Metal Reactor

  • Suk, S.D.;Park, C.K.
    • Nuclear Engineering and Technology
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    • 제31권6호
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    • pp.66-82
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    • 1999
  • The national long-term R&D program, updated in 1997, requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor(KALIMER), along with supporting R&D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R&D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of HAMMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation.

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반복법을 이용한 면진적용 원전구조물의 지반-구조물 상호작용 해석 (Soil-Structure Interaction Analysis for Base-Isolated Nuclear Power Plants Using an Iterative Approach)

  • 한승룡;남민준;서춘교;이상훈
    • 한국지진공학회논문집
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    • 제19권1호
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    • pp.21-28
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    • 2015
  • The nuclear accident due to the recent earthquake in Japan has triggered awareness of the importance of safety with regard to nuclear power plants (NPPs). An earthquake is one of the most important parameters which governs the safety of NPPs among external events. Application of a base isolation system for NPPs can reduce the risk for earthquakes. At present, a soil-structure interaction (SSI) analysis is essential in the seismic design of NPPs in consideration of the ground structure interaction. In the seismic analysis of the base-isolated NPP, it is restrictive to consider the nonlinear properties of seismic isolation devices due to the linear analysis of the SSI analysis programs, such as SASSI. Thus, in this study, SSI analyses are performed using an iterative approach considering the material nonlinearity of the isolators. By performing the SSI analysis using an iterative approach, the nonlinear properties of isolators can be considered. The difference between the SSI analysis results without iteration and SSI with iteration using SASSI is noticeable. The results of the SSI analysis using an effective linear (non-iterative) approach underestimate the spectral acceleration because the effective linear model cannot consider the nonlinear properties of isolators. The results of the SSI analysis show that the horizontal response of the base-isolated NPP is significantly reduced.