• 한국철도학회:학술대회논문집
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• 한국철도학회 2008년도 추계학술대회 논문집
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• pp.56-60
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• 2008

Increasing urban sprawl and climate changes have been causing unexpected high-intensity rainfall events. Thus there are needs to enhance conventional disaster management system for comprehensive actions to secure safety. Therefore long-term and comprehensive flood management plans need to be well established. Recently torrential snowfall are occurring frequently, causing have snow traffic jams on the road. To secure safety and on-time operation of the Bi-modal tram system, well-structured disaster management system capable of analyzing the urban flash flooding and snow pack melt/freezing due to unexpected rainfall event and snowfall are needed. To secure safety of the Bi-modal tram system due to torrential snowfall, the snow melt simulation capability was investigated. The snow accumulation and snow melt were measured to validate the SWMM snow melt component. It showed that there was a good agreement between measured snow melt data and the simulated ones. Therefore, the Bi-modal tram disaster management system will be able to predict snow melt reasonably well to secure safety of the Bi-modal tram system during the winter. The Bi-modal tram disaster management system can be used to identify top priority area for snow removal within the tram route in case of torrential snowfall to secure on-time operation of the tram. Also it can be used for detour route in the tram networks based on the disaster management system predicted data.

• 한국인터넷방송통신학회논문지
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• 제23권5호
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• pp.89-95
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• 2023

지하공동구는 도시의 상하수, 전력, 통신 등과 같은 중요한 시설을 수용하여 관리하는 도시기반시설로 화재, 지진, 침수 등과 같은 재난으로부터 보호해야 하는 국가 시설이다. 예측, 예방, 대비, 대응, 복구 등의 재난안전 전주기 관리 체계를 구축함에 있어서 첨단 ICT 기술과 데이터가 융합된 디지털 트윈 기술을 활용하여 지하공동구의 재난안전관리 플랫폼을 개발 중에 있다. 이 논문에서는 재난안전 디지털 트윈에 대한 성숙도 모델을 살펴보고 각 성숙도 단계 별 재난안전 디지털 트윈 구현을 위해 필요한 데이터셋을 정의하였다. 정의된 데이터셋의 카테고리의 조합에 따라 성숙도 단계를 다르게 하여 디지털 트윈 구현이 가능하도록 구성하였다.

• 한국유체기계학회 논문집
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• 제8권5호
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• pp.22-28
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• 2005

As the water supply facilities are recently getting larger, the domestic waterworks become multi-regional water supply system. Large water supply facilities generally consist of the intake pumping station, water treatment plant and water supply/distribution facilities. Although the pumping stations and the pipeline systems are used to pump up water, it often happens pipeline damage and flooding accident by the water hammer. In this paper, the intake pumping station is guaranteed by both the computer simulation and the field test analysis. This study is contributed to the safe operation program for the pumping station in which results of the adjustment on the safety plan of the pumping station, the air valve and the valve closing time.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.777-782
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• 1998

To terminate the progression of the sever accident and mitigate the accident consequences, corium coaling has been suggested as one of most important design features considered in the swore accident mitigation. Till now, some kinds of cooling methodologies have been identified and, specially the corium cooling at the reactor cavity has been considered as one of the most promising cooling methodologies. Moreover, several design requirements related to the cerium cooling at the reactor cavity have been also suggested and applied to the design of the next generation reactor. In this study technical description are briefly described for the important issues related to the cerium cooling at the reactor cavity, i.e. cavity area, cavity flooding system, etc., and simple evaluation for those items have been performed considering present technical levels the experiment and analytical works..

• Nuclear Engineering and Technology
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• 제28권3호
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• pp.247-256
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• 1996

This paper presents a new approach for assessing accident management strategies using containment event trees (CETs) developed during an individual plant examination (IPE) for a reference plant (CE type, 950 MWe PWR). Various accident management strategies to reduce risk have been proposed through IPE. Three strategies for the station blackout sequence are used as an example : 1) reactor cavity flooding only, 2) primary system depressurization only, and 3) doing both. These strategies are assumed to be initiated at about the time of core uncovery. The station blackout (SBO) sequence is selected in this paper since it is identified as one of the most threatening sequences to safety of the reference plant. The effectiveness and adverse effects of each accident management strategy are considered synthetically in the CETs. A best estimate assessment for the developed CETs using data obtained from NUREG-1150, other PRA results, and the MAAP code calculations is performed. The strategies are ranked with respect to minimizing the frequencies of Various containment failure modes. The proposed approach is demonstrated to be very flexible in that it can be applied to any kind of accident management strategy for any sequence.

• 한국정보과학회논문지:정보통신
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• 제32권3호
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• pp.310-317
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• 2005

모바일 애드흑 네트워크는 기존의 시스템처럼 인증기관(Certificate Authority)이나 중앙 집중화된 서버를 통해 노드들에 대한 신뢰와 온라인 접근을 제공하지 않는다. 그러나, 시스템의 노드들은 서로 안전하게 데이타를 주고받기 위해서 경로를 탐색하는 것뿐만 아니라, 서로를 신뢰할 수 있게 하는 과정이 반드시 필요하다. 이러한 이유 때문에 온라인 신뢰기관이나 인증 저장 공간을 요구했던 전통적인 보안 구조는 안전한 애드혹 네트워크에는 적합하지 않다. 이에 본 논문에서는 애드흑 네트워크 환경에서 효과적인 플러딩(flooding) 기법을 사용하여 노드 사이에 '안전하고 효과적인 최적의 인증경로탐색기법을 제안한다. 이 시스템은 브로드캐스팅(broadcasting)을 통해 목적지만을 찾는 일반적인 라우팅 프로토콜만을 의미하는 것이 아니라, 통신하고자 하는 노드를 안전하고 효과적으로 탐색하며, 찾아진 경로 또한 그 경로에 있는 노드간의 신뢰를 통해 검증하는 과정을 포함한다.

• Nuclear Engineering and Technology
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• 제31권5호
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• pp.486-497
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• 1999

The local heat transfer coefficient is experimentally investigated for the reflux condensation in a countercurrent flow between the steam-air mixture and the condensate, A single vertical tube has a geometry which is a length of 2.4m, inner diameter of 16.56mm and outer diameter of 19.05mm and is made of stainless steel. Air is used as a noncondensible gas. The secondary side has a shape of annulus around vertical tube and the lost heat by primary condensation is transferred to the coolant water. The local temperatures are measured at 11 locations in the vertical direction and each location has 3 measurement points in the radial direction, which are installed at the tube center, at the outer wall and at the coolant side. In three different pressures, the 27 sets of data are obtained in the range of inlet steam flow rate 1.348∼3.282kg/hr, of inlet air mass fraction 11.8∼55.0%. The investigation of the flooding is preceded to find the upper limit of the reflux condensation. Onset of flooding is lower than that of Wallis' correlation. The local heat transfer coefficient increases as the increase of inlet steam flow rate and decreases as the increase of inlet air mass fraction. As an increase of the system pressure, the active condensing region is contracted and the heat transfer capability in this region is magnified. The empirical correlation is developed by 165 data of the local heat transfer. As a result, the Jacob number and film Reynolds number are dominant parameters to govern the local heat transfer coefficient. The rms error is 17.7% between the results by the experiment and by the correlation.

• 한국화재소방학회논문지
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• 제30권5호
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• pp.46-53
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• 2016

우리나라 목조문화재는 화재 및 풍수해 등의 재해에 취약하므로 평상시 효과적인 안전 예방 조치와 관리가 반드시 필요하다. 이에 문화재청에서는 목조문화재 508개를 대상으로 재난방재시스템을 구축하였다. 그러나 508개소에 설치된 재난방재시스템을 종합적으로 파악하기는 힘들며, 관련자들의 자료공유는 물론, 각각의 재난방재시스템의 유지 관리가 불가능하였다. 이에 본 연구에서는, 사전예방적 관리의 기초단계로서 구축된 재난방재시스템의 현장조사를 통하여 주요 제원, 수량, 위치에 관한 자료를 한눈에 볼 수 있도록 방재설비 데이터베이스를 구축하였다. 이것은 추후 종합적인 문화재 안전관리를 가능하게 하는 기본적이며 중요한 정보이며, 다음 단계의 문화재 안전관리 시스템을 표상화 할 수 있는 기본 시스템이다.

• 해양환경안전학회지
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• 제27권7호
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• pp.1129-1136
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• 2021

본 논문은 선박 기관실 내의 효율적인 감시를 위한 팬-틸트-줌(PTZ) 카메라 기반의 모니터링 시스템의 설계 방법을 다룬다. 선박 기관실에는 여전히 전통적인 아날로그 계기들을 사용하는 곳이 많고, 침수나 화재 등 안전과 밀접하게 관련된 사각지대들이 다수 존재한다. 이러한 감시 개소들에 대하여 비교적 빠른 주기로 넓은 범위를 보장하는 카메라 기반 감시 시스템은 선박의 안전을 강화시킬 수 있는 효과적인 대안이 될 수 있다. 이에 본 연구에서는 기존 PTZ 카메라의 기능들을 소프트웨어적 방법으로 더욱 강화시킨 형태의 모니터링 시스템을 제안한다. 보다 구체적으로는 카메라제어 모듈, 위치등록 모듈, 순회제어 모듈, 멀티뷰 영상재구성 모듈로 구성된 모니터링 시스템의 설계 방법을 제안하고, 제안된 방법은 기관실 환경에서의 실험을 통해 그 효용성을 평가한다.

• 한국안전학회지
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• 제35권5호
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• pp.121-127
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• 2020

Since the Fukushima nuclear accident in 2011, the public were concerned about the safety of Nuclear Power Plants (NPPs) in extreme natural disaster situations, such as earthquakes, flooding, heavy rain and tsunami, have been increasing around the world. Accordingly, the Stress Test was conducted in Europe, Japan, Russia, and other countries by reassessing the safety and response capabilities of NPPs in extreme natural disaster situations that exceed the design basis. The extreme natural disaster can put the NPPs in beyond-design-basis conditions such as the loss of the power system and the ultimate heat sink. The behaviors and capabilities of NPPs with losing their essential safety functions should be measured to find and supplement weak areas in hardware, procedures and coping strategies. The Loss of Ultimate Heat Sink (LUHS) accident assumes impairment of the essential service water system accompanying the failure of the component cooling water system. In such conditions, residual heat removal and cooling of safety-relevant components are not possible for a long period of time. It is therefore very important to establish coping strategies considering all available equipment to mitigate the consequence of the LUHS accident and keep the NPPs safe. In this study, thermal hydraulic behavior of the LUHS event was analyzed using RELAP5/Mod3.3 code. We also performed the sensitivity analysis to identify the effects of the operator recovery actions and operation strategy for charging pumps on the results of the LUHS accident.