• 한국마린엔지니어링학회:학술대회논문집
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• 한국마린엔지니어링학회 2011년도 전기공동학술대회 논문집
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• pp.285-285
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• 2011

This project can know realtime localization, sea weather and so on. also send information and message for work efficiency. in the case of an emergency like fall into the water or absent without leave, let the other sailer positions will allow for a quick response. so this system can be great help to emergency responders will be able to play a major role.

• Nuclear Engineering and Technology
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• 제44권7호
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• pp.709-718
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• 2012

The pressurized water reactor APR1400 adopts DVI (Direct Vessel Injection) for the emergency cooling water in the upper downcomer annulus. The International Standard Problem number 50 (ISP-50) was launched with the aim to investigate thermal hydraulic phenomena during a 50% DVI line break scenario with best estimate codes making use of the experimental data available from the ATLAS facility located at KAERI. The present work describes the calculation results obtained for the ISP-50 using the RELAP5/MOD3.3 system code. The work aims at validation and assessment of the code to reproduce the observed phenomena and investigate about its limitations to predict complicated mixing phenomena between the subcooled emergency cooling water and the two-phase flow in the downcomer. The obtained results show that the overall trends of the main test variables are well reproduced by the calculations. In particular, the pressure in the primary system show excellent agreement with the experiment. The loop seal clearance phenomenon was observed in the calculation and it was found to have an important influence on the transient progression. Moreover, the collapsed water levels in the core are accurately reproduced in the simulations. However, the drop in the downcomer level before the activation of the DVI from safety injection tanks was underestimated due to multi-dimensional phenomena in the downcomer that are not properly captured by one-dimensional simulations.

• 한국지하수토양환경학회:학술대회논문집
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• 한국지하수토양환경학회 2003년도 총회 및 춘계학술발표회
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• pp.225-228
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• 2003

For the purpose of finding out the distributions of groundwater uses, the effect of facilities on the parameter and the correlations among measurements, various statistical analysis were carried out with the data of groundwater quality measurements from January to December in 2002. 1. The rates of groundwater for drinking water were 10.5% in Yangcheon-Gu, 10.2% in Kangdong-Gu, and 9.9% in Eunpyung-Gu. The rates of other uses of groundwater were shown to be 58.1%(786 wells) for civil defense emergency, 22.1%(299 wells) for contamination-concerning, 9.8%(133 wells) for water quality monitoring, consisting of 90% of all groundwater. 2. The 52.6% of groundwater for drinking were demonstrated to be appropriate while 91.9% for tither uses-domestic, industrial, agricultural uses- were shown to be proper. 3. For drinking water, the average values of colar, turbidity, NH3-N, F, and Fe were 11.216 degree, 2.138 NTU, 2.458mg/l, 0.212mg/1 and 0.507mg/1 respectively. 4. In cases of drinking water wells for emergency, the results of statistical analysis showed that building year of the wells, depth and pumping rate didn't affect on whether it was proper for that use or not. It were shown that there were linear correlations between depth and NO$_3$-N(-0.171) and F￣(0.332) while the correlation coefficients were 0.381 and -0.169 between the building year of well and depth and pumping rate respectively.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.964-974
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• 2020

The small modular reactors (SMRs) of the integrated pressurized water reactor (IPWR) type have been widely developed owing to their enhanced safety features. The SMR-IPWR adopts passive residual heat removal system (PRHRS) to extract residual heat from the core. Because the PRHRS removes the residual heat using the latent heat of the water stored in the emergency cooldown tank, the PRHRS gradually loses its cooling capacity after the stored water is depleted. A quick restoration of the power supply is expected infeasible under station blackout accident condition, so an advanced PRHRS is needed to ensure an extended grace period. In this study, an advanced design is proposed to indirectly incorporate a dry air cooling tower to the PRHRS through an intermediate loop called indefinite PRHRS. The feasibility of the indefinite PRHRS was assessed through a long-term transient simulation using the MARS-KS code. The indefinite PRHRS is expected to remove the residual heat without depleting the stored water. The effect of the environmental temperature on the indefinite PRHRS was confirmed by parametric analysis using comparative simulations with different environmental temperatures.

• 한국수자원학회:학술대회논문집
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• 한국수자원학회 2007년도 학술발표회 논문집
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• pp.53-57
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• 2007

Tsurumi River Basin successfully started to prepare a Water Master Plan though a series of discussions by gathering all stakeholders in a hall. It began with setting five management targets namely, flood, low flow, natural environment, emergency use, and recreational use, followed by setting management goals by target as well as a one-sentence catchphrase for the Water Master Plan using a bottom-up approach. The author reviews this process and discusses the background of the success.

• 한국수자원학회논문집
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• 제53권spc1호
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• pp.773-784
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• 2020

본 연구에서는 수자원시설물의 노후화 정도와 관리현황 등을 조사·분석함으로써, 수자원시설물의 유지관리 체계 선진화를 위한 입법 및 정책과제를 제시하였다. 수자원시설물의 노후화를 분석하기 위해 한국시설안전공단에서 운영하는 시설물통합정보관리시스템의 자료를 수집하여 분석에 활용하였다. 시설물별, 종별, 시도별, 등급별로 구축된 안전등급 자료를 이용하여 위험시설물 비율과 고령화율을 산정하여 수자원시설물의 현황을 분석하고 수자원시설 관련 지침 및 매뉴얼을 조사하였다. 이를 통해 1) 수자원시설물 범위의 재조정 및 지침·매뉴얼의 보완, 2) 재해여건 변화를 고려한 유지관리 체계의 구축, 3) 시설물통합정보시스템의 개선 및 표준연계서비스 활성화, 4) 시설물의 자산관리체계 구축의 네 가지 입법 및 정책과제를 제시하였다.

• 한국수자원학회논문집
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• 제43권12호
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• pp.1075-1082
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• 2010

지진해일 재해를 저감하는 가장 바람직하고 경제적인 방법은 예측하지 못하는 지진해일의 급습이 예상되는 해안을 따라 비상대처계획을 수립하는 것이다. 비상대처계획은 과거에 발생했던 지진해일과 사전에 기획된 시나리오에 근거하여 작성해야 한다. 본 연구에서는 비상대처계획의 일부분으로 임원항에 대하여 기획된 시나리오에 따라 대피 시뮬레이션을 제작하였다. 제작된 대피 시뮬레이션은 관련기관에서 지진해일 급습에 대비한 방재훈련에 이용될 수 있다.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2010년도 춘계 학술발표회
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• pp.921-926
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• 2010

To examine saturation characteristics of an unsaturated soil in the steep slope area with collapse, it separated dry season from rainy season and measured water content and permeability, and measured permeability by using a tension infiltrometer in the site. In addition, it conducted electrical resistivity survey to look into thickness of ground and geological structure of underground. The collapsed slope increased depth of weathered zone compared to upper slope, and there electrical resistivity anomalous zone caused by the filtrated underground water was observed. The permeability of the collapsed area was observed high compared to upper and lower slopes of retarding basin without collapse, and the permeability measured by dividing the dry season and rainy season was measured high in case of dry season.

• 한국안전학회지
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• 제37권4호
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• pp.129-138
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• 2022

A new method for injecting cooling water into the Korean research reactor (KRR) in the event of beam tube rupture is proposed in this paper. Moreover, the research evaluates the risk to the reactor core in terms of core damage frequency (CDF). The proposed method maintains the cooling water in the chimney at a certain level in the tank to prevent nuclear fuel damage solely by gravitational coolant feeding from the emergency water supply system (EWSS). This technique does not require sump recirculation operations described in the current procedure for resolving beam tube accidents. The reduction in the risk to the core in the event of beam tube rupture that can be achieved by the proposed change in the cooling water injection design is quantified as follows. 1) The total CDF of the KRR for the proposed design change is approximately 4.17E-06/yr, which is 8.4% lower than the CDF of the current design (4.55E-06/yr). 2) The CDF for beam tube rupture is 7.10E-08/yr, which represents an 84.1% decrease compared with that of the current design (4.49E-07/yr). In addition to this quantitative reduction in risk, the modified cooling water injection design maintains a supply of pure coolant to the EWSS tank. This means that the reactor does not require decontamination after an accident. Thermal hydraulic analysis proves that the water level in the reactor pool does not cause damage to the nuclear fuel cladding after beam tube rupture. This is because the amount of water in the chimney can be regulated by the EWSS function. The EWSS supplies emergency water to the reactor core to compensate for the evaporation of coolant in the core, thus allowing water to cover the fuel assemblies in the reactor core over a sufficient amount of time.

• 디지털융복합연구
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• 제14권5호
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• pp.427-432
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• 2016

본 연구의 목적은 수중익사 사망 환자의 임상 치료 및 예방을 알아보고자 하였다. 수중 익사 사고는 소방 방재청에서 사용한 구급 활동 일일 보고서 데이터를 사용하여 확인 하였다. 소방 방재청 통계에서 익사 사고의 특성을 확인했다. 익사 사고의 나이, 날짜, 원인, 위치, 시간 및 사례 조사 하였다. 또한, 검색은 자연적인 원인과 사례를 찾고 NEMA 웹 사이트의 수집했다. 익사 사고의 나이는 20~29년 (25.4 %)이었다. 8월 익사의 경우는 17.6 %였다. 7, 8월 즉 여름에 익사 사고의 약 30%가 발생했다. 물에 빠진 경우에 수영과 관련된 사고가 45.0 %이였다. 수영과 우발적 사고의 절반은 물에서 가족이나 친구를 구출하려고 시도하는 사람의 익사 사고를 포함되었다. 가장 일반적인 위치는 호수나 저수지에서 40.2%이었다. 호수와 해변에 있는 사람들에 대한 인명 구조, 장비 또는 구명조끼가 없었다. 익사 사고는 14시-18시 사이에 가장 많이 발생했다. 익사는 한국의 상해와 관련된 사고의 주요 원인이다. 대한민국에서 익사의 특성을 이해하는 것은 예방 전략을 개발하는 것이 필요하다. 예방 전략으로 구명조끼 및 구명기 설치 의무화, 안전교육 활성화, 수영 능력 향상, 인명구조인력 배치 증가 등이 있다.