• Nuclear Engineering and Technology
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• 제47권7호
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• pp.915-923
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• 2015

Pyroprocess technology has been considered as a fuel cycle option to solve the spent fuel accumulation problems in Korea. The Korea Atomic Energy Research Institute, Daejeon, Korea has been studying pyroprocess technology, and the conceptual design of an engineering-scale pyroprocess facility, called the Reference Engineering-scale Pyroprocess Facility, has been performed on the basis of a 10 ton heavy metal throughput per year. In this paper the concept of Reference Engineering-scale Pyroprocess Facility is introduced along with its safety requirements for the protection of facility workers, collocated workers, the off-site public, and the environment. For the identification of safety structures, systems, and components and/or administrative controls, the following activities were conducted: (1) identifying hazards associated with operations; (2) identifying potential events associated with these hazards; and (3) identifying the potential preventive and/or mitigative controls that reduce the risk associated with these accident events. This study will be used to perform a safety evaluation for accidents involving any of the hazards identified, and to establish safety design policies and propose a more definite safety design.

• 한국콘텐츠학회논문지
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• 제18권7호
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• pp.330-337
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• 2018

최근 사용자 중심의 스마트시티 서비스에 관한 관심이 높아지고 있다. 본 연구는 사용자 중심의 스마트시티 서비스를 계획하 기 위한 사전 연구로 사용자의 니즈를 조사하였다. 본 연구는 스마트시티 서비스에 대한 니즈를 도출하기 위해 GIS 기반 위치분석데이터와 비디오 에스노그래피 방법론을 활용하고자 한다. 본 연구는 스마트시티 테스트베드로 선정된 대전 도안지구의 현장조사를 통해 사용자의 집객도가 높은 지역을 세부조사대상지로 선정하고, 도로교통공단의 교통사고분석시스템(TAAS : Traffic Accidents Analysis System)의 위치분석데이터를 이용하여 주변 보행환경을 함께 조사하였다. 또한 비디오 에스노그래피의 고정카메라기법을 통해 사용자의 행위 유형과 변화를 관찰하였다. 추출된 영상데이터를 통해 사용자의 활동을 11개의 세분화 된 유형으로 분류하고, 관찰되는 문제점 및 특이사항을 분석하였다. 본 연구를 통해 조사된 사용자 행위특성은 향후 사용자 중심 스마트시티 서비스를 제안할 수 있는 근거를 마련한다는 점에 의의가 있다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집D
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• pp.813-820
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• 2001

The Safety depressurization System(SDS) of KNGR prevents RCS from overpressurization by discharging high pressure and temperature coolant through the I-sparger into the IRWST during an accident. If IRWST water temperature rise locally, around the sparger, beyond $200_{\circ}$2000 F by the discharged coolant, unstable steam condensation can cause large pressure load on the IRWST wall. To investigate whether this condition can be avoided for the design basis event IOPOSRV(Inadvertent Opening of one Pilot Operated Safety Relief Valve), the flow and temperature distribution of water in the IRWST is calculated by using CFX 4.3 computational fluid dynamic code. According to the results, since pool water temperature does not exceeds temperature limit within 50 seconds after the opening of one POSRV, it can be assured that the integrity of IRWST wall is maintained.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집B
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• pp.718-723
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• 2001

PPM (Performance Prediction Methodology) developed by EPRI was introduced and applied to calculate the stem thrust of 3 and 4 inches flexible-wedge gate valves. The calculated stem thrusts of open and close strokes including cracking were compared with the results measured at in-situ differential pressure tests. The comparison has shown that PPM is an extremely conservative method to predict the minimum required stem thrust to operate motor-operated valves in a design basis accident condition of nuclear power plants.

• 한국압력기기공학회 논문집
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• 제15권1호
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• pp.1-7
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• 2019

In this paper, the regulations and technical standards related to qualification of safety grade equipment in nuclear power plants are critically reviewed with the qualification procedure in terms of structures, systems, and equipment in nuclear power plants. These facilities should be designed and constructed to protect from natural conditions or disasters and to perform their safety functions even in case of postulated accidents. Equipment Qualification is to demonstrate that the safety related equipment is designed and constructed to perform their safety functions under normal and accident conditions. It is classified into environmental qualification and seismic qualification.

• 전기학회논문지
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• 제60권6호
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• pp.1274-1279
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• 2011

The purpose of this paper is to present the manufacturing defect and damage pattern of a 3 phase 22.9/3.3kV oil immersed transformer, as well as to present an objective basis for the prevention of a similar accident and to secure data for the settlement of PL related disputes. It was found that in order to prevent the occurrence of accidents to transformers, insulating oil analysis, thermal image measurement, and corona discharge diagnosis, etc., were performed by establishing relevant regulation. The result of analysis performed on the external appearance of a transformer to which an accident occurred, the internal insulation resistance and protection system, etc., showed that most of the analysis items were judged to be acceptable. However, it was found that the insulation characteristics between the primary winding and the enclosure, those between the ground and the secondary winding, and those between the primary and secondary windings were inappropriate due to an insulating oil leak caused by damage to the pressure relief valve. From the analysis of the acidity values measured over the past 5 years, it is thought that an increase in carbon dioxide (CO2) caused an increase in the temperature inside the transformer and the increase in the ethylene gas increased the possibility of ignition. Even though 17 years have passed since the transformer was installed, it was found that the system's design, manufacture, maintenance and management have been performed well and the insulating paper was in good condition, and that there was no trace of public access or vandalism. However, in the case of transformers to which accidents have occurred, a melted area between the upper and the intermediate bobbins of the W-phase secondary winding as well as between its intermediate and lower bobbins. It can be seen that a V-pattern was formed at the carbonized area of the transformer and that the depth of the carbonization is deeper at the upper side than the lower side. In addition, it was found that physical bending and deformation occurred inside the secondary winding due to non-uniform pressure while performing transformer winding work. Therefore, since it is obvious that the accident occurred due to a manufacturing defect (winding work defect), it is thought that the manufacturer of the transformer is responsible for the accident and that it is lawful for the manufacture to investigate and prove the concrete cause of the accident according to the Product Liability Law (PLL).

• Nuclear Engineering and Technology
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• 제50권3호
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• pp.356-367
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• 2018

A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the $Prim{\ddot{a}}rkreislauf-Versuchsanlage$ (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project. These investigations address current safety issues related to beyond design basis accident transients with significant core heat up. This work presents a detailed analysis using the best estimate thermal-hydraulic code TRACE (v5.0 Patch4) of different SBO scenarios conducted at the PKL facility; failures of high- and low-pressure safety injection systems together with steam generator (SG) feedwater supply are considered, thus calling for adequate accident management actions and timely implementation of alternative emergency cooling procedures to prevent core meltdown. The presented analysis evaluates the capability of the applied TRACE model of the PKL facility to correctly capture the sequences of events in the different SBO scenarios, namely the SBO tests H2.1, H2.2 run 1 and H2.2 run 2, including symmetric or asymmetric secondary side depressurization, primary side depressurization, accumulator (ACC) injection in the cold legs and secondary side feeding with mobile pump and/or primary side emergency core coolant injection from the fuel pool cooling pump. This study is focused specifically on the prediction of the core exit temperature, which drives the execution of the most relevant accident management actions. This work presents, in particular, the key improvements made to the TRACE model that helped to improve the code predictions, including the modeling of dynamical heat losses, the nodalization of SGs' heat exchanger tubes and the ACCs. Another relevant aspect of this work is to evaluate how well the model simulations of the three different scenarios qualitatively and quantitatively capture the trends and results exhibited by the actual experiments. For instance, how the number of SGs considered for secondary side depressurization affects the heat transfer from primary side; how the discharge capacity of the pressurizer relief valve affects the dynamics of the transient; how ACC initial pressure and nitrogen release affect the grace time between ACC injection and subsequent core heat up; and how well the alternative feeding modes of the secondary and/or primary side with mobile injection pumps affect core quenching and ensure stable long-term core cooling under controlled boiling conditions.

• 한국실내디자인학회:학술대회논문집
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• 한국실내디자인학회 2005년도 춘계학술발표대회 논문집
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• pp.93-97
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• 2005

People can't be free from the panic of flood, war and terrorism which could be fatal for people's life and property in modern society. It is the most important thing that provide food and residence for suffers in disaster areas. When disaster occurred, the emergency public facilities would be the first place that the people stay. However, these also could be destroyed by disaster. In that case, emergency tents or containers could be the major residence for disaster suffers. Because the only concern for planning temporary residence is the matter of supply and efficiency, it is no longer useful after the disaster end. Therefore, temporary residence as well as general residence should be on the basis of social and cultural factors as well as basic and physiological factors. It is very crucial to study the model of temporary residence. It could be the fundamental and necessary for the human being in order to prepare the natural disaster and grand scale accident. The main purpose for this study is examining the temporary residence that satisfy the fundamental, social and cultural factors for disaster sufferers.

• Nuclear Engineering and Technology
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• 제46권1호
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• pp.63-72
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• 2014

Pyroprocess technology has been considered as a fuel cycle option to solve the spent fuel accumulation problems in Korea. The Korea Atomic Energy Research Institute has been studying pyroprocess technology, and the conceptual design of an engineering-scale pyroprocess facility, called the Advanced Fuel Cycle (AFC) facility, has been performed on the basis of a 10tHM throughput per year. In this paper, the concept of the AFC facility was introduced, and its safety evaluations were performed. For the safety evaluations, anticipated accident events were selected, and environmental safety analyses were conducted for the safety of the public and workers. In addition, basic radiation shielding safety analyses and criticality safety analyses were conducted. These preliminary safety studies will be used to specify the concept of safety systems for pyroprocess facilities, and to establish safety design policies and advance more definite safety designs.

• 공업화학
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• 제16권6호
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• pp.809-814
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• 2005

본 논문에서는 원자력 발전소 격납건물 철재면에 적용되는 에폭시 코팅 시스템의 열적 특성에 관하여 방사선 조사 및 설계기준사고(DBA) 시험을 통하여 고찰하였으며, 동일 시스템의 접착강도에 대한 수중침적처리의 영향에 관해서도 알아보았다. ET-5290/carbon steel A 32 에폭시 도장 시스템의 유리전이온도($T_g$)와 열안정성은 DSC와 TGA를 가지고 각각 측정하였으며, 표면에너지적 특성에 대한 수중침적처리의 영향은 접촉각 측정을 통하여 알아보았다. 또한, 카본 철재면과 에폭시 수지간의 계면접착강도를 평가하기 위하여 부착력 시험을 행하였다. 결과로서, 방사선 조사 처리는 경화된 에폭시 도장 시스템에 내부 가교구조를 향상시켜 에폭시 도장 시스템의 $T_g$ 증가 및 열안정성을 향상시켰으며, 또한 경화 시스템의 수중침적처리시 후경화 효과로 인한 기계적 맞물림의 증가로 인하여 전체적으로 시스템의 접착강도의 증가를 가져왔다.