• Proceedings of the KIEE Conference
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• 2009.07a
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• pp.2011_2012
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• 2009

내환경검증은 원자력발전소 안전성 관련 계통의 기기가 정상운전 및 설계기준 사고 환경에서 안전기능을 수행할 수 있는지를 검증하는 것이다. 기기검증 평가에 관한 사항은 원자력법시행규칙 '제19조의2(주기적안전성평가의 세부내용)에 따르며 세부평가 대상범위는 안전기능을 확보하기 위한 안전관련 전기기기, 기능이 상실되면 안전관련 기능 수행을 저해하는 비 안전관련 기기, 규제지침 Reg Guide 1.97에서 요구하는 사고 후 감시기기 등이며 국내의 경우에는 경수로형 원전 안전심사지침 제3.11에 따른 내환경검증 기계류 기기의 비금속 부품 등이 추가로 해당된다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.20 no.1
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• pp.7-15
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• 2024

Environmental qualification is required for safety related electrical equipment under harsh environments located in nuclear power plants according to 10 CFR 50.49 and RG 1.89. As analog technology has recently been replaced by digital technology, NRC established RG 1.209 as a regulatory guideline for environmental qualification of safety related computer-based I&C system located in mild environments, requiring evaluation for electromagnetic compatibility, smoke exposure and type test for actual service conditions such as temperature and humidity. In this paper, the trend of environmental qualification for digital equipment is analyzed by comparing the environmental qualification requirements between digital and analog equipment.

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.478.2-478.2
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• 2003

• 기계와재료
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• v.12 no.4 s.46
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• pp.122-131
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• 2000

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.327.2-327
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• 2001

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.15 no.1
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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.

• Journal of Energy Engineering
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• v.23 no.1
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• pp.90-94
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• 2014

Environmental qualification (EQ) for safety-related equipment is required to ensure that those equipment will perform their required function even under the harsh environment conditions arising from design basis accident in the nuclear power plant. As a part of EQ program, the room temperature analysis in case of a loss of Heating, Ventilation, and Air Conditioning(HVAC) system was carried out to ensure the operability of the safety-related equipment of a nuclear power plant randomly chosen among the Korean nuclear power plants. In this paper, this analysis was performed in the conservative perspective using GOTHIC code. The room temperature analysis includes selecting the rooms in which the safety related equipment are located but not supported by safety related HVAC and determining the temperature of the selected rooms. Target rooms for the analysis consist of W229/W237 (Aux. feedwater pump room), W232 (Aux. feedwater tank room) and W230 (Equipment passageway). The results showed the temperature range from $43^{\circ}C$ to $83^{\circ}C$, in 72 hours after a loss of HVAC. Those values are far below of generic EQ temperature($171^{\circ}C$). Therefore, it is satisfied with EQ requirement of temperature limits on safety related equipment.

• Journal of Energy Engineering
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• v.16 no.3
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• pp.103-112
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• 2007

Flood issue for nuclear power plants designed and built in 1970 is extremely severe for main steam header compartment and main feedwater line region of intermediate building and lower floor. A calculation for flood level at the main feedwater line isolation compartment is now performing by hand calculation. But, this methodology is quite conservative assumption. The goal of this study was to develop method to analyze flowrate using the RETRAN-3D computer code, and the developed method was applied to flood level analysis following main feedwater line break. As a result of analysis, flood level was low remarkably.

• Journal of the Society of Disaster Information
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• v.13 no.3
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• pp.358-365
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• 2017

As the damage caused by disasters increases rapidly around the world, it is necessary to develop the technology for equipment to reduce human injury. Therefore in the support of fire safety and 119 rescue and rescue technology research and development project, in the "Development of a power assist device for a fireman to rescue humans(2015 ~ 2018)" for life saving restoration, we are developing equipment that satisfies the lifting performance considering the disaster environment and the disaster response scenario(Amount of load over 100 kg, height of over 1 m, height over middle 60 cm, speed over 0.2 m/s). In this study, we propose a lifting performance and environmental test method to evaluate the usefulness of the power-assisted device and analyze and verify detailed specifications of the device through dynamics analysis of the lifting performance test. This study suggests that the proposed test method can be applied practically to evaluate whether a stable performance of a power-assisted device is achieved.

• Journal of Power System Engineering
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• v.20 no.5
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• pp.52-59
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• 2016

Environmental Qualification has been almost developed except those of Non-Material Sub-components for valves and pumps though the time has only passed about 10years since EQ test launch of Korea. However EQ test has been performed by a few of engineers under the conditions that experience of EQ test is insufficient and EQ system is not developed completely. In recent years, Strengthen Nuclear Safety Regulation is being done Strictly Nuclear safety components Verification Procedure for Non-Material Sub-components, but the reports contain only performance test results, not Enviro nmental test methods relating to real Aging Degradation. In this Study, there were developed to performance systematically research to acquire EQ technology for five specimens of the Non-Material Sub-components in the Nuclear Power Plant.