• Fire Science and Engineering
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• v.30 no.4
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• pp.20-26
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• 2016

When the fire takes place in Nuclear Powr Plants(NPPs), the reactor should achieve and maintain safe shut-down conditions and minimize the radioactive material released to the environment. The U.S. Nuclear Regulatory Commission (NRC) has issued numerous generic communications related to fire protection over the past 20 years, after it issued its requirements in the Fire Protection Rule set forth in Title 10, Section 50.48 of the Code of Federal Regulations (10 CFR 50.48) and Appendix R to the 10 CFR 50. The and Nuclear Energy Institute (NEI) has developed a Methodology for Risk Informed Fire Safe-Shutdown Analysis, which is related to the Deterministic Method for Multiple Spurious Operations solutions. The aim of this study was to identify, achieve, and maintain Post-Fire Safe-Shutdown of the Main Control Room (MCR) of the CANDU reactor, even though one train of the multiple Safety Structures, Systems, and Components (SCCs) fail by the technical specification and analysis method.

• Fire Science and Engineering
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• v.32 no.1
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• pp.57-65
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• 2018

In this study, a post-fire safe shutdown analysis (PFSSA) including multiple spurious operation (MSO) treatments for cables was conducted with an imaginary nuclear power plant for training using a deterministic fire analysis code. The imaginary nuclear power plant for the training consisted of a reactor containment building and an auxiliary building, including a total of 22 fire areas. The equipment including valves, pumps, emergency diesel generators, switch gears, motor control centers, and logic controllers were located in each fire area of the imaginary plant. It was assumed that each equipment is connected with two cables and that each cable passes through the fire areas along the cable trays. A database containing the information on the equipment and cables for the imaginary plant was constructed for the fire area analysis. The fire area analysis was performed for several assumed MSO scenarios, equipment logics, and cable logics. A mitigation measure using a three hour rated wrap was applied to the failed cables and cable trays after the fire area analysis.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.991-992
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.123.1-123
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• 2001

• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2010.10a
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• pp.203-206
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• 2010

운전원 수동조치는 원자력발전소 화재시 발전소 안전정지를 달성하고 유지하기 위하여 절차에 따라 주제어실 이외의 장소에서 취하는 운전원의 행위를 말한다. 화재시 운전원 수동조치는 발전소 정상운전 동안의 조치에 비해 더 긴장된 상태에서 정해진 시간내에 임무를 완수하여야 한다는 점 때문에 조치성공 가능성을 확인하기 위하여는 행위의 타당성과 신뢰성이 입증되어야 한다. 운전원 수동조치의 타당성과 신뢰성은 조치의 가용시간, 환경조건 등 10가지의 인자를 고려한 시간분석, 절차 및 훈련, 이행, 입증의 과정을 거쳐서 검증될 수 있다.