• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.9 no.1
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• pp.35-39
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• 2013

The Operating Experience Report(OER) has written about the event and accident happened at a Nuclear Power Plant(NPP). The purpose of publishing the OER is to prevent the similar event or accident repeatedly by spreading the experience of a single plant to other plants personnel. Before initiating the analysis mentioned in this paper, 2,298 review reports for the same number of OER published from 2007 to June 2012 have been written to achieve the correct and objective statistics. The analysis introduced in this paper is performed with the various factors such as year, plant type, equipment, type of work, root-cause. The root-cause analysis is showed that the equipment problem is the major factor in domestic NPPs, but on the other hand human-error is the main part of the foreign NPPs. Moreover, while the number of the man-made event is decreasing, the equipment-made event is rapidly increasing in domestic NPPs.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.9 no.1
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• pp.31-34
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• 2013

According to the increase in numbers and operation time of domestic Nuclear Power Plants, KHNP(Korea Hydro & Nuclear Power) has many operating experiences. These show that most of the accidents repeatedly occurred not by the new sources or mechanism like the Fukushima Accident, but by the human and equipment errors from normal habits, process, design, maintenance etc.. These lessons show that the well-established systematic approach is requested to take lessons from past experiences. For this reason, developed countries established INPO, WANO, COG as a non-profit professional organizations to actively share their operating experiences. KHNP is also trying to promote the utilization of operating experiences. As part of this effort, KHNP is developing the KHNP-JIT, reflecting the overseas JIT and the domestic experiences.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.34 no.4
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• pp.495-499
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• 2010

In this paper, the regulatory guidelines for the continued operation of the CANDU reactor in Korea were introduced. Wolsong Unit 1, which is a CANDU 600 reactor in Korea, will reach its design life of 30 years in 2012. A licensee who wants to operate a nuclear power plant beyond its design life should submit reports of periodic safety reviews (PSRs) conducted on the basis of 11 safety factors. In addition, the licensee should provide the following: (1) scoping and screening results for aging management, (2) aging management program, (3) TLAA, including the continued operation term, (4) operation-experience feedback, and (5) important safety-research results. In this study, 54 regulatory guidelines for the five above-mentioned items for the CANDU reactor in Korea were developed.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.10 no.1
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• pp.70-74
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• 2014

An Operating Experience Report(OER) has written about events and accidents happened at a Nuclear Power Plant(NPP). The purpose of publishing the OER is to prevent the similar event or accident repeatedly by spreading the experience of a single plant to other plants personnel. In this paper, it is analyses that the foreign NPPs' OERs on JIT published by the International Nuclear Agency(WANO, INPO, COG, BE). The analysis introduced in this paper is performed along with the various factors such as type of work, root-cause, and equipment. The root-cause analysis about the OERs shows that the Human-error is the major factor in foreign NPPs, but on the other hand equipment problem is the main part of the Domestic NPPs. The ratio of the foreign NPP's OERs on JIT according to the type of work was applied to KHNP-JIT developed nowadays for the first time in KOREA.

• Nuclear industry
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• v.5 no.11 s.33
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• pp.56-65
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• 1985

다음은 미국 MIT원자력공학과의 Hansen 교수와 서독 베를린공과대학의 Winje교수가 공동으로 양국 원자력발전소의 가동실적(1980-1983년까지 년간)을 비교분석한 보고서의 내용이다. 대상으로한 원자로는 미국이 PWR(WH사제) 21기, BWR(GE사제) 22기이고, 서독측은 PWR(KWU사제)6기, BWR(동)4기인데 주요분석은 PWR에 중점을 두고 있으며(표1, 표2) 대상으로한 원자로는 (1) 출력 400MWe이상 (2) 1980년이전에 상업운전개시 (3) NSSS와 터빈$\cdot$발전기의 공급자가 동일이라는 기준으로 선택되어 있다. 가동실적의 비교로는 공통의 지표로 가동율(일정기간중의 발전량을 동기간중의 정격출력발전량으로 나눈 것)을 사용하고 있다. 그밖에 발전손실(정격출력발전량과 실제발전량의 차이)의 원인을 비교분석하여 양국 원전운전실적의 상위와 그 요인$\cdot$배경을 명백히 하려는 것이 연구의 개요이다.

• Nuclear Engineering and Technology
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• v.15 no.1
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• pp.41-49
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• 1983

A computer code, BERD (Bayesian Estimation of Reliability Data), has been developed and tested in order to update the data for the reliability analysis of safety related systems in a specific nuclear power plant. The code has been used to derive the plant-specific data for reliability analysis of the auxiliary feedwater system of a pressurized water reactor. The prior information for components selected was taken from the U.S. Reactor Safety Study, WASH-1400, and the operating experiences from published licensee event reports. The results show that the updated data are well fitted to log-normal distribution curves and the error factors are reduced significantly.