• 한국안전학회지
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• 제21권1호
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• pp.1-5
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• 2006

The damage of important equipments for the nuclear power plant by the earthquake brings the loss of human lives and economic losses. Therefore safety-related equipment of nuclear power plant must be proved that function must be designed and structural integrity so that it can be maintained also from accident condition of various kinds. In this study, the computer room air conditioner to be delivered at the nuclear power plant applied to this qualification, try to develop an optimum model. This model ended up with good results which were under suitably allowable conditions about structurally safe earthquake.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1993년도 하계학술대회 논문집 B
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• pp.609-611
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• 1993

Because the Nuclear power plant needs for the specific high stability and the confidence, it is required that cable shall be flame retardant at fire and endure to be exposed by radiation, chemical fluid, steam and high temperature at sudden accident condition and be maintained its capability on nomal operation up to 40 years as same as it's service life for Nuclear Power Plant. Consequently, In this report, we describe the terms of Environmental Qualification Test for cable and properties required for cable which developed for Nuclear Power Plant.

• 한국콘텐츠학회논문지
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• 제13권9호
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• pp.281-287
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• 2013

본 연구는 부산광역시 거주민을 대상으로 배경 변인에 따라 방사선에 대한 지식, 지식수준의 지각, 방사선의 편익과 원자력 위험에 대한 인식, 그리고 후쿠시마 원전 사고 관련 정보수집과 인식 등은 어떻게 다른지를 알아보기 위한 목적으로 진행되었다. 분석을 위한 연구 대상은 414명의 거주민이다. 그 결과, 조사대상자들은 방사선의 필요성은 원칙적으로 인정하나 안전성에 대해서는 부정적인 인식을 가지고 있는 것으로 분석되었다. 이러한 부정적 인식은 방사선에 대한 지식을 기반으로 한 것이 아니라 과거 원전 사고 등에 기인한 것으로 판단되며, 향후 올바른 인식 전환을 위해서는 미디어를 통한 방사선과 원자력에 대한 교육과 홍보 그리고 방사선지식의 폭을 넓히고 나아가 보다 다양한 측면에서 시민들의 인식 변화를 위한 노력이 필요하다고 사료된다.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.931-942
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• 2019

Radioactive materials are released from the molten core into the containment at the time of a severe accident in a nuclear power plant (NPP). Filtered containment venting system is a popular and effective safety measure installed to obstruct the uncontrolled escape of radioactive materials due to the over pressurization of the containment. Different designs of filtered containment venting system (FCVS) are available today, each being the result of extensive research and development varying in one way or the other. This paper gives an elaborate description of the different types of FCVS currently being used, the current usage status in over 17 countries and the legislations regarding it. The recent researches being carried out in this field has also been discussed in detail. This present paper focuses on the critical review of existing FCVS, reports the challenges faced by it and highlights the potential developments to overcome the difficulties.

• 한국안전학회지
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• 제29권6호
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• pp.172-178
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• 2014

In terms of an accident management, the cases causing severe core damage need to be analyzed and arranged systematically for an easy access to the results since the Three Mile Island (TMI) accident. The objectives of this paper are to explain how to identify the plant response and cope with its vulnerabilities using the probabilistic safety assessment (PSA) quantified results and severe accident database SARDB(Severe Accident Risk Data Bank) based on sequences analysis results. Although PSA has been performed for the Korean Standard Power Plants (KSNPs), and that it considered the necessary sequences for an assessment of the containment integrity. The developed Database (DB) system includes a graphical display for a plant and equipment status, previous research results by a knowledge-based technique, and the expected plant behaviour. The plant model used in this paper is oriented to the cases of loss of coolant accident (LOCA) is be used as a training simulator for a severe accident management.

• Journal of Radiation Protection and Research
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• 제37권1호
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• pp.1-9
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• 2012

2011년 3월 11일 발생한 일본 후쿠시마 원전 사고 1주년을 계기로 한국 국민의 방사선 인식도를 조사하고자 하였다. 연구 방법론적 설계는 양적 조사로 하고, 빈도 분석을 하였다. 분석 대상은 전국에서 무작위로 추출한 일반인으로부터 수거한 설문 응답지 2754부이다. 연구 도구는 설문지이며, 직접 배포한 뒤 수거하였다. 설문은 40문항으로 구성하였으며, 하위영역별 크론바하 알파(Cronbach's ${\alpha}$) 계수는 '방사선의 자아인식' 0.620, '방사선의 위험' 0.830, '방사선의 편익' 0.781, '방사선의 관리' 0.685, '방사선의 정보원' 0.831, '후쿠시마 사고의 영향 정도' 0.763으로 모두 높게 나타났다. 설문 분석 결과 응답자의 방사선 개념에 대한 지식은 100점 만점 환산 평균 69.5점이며, 이는 자신들이 '방사선에 대해 잘 알고 있다'고 응답한 비율 53.7%, '보통 알고 있다'는 응답이 37.4%인 것과는 상당히 다른 결과다. '방사선이 위험하다'고 느끼는 중요 원인 중 하나는 '방사선에 노출되면 지금은 아니더라도 다음 세대에 문제가 생길 수 있기 때문'(66.1%)으로 분석됐다. 방사선에 대한 정부 발표를 믿지 못하는 응답자가 41%에 이르러 정부에 대한 불신이 높았다. 후쿠시마 원전 사고 때문에 원전을 운영하지 말아야 한다는 쪽으로 생각을 바꾼 응답자도 39.5%나 됐다. 본 연구는 후쿠시마 원전 사고 이후 방사선에 대한 한국 국민의 인식을 처음 조사한 것으로 그 의의가 크다. 향후 방사선에 대한 정부의 정책 수립에도 크게 기여할 것으로 기대된다.

• 한국안전학회지
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• 제28권3호
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• pp.95-99
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• 2013

The goal of this study was to investigate some significant factors to influence level of safety at plant construction field and analyze degree of risk by work classification. Currently, there are lots of construction fields for the nuclear power plant for electricity generation, and our government also planned constructing more nuclear power plant in near future. However, much of the safety literature neglected the degree of risk factors on the plant construction field. Safety managers participated in the brainstorming session for drawing decision criteria of the degree of risk (i.e., significant factors). Then, they were asked to answer a structured questionnaire which was developed for drawing most important factors. Finally, the analytic hierarchy process (AHP) was used to analyze level of risk by work classification. The following results were obtained. First, total twelve factors judging degree of risk were found in the brainstorming session. Second, the questionnaire showed four significant factors, including number of workers, working environments, skill of craft and accident experience. Third, the results of AHP showed Architecture work is the most dangerous work among 6 work types. The results could be used to reduce degree of risk in construction field of the nuclear power plant.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1993년도 하계학술대회 논문집 A
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• pp.525-528
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• 1993

KEPCO Research Center is carrying out a simulator(full scope replica type) development project for two nuclear power plants(Kori-2, Younggwang-3,4) and one fossil power plant(Poryong-3,4). In this project, we aim not only the installation of high performance simulators at the power plant sites but also the realization of self reliance of power plant simulation technology in Korea. In the course of preparing procurement specification for the 3 simulators, the present status of power plant simulation technology has been surveyed and is presented in this paper. The fidelity of simulation and the automation of simulation model production has been greatly improved due to the ever increasing computing power of today's workstations. The need and importance of the application of high fidelity simulators to the operator training is refocused since the accident at TMI Nuclear Power Plant, U.S.A.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.56-61
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• 2016

After Japanese Fukushima nuclear power plant accident caused by the beyond design basis earthquake and tsunami, it has turned to be a major challenge for nuclear safety. IAEA, US NRC and EU have provided new safety design standards for beyond design basis event, Domestic regulatory bodies have also enacted guidances for licensees and applicants on additional methods related to beyond design basis events. This paper describes several evaluation methods for applying to nuclear power plants piping for beyond design basis earthquake. As a results, energy method based on the absorbed energy on nuclear power plant, deterministic method following design code and theory, experience method considering past earthquake data and information and probabilistic methods similar to probabilistic risk assessment were reviewed.

• International Journal of Reliability and Applications
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• 제3권1호
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• pp.25-35
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• 2002

This paper presents a dynamic reliability assessment methodology for use in the safety assessment of a complex system such as a nuclear power plant. The method is applied to a dynamic analysis of the potential accident sequences that may occur during mid-loop operation in a nuclear power plant. The idea behind this approach consists of both the use of the concept of the performance achievement/requirement correlation and of a dynamic event tree generation method. The assessment of the system reliability depends on the determination of both the required performance distribution and the achieved performance distribution. The quantified correlation between requirement and achievement represents a comparison between two competing variables. It is demonstrated that this method is easily applicable and flexible in that it can be applied to any kind of dynamic reliability problem.