• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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• pp.481-486
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• 1996

Safety management may be classified into three dimensions: (1) risk management, (2) accident management, and (3) emergency management. This paper addresses the recent trends of safety management in nuclear industry, focussing on risk management and accident management.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.442-449
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• 2017

Risk management of the Fukushima Daiichi Nuclear Power Station decommissioning is a great challenge. In the present study, a risk management framework has been developed for the decommissioning work. It is applied to fuel assembly retrieval from Unit 3 spent fuel pool. Whole retrieval work is divided into three phases: preparation, retrieval, and transportation and storage. First of all, the end point has been established and the success path has been developed. Then, possible threats, which are internal/external and technical/societal/management, are identified and selected. "What can go wrong?" is a question about the failure scenario. The likelihoods and consequences for each scenario are roughly estimated. The whole decommissioning project will continue for several decades, i.e., long-term perspective is important. What should be emphasized is that we do not always have enough knowledge and experience of this kind. It is expected that the decommissioning can make steady and good progress in support of the proposed risk management framework. Thus, risk assessment and management are required, and the process needs to be updated in accordance with the most recent information and knowledge on the decommissioning works.

• Nuclear Engineering and Technology
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• 제46권1호
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• pp.27-38
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• 2014

The Fukushima Dai-Ichi accident in 2011 has affected various aspects of the nuclear society worldwide. The accident revealed some problems in the conventional approaches used to ensure the safety of nuclear installations. To prevent such disastrous accidents in the future, we have to learn from them and improve the conventional approaches in a more systematic manner. In this paper, we will cover three issues. The first is to identify the key issues that affected the progress of the Fukushima Dai-Ichi accident greatly. We examine the accident from a defense-in-depth point of view to identify such issues. The second is to develop a more systematic approach to enhance the safety of nuclear installations. We reexamine nuclear safety from a risk point of view. We use the concepts of residual and unknown risks in classifying the risk space. All possible accident scenarios types are reviewed to clarify the characteristics of the identified issues. An approach is proposed to improve our conventional approaches used to ensure nuclear safety including the design of safety features and the safety assessments from a risk point of view. Finally, we address some issues to be improved in the conventional risk assessment and management framework and/or practices to enhance nuclear safety.

• 국제학술발표논문집
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• The 5th International Conference on Construction Engineering and Project Management
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• pp.451-458
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• 2013

This research documents the initial findings and recommendations for developing a risk management tool to assess and quantify the risks associated with the construction of the next generation of nuclear power plants. The proposed tool builds upon the Construction Industry Institute's International Project Risk Assessment (IPRA) Best Practice. This paper provides an overview of the investigation to assess the unique risk elements pertaining to nuclear power plant construction and documents the preliminary findings from historical project performance data to better understand the function and use of the IPRA's Relative Impact value.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4809-4818
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• 2022

The decommissioning project of a nuclear facility is a large-scale process that is expected to take about 15 years or longer. The range of risks to be considered is large and complex, then, it is expected that various risks will arise in decision-making by area during the project. Therefore, in this study, the risk family derived from the Decommissioning Risk Management (DRiMa) project was reconstructed into a decommissioning project risk profile suitable for the Kori Unit 1. Two criteria of uncertainty and importance are considered in order to prioritize the selected 26 risks of decommissioning project. The uncertainty is scored according to the relevant laws and decommissioning plan preparation guidelines, and the project importance is scored according to the degree to which it primarily affects the triple constraints of the project. The results of risks are divided into high, medium, and low. Among them, 10 risks are identified as medium level and 16 risks are identified as low level. 10 risks, which are medium levels, are classified in five categories: End state of decommissioning project, Management of waste and materials, Decommissioning strategy and technology, Legal and regulatory framework, and Safety. This study is a preliminary assessment of the risk of the decommissioning project that could be considered in the preparation stage. Therefore, we expect that the project risks considered in this study can be used as an initial data for reevaluation by reflecting the detail project progress in future studies.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.1090-1094
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• 2017

The determinants of the public's nuclear power acceptance have received considerable attention as decisive factors regarding nuclear power policy. However, the contingency of the relative importance of different determinants has been less explored. Building on the literature of psychological distance between the individual and the object, the present study demonstrates that the relative effects of different types of perceived risks regarding nuclear power generation differ across acceptance targets. Using a sample of Korea, our results show that, regarding national acceptance of nuclear power generation, perceived risk from nuclear power plants exerts a stronger negative effect than that from radioactive waste management; however, the latter exerts a stronger negative effect than the former on local acceptance of a nuclear power plant. This finding provides implications for efficient public communication strategy to raise nuclear power acceptance.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1199-1209
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• 2018

After the Fukushima-Daiichi accident in 2011, the multi-unit risk, i.e., the risk due to several nuclear power plants (NPPs) in a site has become an important issue in several countries such as Korea, Canada, and China. However, the multi-unit risk has been discussed for a long time in the nuclear community before the Fukushima-Daiichi nuclear accident occurred. The regulatory authorities around the world and the international organizations had proposed requirements or guidelines to reduce the multi-unit risk. The concerns regarding the multi-unit risk can be summarized in the following three questions: How much the accident of an NPP in a site affects the safety of other NPPs in the same site? What is the total risk of a site with many NPPs? Will the risk of the simultaneous accidents at several NPPs in a site such as the Fukushima Daiichi accident be low enough? The multi-unit risk assessment (MURA) in an integrated framework is a practical approach to obtain the answers for the above questions. Even though there were few studies to assess the multi-unit risk before the Fukushima-Daiichi nuclear accident, there are still several issues to be resolved to perform the complete MURA. This article aims to provide an overview of the multi-unit risk issues and its assessment. We discuss the several critical issues in the current MURA to get useful insights regarding the multi-unit risk with the current state art of probabilistic safety assessment (PSA) technologies. Also, the qualitative answers for the above questions are addressed.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2014년도 추계 학술논문 발표대회
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• pp.212-213
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• 2014

The purpose of this study is to suggest analysis model of RCB construction in nuclear power plant. For the objective, This study drew the risk factors of RCB construction from existing literature. The results of the study proposed analysis model made hierarchy in rebar, form, and concrete work. These will be baseline data for risk management in construction project of nuclear power plant.

• 핵의학기술
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• 제13권3호
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• pp.110-122
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• 2009

목적: 최근 의료기관평가제도는 의료의 질에 대한 병원들의 관심을 높게 하고 그것을 향상시키기 위한 활동을 활발히 전개하고 있다. 또한 추가된 항목인 환자의 위험관리에 대해서도 많은 관심을 보이고 있다. 의정부성모병원 핵의학과는 2008년도 PET/CT도입으로 시작된 부서내 리모델링은 과내 구조 및 업무 프로세스에 많은 변화를 가져왔다. 따라서 변경된 구조와 기존의 업무 처리방식은 미처 알지 못하는 위험요인을 내포하게 되었다. 그러므로 영상 검사 과정에서 발생할 수 있는 위험요인을 다각도로 찾고 분석하여, 부서의 특수한 환경에 맞는 위험관리 프로세스와 위험요인 제거업무를 포함한 개선 활동을 목적으로 한다. 실험재료 및 방법: 핵의학과의 새로워진 프로세스를 다각도로 분석하여 첫째, 위험관리 응대메뉴얼을 제작하여 교육후 실제 업무에 적용한다. 결과분석은 전년도 위험사고 발생건수와 개선활동 후 위험사고 발생건수를 비교하였다. 둘째, 위험관리 홍보동영상은 제작 후 검사전 해당 환자에게 상영하였고 그 후 자체 제작된 설문지로 해당 환자 100명에게 만족도 조사를 하였다. 셋째, 위험요소를 개선할 수 있는 시설물 참여형 개선활동을 통해서 위험요소를 제거하였다. 결과: 안전사고 발생건수는 개선활동이후 PET/CT와 감마카메라 영상 검사 모두 검사건수대비 투약오류, 낙상, 충돌 등의 안전사고가 0건으로 조사되었다. 설문조사 결과는 동영상 상영 후 검사진행과정 이해 74%, 불안감해소 81%로 "만족한다"는 결과가 조사되었다. "위험요소에 대해 주의했습니까?" 라는 물음의 경우 PET/CT는 94%, 감마카메라는 89%가 주의했다는 결과로 조사되었다. 개선활동을 통해서 핵의학과내에서의 고객위험관리를 효과적으로 수행할 수 있었다. 결론: 본 개선활동을 통하여 영상 검사 시 산재된 위험요소를 체계적으로 나열하고 분석하는 계기가 되었다. 또한 안전사고에 대처하는 방사선사의 업무방법에서도 기준이 되는 응대메뉴얼을 적용시킨다면 안전사고의 최소화와 안전사고시 체계적인 피드백이 가능함을 알 수 있었다. 위험요소를 알려주는 방법론적인 부분에서도 일상생활에서 쉽게 접할 수 있는 시청각자료로 제공 되었을 때 보다 효과적이였다. 따라서 이런 활동이 지속적이고 세부화 된 업그레이드 작업을 통해서 환자들에게 제작되어 제공된다면 핵의학 검사 이용의 안전성과 편리성에 도움을 줄 수 있으리라 생각된다.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.313-326
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• 2017

The systematic management of plant risk is crucial for enhancing the safety of nuclear power plants and for designing new nuclear power plants. Accident sequence precursor (ASP) analysis may be able to provide risk significance of operational experience by using probabilistic risk assessment to evaluate an operational event quantitatively in terms of its impact on core damage. In this study, an ASP methodology for two operation mode, full power and low power/shutdown operation, has been developed and applied to significant accident precursors that may occur during the operation of nuclear power plants. Two operational events, loss of feedwater and steam generator tube rupture, are identified as ASPs. Therefore, the ASP methodology developed in this study may contribute to identifying plant risk significance as well as to enhancing the safety of nuclear power plants by applying this methodology systematically.