• 방사성폐기물학회지
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• 제17권1호
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• pp.95-106
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• 2019

원전 해체를 준비함에 있어 정성적 또는 정량적 위험도 평가는 필수요소이다. 해체 공정간 발생하는 방사선학적 및 비방사선학적 위험요소는 해체 작업자 및 대중의 안전을 보장하기 위해 사전에 평가되어야 한다. 현재 해체 경험이 많은 미국의 기존 사업자들 및 NRC의 경우 위험의 중대성만 평가하는 결정론적 위험도 평가에 집중하고 있다. 하지만 최근 IAEA는 위험도 매트릭스를 활용한 위험도평가를 결정론적 위험도 평가의 대체안으로 제안하고 있다. 따라서 본 연구에서는 위험도평가에 앞서 해체 공정 별 해체 활동을 Risk Breakdown Structure에 맞추어 정리하였고, 미국 20여개 해체 원전에서 해체 공정별 위험도 평가 시행 중 선정한 해체 활동간 잠재적 사고를 해체 활동에 맞게 체계적으로 정리하였다. 그리고 복합 리스크 매트릭스를 개발 및 활용하여 해체 공정간 방사선학적 및 비방사선학적 위험요소의 위험도를 평가하여 정량적으로 수치화 하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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• pp.568-573
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• 1995

Technical Specifications (TSs) for a nuclear power plant is an important licensing document which defines various operational requirements or conditions. Recently, many researchers have evaluated the risk impacts associated with the TS requirements, using probabilistic safety assessments becoming widely available. This paper presents insights gained km our review of recent risk-based analyses of TSs, focussing on surveillance requirements and AOT (allowed outage time) requirements.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.838-843
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• 1998

Risk importance measures are widely wed to rank risk contributors in risk-based applications. Typically, Fussell-Vesely (F-V) importance and risk achievement worth (RAW) are used in the component importance raking for the reliability centered maintenance (RCM) analysis of safety system in nuclear power plants (NPPs). This study was performed as part of feasibility study on RCM for domestic NPPs, which is focused on the component importance ranking approach the maintenance recommendation. The approach of modulizing faulting tree basic events was applied in the simplification process of the PSA model and the validity of the approach was evaluated As a result of the case study, this paper included the importance and the maintenance recommendations for the safety-related equipments associated with safety injection and containment spray in large loss of coolant accident sequences.

• 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.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 추계학술발표회요약집
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• pp.386-386
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• 2001

• 한국안전학회지
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• 제32권1호
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• pp.134-139
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• 2017

This study has been performed to investigate the risk perceptions of employees in nuclear power plants. A representative sample of 473 employees was surveyed(about 79% response rate). The questionnaire included scales on both risk perceptions of critical five hazards that could be occurring in the nuclear power plants and two psychometric attitudes. Higher risk perceptions between managers and non-managers to five hazards used in this study were entirely obtained from the managers. It was also found that the perceived higher hazards were in the following order: radiation exposure, radioactive release, explosion, fire and radioactive waste. For the controllability, higher risk perceptions to the all factors were obtained from the managers, and higher ones were non-managers in the dread.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1814-1820
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• 2023

Safety classification of systems, structures, and components (SSC) is an essential activity for nuclear reactor design and operation. The current regulatory trend is to require risk-informed safety classification that considers first, the severity, but also the frequency of SSC failures. While safety classification for nuclear power plants is covered in many regulatory and scientific publications, research reactors received less attention. Research reactors are typically of lower power but, at the same time, are less standardized i.e., have more variability in the design, operational modes, and operating conditions. This makes them more challenging when considering safety classification. This work presents the Integrated Risk-Informed Safety Classification (IRISC) procedure which is a novel extension of the IAEA recommended process with dedicated probabilistic treatment of research reactor designs. The article provides the details of probabilistic analysis performed within safety classification process to a degree that is often missing in most literature on the topic. The article presents insight from the implementation of the procedure in the safety classification for the MARIA Research Reactor operated by the National Center for Nuclear Research in Poland.

• Nuclear Engineering and Technology
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• 제37권3호
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• pp.273-278
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• 2005

Key concepts in South Korean nuclear safety regulation are safety and risk. Nuclear regulation in South Korea has required reactor designs and safeguards that reduce the risk of a major accident to less than one in a million reactor-years-a risk supposedly low enough to be acceptable. To date, in South Korean nuclear safety regulation has involved the establishment of many technical standards to enable administration enforcement. In scientific lawsuits in which the legal issue is the validity of specialized technical standards that are used for judge whether a particular nuclear power plant is to be licensed, the concept of uncertainty law is often raised with regard to what extent the examination and judgment by the judicial power affects a discretion made by the administrative office. In other words, the safety standards for nuclear power plants has been adapted as a form of the scientific technical standards widely under the idea of uncertainty law. Thus, the improvement of nuclear safety regulation in South Korea seems to depend on the rational lawmaking and a reasonable, judicial examination of the scientific standards on nuclear safety.

• Nuclear Engineering and Technology
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• 제21권3호
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• pp.171-185
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• 1989

유연탄 발전과 원자력 발전의 경제성 평가를 균등한 인체 위험도 하에서 서기 2000년의 시점에서 수행하였다. 유연탄 발전과 원자력 발전의 인체에 대한 영향 비교에서, 유연탄의 영향이 원자력에 비해서 10배가량 높은 것을 에너지 시스템의 위험도 평가에 관한 여러 연구결과들로부터 알 수 있었다. 그런데 위험도가 0인 상태는 존재하지 않으므로, 유연탄 발전과 원자력 발전간의 위험도 차이만을 본 논문의 위험도로 간주했다. 인체 위험도 비용은 사망과 질병의 두 경우로 나누어서, 사망의 경우에는 Human Life Value로 계산하고, 질병의 경우에는 완치될 때까지의 치료비등 제반 비용으로 계산했다. 이러한 방법에 의한 계산 결과 사망의 비용은 ＄250,000이 되었고, 질병의 경우는 ＄90,000이 되었다. (1986 US＄) 그리고 비용편익분석을 통해서 유연탄 화력 발전의 최적 규제 기준치를 구했는데, 이 규제치는 최소 사회비용이 발생되는 지점에서 구해졌다. 서기 2000년의 한국에서의 SOx에 대한 최적 규제치는 165ppm으로 나타났다. 이러한 전력 생산의 경제성 평가 방법으로부터, 원자력이 유연탄 화력에 비해서 더 경제적인 것으로 나타났다. 반면에 불확실도는 유연탄화력이 더 작은 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제41권6호
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• pp.849-858
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• 2009

Risk caused by safety-critical instrumentation and control (I&C) systems considerably affects overall plant risk. As digitalization of safety-critical systems in nuclear power plants progresses, a risk model of a digitalized safety system is required and must be included in a plant safety model in order to assess this risk effect on the plant. Unique features of a digital system cause some challenges in risk modeling. This article aims at providing an overview of the issues related to the development of a static fault-tree-based risk model. We categorize the complicated issues of digital system probabilistic risk assessment (PRA) into four groups based on their characteristics: hardware module issues, software issues, system issues, and safety function issues. Quantification of the effect of these issues dominates the quality of a developed risk model. Recent research activities for addressing various issues, such as the modeling framework of a software-based system, the software failure probability and the fault coverage of a self monitoring mechanism, are discussed. Although these issues are interrelated and affect each other, the categorized and systematic approach suggested here will provide a proper insight for analyzing risk from a digital system.