• 제목/요약/키워드: Nuclear risk

검색결과 932건 처리시간 0.027초

CURRENT RESEARCH AND DEVELOPMENT ACTIVITIES ON FISSION PRODUCTS AND HYDROGEN RISK AFTER THE ACCIDENT AT FUKUSHIMA DAIICHI NUCLEAR POWER STATION

  • NISHIMURA, TAKESHI;HOSHI, HARUTAKA;HOTTA, AKITOSHI
    • Nuclear Engineering and Technology
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    • 제47권1호
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    • pp.1-10
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    • 2015
  • After the Fukushima Daiichi nuclear power plant (NPP) accident, new regulatory requirements were enforced in July 2013 and a backfit was required for all existing nuclear power plants. It is required to take measures to prevent severe accidents and mitigate their radiological consequences. The Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R) has been conducting numerical studies and experimental studies on relevant severe accident phenomena and countermeasures. This article highlights fission product (FP) release and hydrogen risk as two major areas. Relevant activities in the S/NRA/R are briefly introduced, as follows: 1. For FP release: Identifying the source terms and leak mechanisms is a key issue from the viewpoint of understanding the progression of accident phenomena and planning effective countermeasures that take into account vulnerabilities of containment under severe accident conditions. To resolve these issues, the activities focus on wet well venting, pool scrubbing, iodine chemistry (in-vessel and ex-vessel), containment failure mode, and treatment of radioactive liquid effluent. 2. For hydrogen risk: because of three incidents of hydrogen explosion in reactor buildings, a comprehensive reinforcement of the hydrogen risk management has been a high priority topic. Therefore, the activities in evaluation methods focus on hydrogen generation, hydrogen distribution, and hydrogen combustion.

A CYBER SECURITY RISK ASSESSMENT FOR THE DESIGN OF I&C SYSTEMS IN NUCLEAR POWER PLANTS

  • Song, Jae-Gu;Lee, Jung-Woon;Lee, Cheol-Kwon;Kwon, Kee-Choon;Lee, Dong-Young
    • Nuclear Engineering and Technology
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    • 제44권8호
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    • pp.919-928
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    • 2012
  • The applications of computers and communication system and network technologies in nuclear power plants have expanded recently. This application of digital technologies to the instrumentation and control systems of nuclear power plants brings with it the cyber security concerns similar to other critical infrastructures. Cyber security risk assessments for digital instrumentation and control systems have become more crucial in the development of new systems and in the operation of existing systems. Although the instrumentation and control systems of nuclear power plants are similar to industrial control systems, the former have specifications that differ from the latter in terms of architecture and function, in order to satisfy nuclear safety requirements, which need different methods for the application of cyber security risk assessment. In this paper, the characteristics of nuclear power plant instrumentation and control systems are described, and the considerations needed when conducting cyber security risk assessments in accordance with the lifecycle process of instrumentation and control systems are discussed. For cyber security risk assessments of instrumentation and control systems, the activities and considerations necessary for assessments during the system design phase or component design and equipment supply phase are presented in the following 6 steps: 1) System Identification and Cyber Security Modeling, 2) Asset and Impact Analysis, 3) Threat Analysis, 4) Vulnerability Analysis, 5) Security Control Design, and 6) Penetration test. The results from an application of the method to a digital reactor protection system are described.

AHP를 이용한 원자력발전소 건설공사의 단위작업 위험도 평가 (Assessment of risk of unit work in nuclear power plant construction using AHP)

  • 이종빈;장성록
    • 한국안전학회지
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    • 제29권2호
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    • pp.62-67
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    • 2014
  • The purpose of this study is to analyze the degree of risk of the working unit of nuclear power plants construction. In order to do this, and the risk index by type and source of risk judgment derived in the previous study were utilized. Further, to derive a risk index of unit work in nuclear power plant construction, a survey targeting safety professionals was conducted. The analytic hierarchy process (AHP) was used for analysis of the survey. The following results were obtained. Firstly, the results of AHP showed that main building work is the most dangerous work, and base excavation work is the second dangerous work among 21 unit works. Secondly, so, it is required to invest more and to take a increasing interest in unit works of civil and architecture as compared to other unit works. Further, the results could be used to reduce the degree of risk in construction of the nuclear power plant.

한국표준형원전의 격납건물종합누설률 시험 주기연장에 대한 리스크 평가 (Risk Assessment of Integrated Leak Rate Test(ILRT) Extension for Korea Standard Nuclear Power Plant)

  • 지문구;황석원;오지용
    • 한국안전학회지
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    • 제26권5호
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    • pp.99-104
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    • 2011
  • An ILRT Interval for a nuclear power plant in Korea was extended from once in five years to once in ten years. Therefore, it is necessary to evaluate risk impact for ILRT interval extensions. In this paper, input data were generated for the reference plants, KSNP, using raw data such as meteorological data, population distribution data and source term data. And, using MACCS II code the risk impact assessment was performed based on the two methodologies of NUREG-1493 and NEI Interim Report. The risk impact derived from an ILRT interval extension was identified not to be significant. It is considered to apply this study and results to making an accident management plan and safety goal, and to the field of public acceptance.

How should the regulatory defaults be set?

  • Jang, Seung-Cheol
    • Nuclear Engineering and Technology
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    • 제50권7호
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    • pp.1099-1105
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    • 2018
  • How to choose defaults in risk-informed regulations depends on the conservatism implicated in regulatory defaults. Without a universal agreement on the approaches dealing with the conservatism of defaults, however, the desirability of conservatism in regulatory risk analyses has long been controversial. The opponent views it as needlessly costly and irrational, and the proponent as a form of protection against possible omissions or underestimation of risks. Moreover, the inherent ambiguity of risk makes it difficult to set suitable defaults in terms of risk. This paper, the extension of the previous work [1], focuses on the effects of different levels of conservatism implicated in regulatory defaults on the estimates of risk. According to the postulated behaviors of regulated parties and the diversity of interests of regulators, in particular, various measures for evaluating the effect of conservatism in defaults are developed and their properties are explored. In addition, a simple decision model for setting regulatory defaults is formulated, based on the understanding of the effect of conservatism implicated in them. It can help decision makers evaluate the levels of safety likely to result from their regulatory policies.

Risk Monster를 이용한 On-Line Maintenance

  • 김길유;박창규
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.713-718
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    • 1996
  • Risk Monster는 한국원자력연구소에서 개발한 risk monitor로서 발전운영시 및 정비계획시 원전의 기기 운영 상태 (=Configuration)의 실제 변경이나 계획시 이에 따른 원전의 안전성 (또는 Risk)를 평가 및 감시하는 시스템이다. 안전성은 노심손상 빈도를 가지고 평가하며 이 Risk Monster의 국내 원전에의 활용, 특히 on-line maintenance시의 활용을 모색하였다. 외국에서처럼 국내 원전에서도 risk monitor를 이용한 on-line maintenance를 실시 하여 원전의 경제성 및 안전성을 향상 시켜야 한다.

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원자력발전소 지진 PSA의 계통분석방법 개선 연구 (A Study of System Analysis Method for Seismic PSA of Nuclear Power Plants)

  • 임학규
    • 한국안전학회지
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    • 제34권5호
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    • pp.159-166
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    • 2019
  • The seismic PSA is to probabilistically estimate the potential damage that a large earthquake will cause to a nuclear power plant. It integrates the probabilistic seismic hazard analysis, seismic fragility analysis, and system analysis and is utilized to identify seismic vulnerability and improve seismic capacity of nuclear power plants. Recently, the seismic risk of domestic multi-unit nuclear power plant sites has been evaluated after the Great East Japan Earthquake and Gyeongju Earthquake in Korea. However, while the currently available methods for system analysis can derive basic required results of seismic PSA, they do not provide the detailed results required for the efficient improvement of seismic capacity. Therefore, for in-depth seismic risk evaluation, improved system analysis method for seismic PSA has become necessary. This study develops a system analysis method that is not only suitable for multi-unit seismic PSA but also provides risk information for the seismic capacity improvements. It will also contribute to the enhancement of the safety of nuclear power plants by identifying the seismic vulnerability using the detailed results of seismic PSA. In addition, this system analysis method can be applied to other external event PSAs, such as fire PSA and tsunami PSA, which require similar analysis.

A software tool for integrated risk assessment of spent fuel transportation and storage

  • Yun, Mirae;Christian, Robby;Kim, Bo Gyung;Almomani, Belal;Ham, Jaehyun;Lee, Sanghoon;Kang, Hyun Gook
    • Nuclear Engineering and Technology
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    • 제49권4호
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    • pp.721-733
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    • 2017
  • When temporary spent fuel storage pools at nuclear power plants reach their capacity limit, the spent fuel must be moved to an alternative storage facility. However, radioactive materials must be handled and stored carefully to avoid severe consequences to the environment. In this study, the risks of three potential accident scenarios (i.e., maritime transportation, an aircraft crashing into an interim storage facility, and on-site transportation) associated with the spent fuel transportation process were analyzed using a probabilistic approach. For each scenario, the probabilities and the consequences were calculated separately to assess the risks: the probabilities were calculated using existing data and statistical models, and the consequences were calculated using computation models. Risk assessment software was developed to conveniently integrate the three scenarios. The risks were analyzed using the developed software according to the shipment route, building characteristics, and spent fuel handling environment. As a result of the risk analysis with varying accident conditions, transportation and storage strategies with relatively low risk were developed for regulators and licensees. The focus of this study was the risk assessment methodology; however, the applied model and input data have some uncertainties. Further research to reduce these uncertainties will improve the accuracy of this model.

Moderating effect of regulatory focus on public acceptance of nuclear energy

  • He, Yanling;Li, Yazhou;Xia, Dongqin;Zhang, Tingting;Wang, Yongliang;Hu, Li;Gu, Jibao;Wu, Yican
    • Nuclear Engineering and Technology
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    • 제51권8호
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    • pp.2034-2041
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    • 2019
  • Public acceptance has become the most critical question for sustainable development of nuclear energy in recent decades. Many researches concentrated on risk and benefit perception, which were deemed as the most influential factors of Public Acceptance of Nuclear Energy (PANE). But few researches focused on psychological factors including regulatory focus. Therefore, this paper aimed to explore the moderating effect of regulatory focus on PANE based on Regulatory Focus Theory in order to find ways to increase/decrease PANE. An Internet-based survey had been carried out in China nationwide. The results indicated that trust in government was positively related to PANE and this relationship was mediated by risk and benefit perception. In addition, the strength of the associations between risk and benefit perception and PANE were moderated by regulatory focus, consisting of prevention focus and promotion focus. Prevention focus strengthened the negative relationship between risk perception and PANE, while promotion focus weakened. Moreover, promotion focus weakened the positive relationship between benefit perception and PANE, but no significant moderating effect of prevention focus was founded on the relationship between benefit perception and PANE. Some policy implications were also proposed on the basis of above-mentioned findings.