• 제목/요약/키워드: severe accidents

검색결과 410건 처리시간 0.028초

폭발재해 예방대책에 관한 소고 (A Study on Prevention of Explosion Accidents)

  • 김인성
    • 화약ㆍ발파
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    • 제12권3호
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    • pp.32-41
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    • 1994
  • The specific characters in recent Chemical processing and industrial plants are the handling of severe limit conditions such as high pressure, high and low temperature, high speed production and transportation plant automation and appearance of many new hazardous materials in numbers and quantity. The possibilities of these characters causing the accident and environmental pollution in industrial activities become very high. This paper describes the concrete policy In prevent the explosion accident out of the many accidents which are the safety of the safety engineering.

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한국표준형 원전의 중대사고시 MACCS 코드를 이용한 위험성평가 (A Risk Assessment for A Korean Standard Nuclear Power Plant)

  • 황석원;제무성
    • Journal of Radiation Protection and Research
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    • 제28권3호
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    • pp.189-197
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    • 2003
  • Level 3 PSA(사고결말분석)는 원자력 발전소의 사고 시 누출된 방사성 핵종으로 인해 야기되는 환경 및 인체에 미치는 영향(공중위험도)을 평가하는 것이다. 본 논문에서는 원자력 발전소의 중대사고시 환경으로 방출되는 방사성물질의 방출특성과 그 결과로 인체에 미치는 영향에 대하여 확률론적 사고영향분석코드인 MACCS를 이용하여 평가하였다. 이러한 평가는 관련 변수들의 상대적 중요도를 파악하는데 유용할 뿐만 아니라 소외리스크(Offsite Risk)를 최소화시키기 위한 대책개발에 있어 중요한 지표가 될 수 있다. 특히 방출고도, 열 함량, 방출기간의 3가지 중요 변수를 선정하여, 이들 변수들의 변화에 따라 영향을 받는 조기사망자 수와 암 사망자 수의 변화를 분석하였다. 또한, 참조원전의 위험성 평가를 위하여 IPE(Individual Plant Examination)에서 제시된 STC(Source Term Category) 19가지 시나리오에 대한 각 사고별 빈도와 MACCS코드를 수행한 결과값을 이용하여 참조원전의 위험성 평가를 수행하였다.

Development of a Korean roadmap for technical issue resolution for fission product behavior during severe accidents

  • Kim, Han-Chul;Ha, Kwang Soon;Kim, Sung Joong;Seo, Miro;Kang, Sang-Ho;Lee, Doo Yong;Song, Yong-Mann;Lee, Jongseong;Im, Hee-Jung;Cho, Chang-Sok;Yeon, Jei-Won;Kim, Sung Il;Cho, Song-Won;Song, Jinho;Ryu, Yong-Ho
    • Nuclear Engineering and Technology
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    • 제49권8호
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    • pp.1575-1588
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    • 2017
  • In order to develop a domestic research roadmap for severe accidents, a special committee was established by the Korean Nuclear Society. One of the subcommittees discussed the characteristics and the relevant technical issues in the stages of fission product release and physical forms of radionuclide release and transport. The group members developed a tree to identify fission product release phenomena by tracing failures of individual defense-in-depth barriers and added possible countermeasures against failure. For each elemental issue, they searched for technical problems by examining the phenomena, accident management actions, and regulatory aspects relevant to the mitigation features for containment, including mitigation strategies against containment bypass accidents. Regulatory concerns, including the source term and the acceptance criteria for radionuclide release, were also considered. They identified further research needs regarding important technical issues based on the degree of the current knowledge level in Korea and in foreign countries, looking at the significance and urgency of issues and the expected research period required to reach an advanced level of knowledge. As a result, the group identified the 12 most important and urgent issues, most of which were expected to require mid-term and long-term research periods.

Characteristics of injuries associated with electric personal mobility devices: a nationwide cross-sectional study in South Korea

  • Kim, Maro;Suh, Dongbum;Lee, Jin Hee;Kwon, Hyuksool;Choi, Yujin;Jeong, Joo;Kim, Sola;Hwang, Soyun;Park, Joong Wan;Jo, You Hwan
    • Journal of Trauma and Injury
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    • 제35권1호
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    • pp.3-11
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    • 2022
  • Purpose: The increasing use of electric personal mobility devices (ePMDs) has been accompanied by an increasing incidence of associated accidents. This study aimed to investigate the characteristics of ePMD-related injuries and their associated factors. Methods: This cross-sectional study was conducted using data from the Emergency Department-based Injury In-depth Surveillance database from 2014 to 2018. All patients who were injured while operating an ePMD were eligible. The primary outcome was the rate of severe injury, defined as an excess mortality ratio-adjusted Injury Severity Score of ≥25. We calculated the adjusted odds ratios (AORs) of outcomes associated with ePMD-related injuries. Results: Of 1,391,980 injured patients, 684 (0.05%) were eligible for inclusion in this study. Their median age was 28 years old, and most injuries were sustained by men (68.0%). The rate of ePMD-related injuries increased from 3.1 injuries per 100,000 population in 2014 to 100.3 per 100,000 population in 2018. A majority of the injuries occurred on the street (32.7%). The most commonly injured area was the head and face (49.6%), and the most common diagnosis was superficial injuries or contusions (32.9%). Being aged 55 years or older (AOR, 3.88; 95% confidence interval, 1.33-11.36) and operating an ePMD while intoxicated (AOR, 2.78; 95% confidence interval, 1.52-5.08) were associated with severe injuries. Conclusions: The number of emergency room visits due to ePMD-related injuries is increasing. Old age and drunk driving are both associated with serious injuries. Active traffic enforcement and safety regulations regarding ePMDs should be implemented to prevent severe injuries caused by ePMD-related accidents.

Theoretical Model for Accident Prevention Based on Root Cause Analysis With Graph Theory

  • Molan, Gregor;Molan, Marija
    • Safety and Health at Work
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    • 제12권1호
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    • pp.42-50
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    • 2021
  • Introduction: Despite huge investments in new technology and transportation infrastructure, terrible accidents still remain a reality of traffic. Methods: Severe traffic accidents were analyzed from four prevailing modes of today's transportations: sea, air, railway, and road. Main root causes of all four accidents were defined with implementation of the approach, based on Flanagan's critical incident technique. In accordance with Molan's Availability Humanization model (AH model), possible preventive or humanization interventions were defined with the focus on technology, environment, organization, and human factors. Results: According to our analyses, there are significant similarities between accidents. Root causes of accidents, human behavioral patterns, and possible humanization measures were presented with rooted graphs. It is possible to create a generalized model graph, which is similar to rooted graphs, for identification of possible humanization measures, intended to prevent similar accidents in the future. Majority of proposed humanization interventions are focused on organization. Organizational interventions are effective in assurance of adequate and safe behavior. Conclusions: Formalization of root cause analysis with rooted graphs in a model offers possibility for implementation of presented methods in analysis of particular events. Implementation of proposed humanization measures in a particular analyzed situation is the basis for creation of safety culture.

Fuzzy-technique-based expert elicitation on the occurrence probability of severe accident phenomena in nuclear power plants

  • Suh, Young A;Song, Kiwon;Cho, Jaehyun
    • Nuclear Engineering and Technology
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    • 제53권10호
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    • pp.3298-3313
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    • 2021
  • The objective of this study is to estimate the occurrence probabilities of severe accident phenomena based on a fuzzy elicitation technique. Normally, it is difficult to determine these probabilities due to the lack of information on severe accident progression and the highly uncertain values currently in use. In this case, fuzzy set theory (FST) can be best exploited. First, questions were devised for expert elicitation on technical issues of severe accident phenomena. To deal with ambiguities and the imprecision of previously developed (reference) probabilities, fuzzy aggregation methods based on FST were employed to derive the occurrence probabilities of severe accidents via four phases: 1) choosing experts, 2) quantifying weighting factors for the experts, 3) aggregating the experts' opinions, and 4) defuzzifying the fuzzy numbers. In this way, this study obtained expert elicitation results in the form of updated occurrence probabilities of severe accident phenomena in the OPR-1000 plant, after which the differences between the reference probabilities and the newly acquired probabilities using fuzzy aggregation were compared, with the advantages of the fuzzy technique over other approaches explained. Lastly, the impact of applying the updated severe accident probabilities on containment integrity was quantitatively investigated in a Level 2 PSA model.

LIGHT WATER REACTOR (LWR) SAFETY

  • Sehgal Bal Raj
    • Nuclear Engineering and Technology
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    • 제38권8호
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    • pp.697-732
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    • 2006
  • In this paper, a historical review of the developments in the safety of LWR power plants is presented. The paper reviews the developments prior to the TMI-2 accident, i.e. the concept of the defense in depth, the design basis, the large LOCA technical controversies and the LWR safety research programs. The TMI-2 accident, which became a turning point in the history of the development of nuclear power is described briefly. The Chernobyl accident, which terrified the world and almost completely curtailed the development of nuclear power is also described briefly. The great international effort of research in the LWR design-base and severe accidents, which was, respectively, conducted prior to and following the TMI-2 and Chernobyl accidents is described next. We conclude that with the knowledge gained and the improvements in plant organisation/management and in the training of the staff at the presently-installed nuclear power stations, the LWR plants have achieved very high standards of safety and performance. The Generation 3+LWR power plants, next to be installed, may claim to have reached the goal of assuring the safety of the public to a very large extent. This review is based on the historical developments in LWR safety that occurred primarily in USA, however, they are valid for the rest of the Western World. This review can not do justice to the many fine contributions that have been made over the last fifty years to the cause of LWR safety. We apologize if we have not mentioned them. We also apologize for not providing references to many of the fine investigations, which have contributed towards LWR safety earning the conclusions that we describe just above.

Smart support system for diagnosing severe accidents in nuclear power plants

  • Yoo, Kwae Hwan;Back, Ju Hyun;Na, Man Gyun;Hur, Seop;Kim, Hyeonmin
    • Nuclear Engineering and Technology
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    • 제50권4호
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    • pp.562-569
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    • 2018
  • Recently, human errors have very rarely occurred during power generation at nuclear power plants. For this reason, many countries are conducting research on smart support systems of nuclear power plants. Smart support systems can help with operator decisions in severe accident occurrences. In this study, a smart support system was developed by integrating accident prediction functions from previous research and enhancing their prediction capability. Through this system, operators can predict accident scenarios, accident locations, and accident information in advance. In addition, it is possible to decide on the integrity of instruments and predict the life of instruments. The data were obtained using Modular Accident Analysis Program code to simulate severe accident scenarios for the Optimized Power Reactor 1000. The prediction of the accident scenario, accident location, and accident information was conducted using artificial intelligence methods.

사업장 안전보건관리체계 향상을 위한 역학모형 기반의 사고분석기법 활용 방안 연구 (An Application Study of Accident Analysis Method Based on Epidemiological Model to Improve Occupational Safety and Health Management System)

  • 김경환;정기효
    • 대한안전경영과학회지
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    • 제25권2호
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    • pp.9-15
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    • 2023
  • The Severe Disaster Punishment Act had recently been established in order to promote safety and health (OSH) management system for severe accident prevention. OSH management system is primarily designed based on risk assessments; however, companies in industries have been experiencing difficulties in hazard identification and selecting proper measures for risk assessments and accident prevention. This study intended to introduce an accident analysis method based on epidemiological model in finding hazard and preventive measures. The accident analysis method employed in this study was proposed by the U.S. Department of Energy. To demonstrate the effectiveness of the accident analysis method, this study applied it to two accident cases occurred in construction and manufacturing industries. The application process and results of this study can be utilized in improving OSH management system and preventing severe accidents.

연구실 사고 유형분석 및 관리방안에 관한 연구 (Study on Analysis and Management of the Type of Laboratory Accident)

  • 송혜숙;김재중;최재규;천성현;이난희
    • 한국안전학회지
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    • 제33권6호
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    • pp.157-162
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    • 2018
  • There have been 1,039 accidents in laboratory(National Research Safety Headquarters). Accidents in laboratory has increased by 71.5% from 158 cases in 2011 to 271 cases in 2016. Accident analysis results show that there has been no death accident after 2011 when 5 death accidents happened. The results also show that severe injuries have been 23 cases(2%) from 2011 to 2016(7 cases in 2011, 2 cases in 2012, 2013 and 2014, 3 cases in 2015, 7 cases in 2016). Minor injuries shows increasing trend from 151 cases in 2011(92.6%) to 294 cases in 2016(97.6%). Among the causes of accidents in laboratory, piercing injuries by injector were 69 cases(10.4%) for recent 3 years, i.e. 22 cases(12.6%) in 2014, 18 cases(14.2%) in 2015 and 29 cases(16%). Piercing injuries by injector with infection such as viral hepatitis and HIV/AIDS were identified in 10 cases in 2014, 5 cases in 2015, and 10 cases in 2016.Therefore, we would like to contribute to the safety of laboratories by suggesting a guideline for prevention and post management of laboratory accidents.