WorldWideScience

Sample records for major accident hazards

  1. Prevention of Major Accident Hazards (MAHs) in major Hazard Installation (MHI) premises via land use planning (LUP): a review

    Science.gov (United States)

    Khudbiddin, M. Q.; Rashid, Z. A.; Yeong, A. F. M. S.; Alias, A. B.; Irfan, M. F.; Fuad, M.; Hayati, H.

    2018-03-01

    For a number of years, there is a concern about the causes of major hazards, their identification, risk assessment and the process of its management from the global perspective on the activities of the industries due to the protection of the environment, human and property. Though, industries cannot take pleasure in their business by harming the nature of the land, there are a number of measures that need to be put into consideration by the industries. Such measures are in terms of management and safety for the businesses, lives, properties, as well as the environment. The lack of consideration in the selected appropriate criteria can result in major accidental hazards (MAHs). This paper will review the land use planning (LUP) methods used in the past and present to prevent major accident hazards at major hazard installation (MHI).

  2. Hazards to nuclear plants from surface traffic accidents

    International Nuclear Information System (INIS)

    Hornyik, K.

    1975-01-01

    Analytic models have been developed for evaluating hazards to nuclear plants from hazardous-materials accidents in the vicinity of the plant. In particular, these models permit the evaluation of hazards from such accidents occurring on surface traffic routes near the plant. The analysis uses statistical information on accident rates, traffic frequency, and cargo-size distribution along with parameters describing properties of the hazardous cargo, plant design, and atmospheric conditions, to arrive at a conservative estimate of the annual probability of a catastrophic event. Two of the major effects associated with hazardous-materials accidents, explosion and release of toxic vapors, are treated by a common formalism which can be readily applied to any given case by means of a graphic procedure. As an example, for a typical case it is found that railroad shipments of chlorine in 55-ton tank cars constitute a greater hazard to a nearby nuclear plant than equally frequent rail shipments of explosives in amounts of 10 tons. 11 references. (U.S.)

  3. Multi-objective evolutionary emergency response optimization for major accidents

    International Nuclear Information System (INIS)

    Georgiadou, Paraskevi S.; Papazoglou, Ioannis A.; Kiranoudis, Chris T.; Markatos, Nikolaos C.

    2010-01-01

    Emergency response planning in case of a major accident (hazardous material event, nuclear accident) is very important for the protection of the public and workers' safety and health. In this context, several protective actions can be performed, such as, evacuation of an area; protection of the population in buildings; and use of personal protective equipment. The best solution is not unique when multiple criteria are taken into consideration (e.g. health consequences, social disruption, economic cost). This paper presents a methodology for multi-objective optimization of emergency response planning in case of a major accident. The emergency policy with regards to protective actions to be implemented is optimized. An evolutionary algorithm has been used as the optimization tool. Case studies demonstrating the methodology and its application in emergency response decision-making in case of accidents related to hazardous materials installations are presented. However, the methodology with appropriate modification is suitable for supporting decisions in assessing emergency response procedures in other cases (nuclear accidents, transportation of hazardous materials) or for land-use planning issues.

  4. Historical analysis of US pipeline accidents triggered by natural hazards

    Science.gov (United States)

    Girgin, Serkan; Krausmann, Elisabeth

    2015-04-01

    Natural hazards, such as earthquakes, floods, landslides, or lightning, can initiate accidents in oil and gas pipelines with potentially major consequences on the population or the environment due to toxic releases, fires and explosions. Accidents of this type are also referred to as Natech events. Many major accidents highlight the risk associated with natural-hazard impact on pipelines transporting dangerous substances. For instance, in the USA in 1994, flooding of the San Jacinto River caused the rupture of 8 and the undermining of 29 pipelines by the floodwaters. About 5.5 million litres of petroleum and related products were spilled into the river and ignited. As a results, 547 people were injured and significant environmental damage occurred. Post-incident analysis is a valuable tool for better understanding the causes, dynamics and impacts of pipeline Natech accidents in support of future accident prevention and mitigation. Therefore, data on onshore hazardous-liquid pipeline accidents collected by the US Pipeline and Hazardous Materials Safety Administration (PHMSA) was analysed. For this purpose, a database-driven incident data analysis system was developed to aid the rapid review and categorization of PHMSA incident reports. Using an automated data-mining process followed by a peer review of the incident records and supported by natural hazard databases and external information sources, the pipeline Natechs were identified. As a by-product of the data-collection process, the database now includes over 800,000 incidents from all causes in industrial and transportation activities, which are automatically classified in the same way as the PHMSA record. This presentation describes the data collection and reviewing steps conducted during the study, provides information on the developed database and data analysis tools, and reports the findings of a statistical analysis of the identified hazardous liquid pipeline incidents in terms of accident dynamics and

  5. Lessons learned from major accidents relating to ageing of chemical plants

    OpenAIRE

    GYENES ZSUZSANNA; WOOD Maureen

    2016-01-01

    Major industrial accidents that occurred in the past and even recently, such as the Flixborough, UK in 1974, the ConocoPhillips, UK in 2001 and the Chevron, US in 2012 show that ageing is still a disturbing phenomenon present in chemical process industries. Further to these cases, it is estimated that 30 % of the major accidents reported in the eMARS accident database run by the Major Accident Hazards Bureau of the European Commission are connected to at least one ageing phenomenon. It is som...

  6. A review of accidents, prevention and mitigation options related to hazardous gases

    International Nuclear Information System (INIS)

    Fthenakis, V.M.

    1993-05-01

    Statistics on industrial accidents are incomplete due to lack of specific criteria on what constitutes a release or accident. In this country, most major industrial accidents were related to explosions and fires of flammable materials, not to releases of chemicals into the environment. The EPA in a study of 6,928 accidental releases of toxic chemicals revealed that accidents at stationary facilities accounted for 75% of the total number of releases, and transportation accidents for the other 25%. About 7% of all reported accidents (468 cases) resulted in 138 deaths and 4,717 injuries ranging from temporary respiratory problems to critical injuries. In-plant accidents accounted for 65% of the casualties. The most efficient strategy to reduce hazards is to choose technologies which do not require the use of large quantities of hazardous gases. For new technologies this approach can be implemented early in development, before large financial resources and efforts are committed to specific options. Once specific materials and options have been selected, strategies to prevent accident initiating events need to be evaluated and implemented. The next step is to implement safety options which suppress a hazard when an accident initiating event occurs. Releases can be prevented or reduced with fail-safe equipment and valves, adequate warning systems and controls to reduce and interrupt gas leakage. If an accident occurs and safety systems fail to contain a hazardous gas release, then engineering control systems will be relied on to reduce/minimize environmental releases. As a final defensive barrier, the prevention of human exposure is needed if a hazardous gas is released, in spite of previous strategies. Prevention of consequences forms the final defensive barrier. Medical facilities close by that can accommodate victims of the worst accident can reduce the consequences of personnel exposure to hazardous gases

  7. Accident hazard evaluation and control decisions on forested recreation sites

    Science.gov (United States)

    Lee A. Paine

    1971-01-01

    Accident hazard associated with trees on recreation sites is inherently concerned with probabilities. The major factors include the probabilities of mechanical failure and of target impact if failure occurs, the damage potential of the failure, and the target value. Hazard may be evaluated as the product of these factors; i.e., expected loss during the current...

  8. A study of maintenance-related major accident cases in the 21st century

    OpenAIRE

    Okoh, Peter; Haugen, Stein

    2014-01-01

    This paper is based on a review of 183 detailed, major accident investigation and analysis reports related to the handling, processing and storage of hydrocarbons and hazardous chemicals over a decade from 2000 to 2011. The reports cover technical, human and organizational factors. In this paper, the Work and Accident Process (WAP) classification scheme is applied to the accident reports with the intention of investigating to what extent maintenance has been a cause of major accidents and wha...

  9. Risk assessment of major hazards and its application in urban planning: a case study.

    Science.gov (United States)

    Zhou, Yafei; Liu, Mao

    2012-03-01

    With the rapid development of industry in China, the number of establishments that are proposed or under construction is increasing year by year, and many are industries that handle flammable, explosive, toxic, harmful, and dangerous substances. Accidents such as fire, explosion, and toxic diffusion inevitably happen. Accidents resulting from these major hazards in cities cause a large number of casualties and property losses. It is increasingly important to analyze the risk of major hazards in cities realistically and to suitably plan and utilize the surrounding land based on the risk analysis results, thereby reducing the hazards. A theoretical system for risk assessment of major hazards in cities is proposed in this article, and the major hazard risk for the entire city is analyzed quantitatively. Risks of various major accidents are considered together, superposition effect is analyzed, individual risk contours of the entire city are drawn out, and the level of risk in the city is assessed using "as low as reasonably practicable" guidelines. After the entire city's individual risk distribution is obtained, risk zones are divided according to corresponding individual risk value of HSE, and land-use planning suggestions are proposed. Finally, a city in China is used as an example to illustrate the risk assessment process of the city's major hazard and its application in urban land-use planning. The proposed method has a certain theoretical and practical significance in establishing and improving risk analysis of major hazard and urban land-use planning. On the one hand, major urban public risk is avoided; further, the land is utilized in the best possible way in order to obtain the maximum benefit from its use. © 2011 Society for Risk Analysis.

  10. A comparison of the hazard perception ability of accident-involved and accident-free motorcycle riders.

    Science.gov (United States)

    Cheng, Andy S K; Ng, Terry C K; Lee, Hoe C

    2011-07-01

    Hazard perception is the ability to read the road and is closely related to involvement in traffic accidents. It consists of both cognitive and behavioral components. Within the cognitive component, visual attention is an important function of driving whereas driving behavior, which represents the behavioral component, can affect the hazard perception of the driver. Motorcycle riders are the most vulnerable types of road user. The primary purpose of this study was to deepen our understanding of the correlation of different subtypes of visual attention and driving violation behaviors and their effect on hazard perception between accident-free and accident-involved motorcycle riders. Sixty-three accident-free and 46 accident-involved motorcycle riders undertook four neuropsychological tests of attention (Digit Vigilance Test, Color Trails Test-1, Color Trails Test-2, and Symbol Digit Modalities Test), filled out the Chinese Motorcycle Rider Driving Violation (CMRDV) Questionnaire, and viewed a road-user-based hazard situation with an eye-tracking system to record the response latencies to potentially dangerous traffic situations. The results showed that both the divided and selective attention of accident-involved motorcycle riders were significantly inferior to those of accident-free motorcycle riders, and that accident-involved riders exhibited significantly higher driving violation behaviors and took longer to identify hazardous situations compared to their accident-free counterparts. However, the results of the regression analysis showed that aggressive driving violation CMRDV score significantly predicted hazard perception and accident involvement of motorcycle riders. Given that all participants were mature and experienced motorcycle riders, the most plausible explanation for the differences between them is their driving style (influenced by an undesirable driving attitude), rather than skill deficits per se. The present study points to the importance of

  11. Emergency Evacuation of Hazardous Chemical Accidents Based on Diffusion Simulation

    OpenAIRE

    Jiang-Hua Zhang; Hai-Yue Liu; Rui Zhu; Yang Liu

    2017-01-01

    The recent rapid development of information technology, such as sensing technology, communications technology, and database, allows us to use simulation experiments for analyzing serious accidents caused by hazardous chemicals. Due to the toxicity and diffusion of hazardous chemicals, these accidents often lead to not only severe consequences and economic losses, but also traffic jams at the same time. Emergency evacuation after hazardous chemical accidents is an effective means to reduce the...

  12. Major Accidents (Gray Swans) Likelihood Modeling Using Accident Precursors and Approximate Reasoning.

    Science.gov (United States)

    Khakzad, Nima; Khan, Faisal; Amyotte, Paul

    2015-07-01

    Compared to the remarkable progress in risk analysis of normal accidents, the risk analysis of major accidents has not been so well-established, partly due to the complexity of such accidents and partly due to low probabilities involved. The issue of low probabilities normally arises from the scarcity of major accidents' relevant data since such accidents are few and far between. In this work, knowing that major accidents are frequently preceded by accident precursors, a novel precursor-based methodology has been developed for likelihood modeling of major accidents in critical infrastructures based on a unique combination of accident precursor data, information theory, and approximate reasoning. For this purpose, we have introduced an innovative application of information analysis to identify the most informative near accident of a major accident. The observed data of the near accident were then used to establish predictive scenarios to foresee the occurrence of the major accident. We verified the methodology using offshore blowouts in the Gulf of Mexico, and then demonstrated its application to dam breaches in the United Sates. © 2015 Society for Risk Analysis.

  13. Managing major chemical accidents in China: Towards effective risk information

    International Nuclear Information System (INIS)

    He Guizhen; Zhang Lei; Lu Yonglong; Mol, Arthur P.J.

    2011-01-01

    Chemical industries, from their very inception, have been controversial due to the high risks they impose on safety of human beings and the environment. Recent decades have witnessed increasing impacts of the accelerating expansion of chemical industries and chemical accidents have become a major contributor to environmental and health risks in China. This calls for the establishment of an effective chemical risk management system, which requires reliable, accurate and comprehensive data in the first place. However, the current chemical accident-related data system is highly fragmented and incomplete, as different responsible authorities adopt different data collection standards and procedures for different purposes. In building a more comprehensive, integrated and effective information system, this article: (i) reviews and assesses the existing data sources and data management, (ii) analyzes data on 976 recorded major hazardous chemical accidents in China over the last 40 years, and (iii) identifies the improvements required for developing integrated risk management in China.

  14. Emergency Evacuation of Hazardous Chemical Accidents Based on Diffusion Simulation

    Directory of Open Access Journals (Sweden)

    Jiang-Hua Zhang

    2017-01-01

    Full Text Available The recent rapid development of information technology, such as sensing technology, communications technology, and database, allows us to use simulation experiments for analyzing serious accidents caused by hazardous chemicals. Due to the toxicity and diffusion of hazardous chemicals, these accidents often lead to not only severe consequences and economic losses, but also traffic jams at the same time. Emergency evacuation after hazardous chemical accidents is an effective means to reduce the loss of life and property and to smoothly resume the transport network as soon as possible. This paper considers the dynamic changes of the hazardous chemicals’ concentration after their leakage and simulates the diffusion process. Based on the characteristics of emergency evacuation of hazardous chemical accidents, we build a mixed-integer programming model and design a heuristic algorithm using network optimization and diffusion simulation (hereafter NODS. We then verify the validity and feasibility of the algorithm using Jinan, China, as a computational example. In the end, we compare the results from different scenarios to explore the key factors affecting the effectiveness of the evacuation process.

  15. The situation of hazardous chemical accidents in China between 2000 and 2006

    Energy Technology Data Exchange (ETDEWEB)

    Duan Weili [Institute of Safety Science and Engineering, South China University of Technology, Guangzhou 510640, Guangdong (China); Chen Guohua, E-mail: scut.safetycenter@gmail.com [Institute of Safety Science and Engineering, South China University of Technology, Guangzhou 510640, Guangdong (China); Ye Qing; Chen Qingguang [Institute of Safety Science and Engineering, South China University of Technology, Guangzhou 510640, Guangdong (China)

    2011-02-28

    From the aspects of the total quantity of accidents, regional inequality, enterprises scale and environmental pollution accidents, this study makes an analysis of hazardous chemical accidents in China for the period spanning from 2000 to 2006. The following results are obtained: firstly, there were lots of accidents and fatalities in hazardous chemical business, i.e., the number of casualty accidents fluctuated between 200 and 600/year, the number of fatality fluctuated between 220 and 1100/year. Secondly, the accident rate in developed southeast coastal areas, e.g., Guangdong, Zhejiang and Jiangsu, was far higher than that in the northwest regions, e.g., Xizang, Xinjiang, and Qinghai. Thirdly, nearly 80% of dangerous chemical accidents had occurred in small and medium-sized enterprises (SMEs). Finally, various sudden environmental pollution accidents resulted from hazardous chemicals were frequent in recent years, causing a huge damage to human and property. Then, based on the readjustment of economic structure in the last decades, the development status of Occupational Health and Safety (OHS) in SMEs and other factors, the paper explores the main causes, which offers valuable insight into measures that should be taken to reduce hazardous chemical accidents.

  16. The situation of hazardous chemical accidents in China between 2000 and 2006

    International Nuclear Information System (INIS)

    Duan Weili; Chen Guohua; Ye Qing; Chen Qingguang

    2011-01-01

    From the aspects of the total quantity of accidents, regional inequality, enterprises scale and environmental pollution accidents, this study makes an analysis of hazardous chemical accidents in China for the period spanning from 2000 to 2006. The following results are obtained: firstly, there were lots of accidents and fatalities in hazardous chemical business, i.e., the number of casualty accidents fluctuated between 200 and 600/year, the number of fatality fluctuated between 220 and 1100/year. Secondly, the accident rate in developed southeast coastal areas, e.g., Guangdong, Zhejiang and Jiangsu, was far higher than that in the northwest regions, e.g., Xizang, Xinjiang, and Qinghai. Thirdly, nearly 80% of dangerous chemical accidents had occurred in small and medium-sized enterprises (SMEs). Finally, various sudden environmental pollution accidents resulted from hazardous chemicals were frequent in recent years, causing a huge damage to human and property. Then, based on the readjustment of economic structure in the last decades, the development status of Occupational Health and Safety (OHS) in SMEs and other factors, the paper explores the main causes, which offers valuable insight into measures that should be taken to reduce hazardous chemical accidents.

  17. Uranium storage bed accident hazards evaluation

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Shmayda, W.T.

    1989-01-01

    To properly assess hazards and risks associated with the use of uranium beds as tritium storage devices in fusion reactor systems, it is necessary to understand the consequences occurring in the event of an accident. Accidents involving uranium beds are postulated, and the possible results are considered. A research program to more fully and accurately understand those results has been initiated involving the Idaho National Engineering Laboratory and Ontario Hydro. The plan and objectives of that program are presented. 11 refs., 1 tab

  18. Uranium storage bed accident hazards evaluation

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Shmayda, W.T.

    1989-10-01

    To properly assess hazards and risks associated with the use of uranium beds as tritium storage devices in fusion reactor systems, it is necessary to understand the consequences occurring in the event of an accident. Accidents involving uranium beds are postulated, and the possible results are considered. A research program to more fully and accurately understand those results has been initiated involving the Idaho National Engineering Laboratory and Ontario Hydro. The plan and objectives of that program are presented. 11 refs., 1 tab

  19. Relationships between safety and reliability in major hazard situations

    International Nuclear Information System (INIS)

    Farmer, F.R.

    1978-01-01

    Individual risk rates for various activities are presented and discussed. The concept of societal risk is introduced -the chance of hurting many people from one event. Major hazards present a possibility that an ensuing accident could have a very wide range of consequences from the trivial to a catastrophe. The techniques of assessing risks and consequences are being developed; these are closely related to the techniques of ensuring plant and system reliability. (author)

  20. Hazard Identification, Risk Assessment and Risk Control (HIRARC Accidents at Power Plant

    Directory of Open Access Journals (Sweden)

    Ahmad Asmalia Che

    2016-01-01

    Full Text Available Power plant had a reputation of being one of the most hazardous workplace environments. Workers in the power plant face many safety risks due to the nature of the job. Although power plants are safer nowadays since the industry has urged the employer to improve their employees’ safety, the employees still stumble upon many hazards thus accidents at workplace. The aim of the present study is to investigate work related accidents at power plants based on HIRARC (Hazard Identification, Risk Assessment and Risk Control process. The data were collected at two coal-fired power plant located in Malaysia. The finding of the study identified hazards and assess risk relate to accidents occurred at the power plants. The finding of the study suggested the possible control measures and corrective actions to reduce or eliminate the risk that can be used by power plant in preventing accidents from occurred

  1. Hazards of nuclear reactors and other major industrial complexes

    International Nuclear Information System (INIS)

    Farmer, F.R.

    1982-01-01

    Some of the problems of quantified risk analysis of the hazards of nuclear reactors and other major industrial complexes are raised particularly as seen by the proponents and opponents of atomic energy. These are exemplified by discussing the chemical accidents at Flixborough and Canvey Island and the Light Water Reactor Studies. The role of risk analysis in improving knowledge of the systems studies, improving methods of analysis, identifying weaknesses in systems and in improving engineering/maintenance/operation is also stressed. (U.K.)

  2. Global process industry initiatives to reduce major accident hazards

    Energy Technology Data Exchange (ETDEWEB)

    Pitblado, Robin [DNV Energy Houston, TX (United States). SHE Risk Management; Pontes, Jose [DNV Energy Rio de Janeiro, RJ (Brazil). Americas Region; Oliveira, Luiz [DNV Energy Rio de Janeiro, RJ (Brazil)

    2008-07-01

    Since 2000, disasters at Texas City, Toulouse, Antwerp, Buncefield, P-36 and several near total loss events offshore in Norway have highlighted that major accident process safety is still a serious issue. Hopes that Process Safety Management or Safety Case regulations would solve these issues have not proven true. The Baker Panel recommended to BP several actions mainly around leadership, incentives, metrics, safety culture and more effective implementation of PSM systems. In Europe, an approach built around mechanical integrity and safety barriers, especially relating to technical safety systems, is being widely adopted. DNV has carried out a global survey of process industry initiatives, by interview and by literature review, for both upstream and downstream activities, to identify what the industry itself is planning to implement to enhance process safety in the next 5 - 10 years. This shows that an approach combining Baker Panel and EU barrier approaches and some nuclear industry real-time risk management approaches might be the best means to achieve a factor of 3-4 improvement in process safety. (author)

  3. Hazards and accident analyses, an integrated approach, for the Plutonium Facility at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pan, P.Y.; Goen, L.K.; Letellier, B.C.; Sasser, M.K.

    1995-01-01

    This paper describes an integrated approach to perform hazards and accident analyses for the Plutonium Facility at Los Alamos National Laboratory. A comprehensive hazards analysis methodology was developed that extends the scope of the preliminary/process hazard analysis methods described in the AIChE Guidelines for Hazard Evaluations. Results fro the semi-quantitative approach constitute a full spectrum of hazards. For each accident scenario identified, there is a binning assigned for the event likelihood and consequence severity. In addition, each accident scenario is analyzed for four possible sectors (workers, on-site personnel, public, and environment). A screening process was developed to link the hazard analysis to the accident analysis. Specifically the 840 accident scenarios were screened down to about 15 accident scenarios for a more through deterministic analysis to define the operational safety envelope. The mechanics of the screening process in the selection of final scenarios for each representative accident category, i.e., fire, explosion, criticality, and spill, is described

  4. Written instructions for the transport of hazardous materials: Accident management instruction sheets

    International Nuclear Information System (INIS)

    Ridder, K.

    1988-01-01

    In spite of the regulations and the safety provisions taken, accidents are not entirely avoidable in the transport of hazardous materials. For managing an accident and preventing further hazards after release of dangerous substances, the vehicle drivers must carry with them the accident management instruction sheets, which give instructions on immediate counter measures to be taken by the driver, and on information to be given to the police and the fire brigades. The article in hand discusses the purpose, the contents, and practice-based improvement of this collection of instruction sheets. Particular reference is given to the newly revised version of June 15, 1988 (Verkehrsblatt 1/88) of the 'Directives for setting up accident management instruction sheets - written instructions - for road transport of hazardous materials', as issued by the Federal Ministry of Transport. (orig./HP) [de

  5. Transportation of hazardous materials in Iran: A strategic approach for decreasing accidents

    Directory of Open Access Journals (Sweden)

    S. Ghazinoory

    2008-06-01

    Full Text Available .“Hazardous materials” refer to those substances that seriously endanger human lives and/or the environment. The transportation of these materials will be inevitable in the increasingly industrialized economy of Iran. Nonetheless, numerous deadly accidents caused by the movement of these materials necessitate the design and implementation of preventive plans on several levels. This article looks into the present condition of transportation of hazardous materials in Iran and the resulting accidents. Optimal condition for the general transportation system of hazardous materials is delineated with due focus on transportation risk as the main parameter. Strategies for reaching the optimal condition are laid out and the impacts of these strategies on the reduction of accidents are analyzed.

  6. The risk of a major nuclear accident: calculation and perception of probabilities

    International Nuclear Information System (INIS)

    Leveque, Francois

    2013-07-01

    The accident at Fukushima Daiichi, Japan, occurred on 11 March 2011. This nuclear disaster, the third on such a scale, left a lasting mark in the minds of hundreds of millions of people. Much as Three Mile Island or Chernobyl, yet another place will be permanently associated with a nuclear power plant which went out of control. Fukushima Daiichi revived the issue of the hazards of civil nuclear power, stirring up all the associated passion and emotion. The whole of this paper is devoted to the risk of a major nuclear accident. By this we mean a failure initiating core meltdown, a situation in which the fuel rods melt and mix with the metal in their cladding. Such accidents are classified as at least level 5 on the International Nuclear Event Scale. The Three Mile Island accident, which occurred in 1979 in the United States, reached this level of severity. The explosion of reactor 4 at the Chernobyl plant in Ukraine in 1986 and the recent accident in Japan were classified as class 7, the highest grade on this logarithmic scale. The main difference between the top two levels and level 5 relates to a significant or major release of radioactive material to the environment. In the event of a level-5 accident, damage is restricted to the inside of the plant, whereas, in the case of level-7 accidents, huge areas of land, above or below the surface, and/or sea may be contaminated. Before the meltdown of reactors 1, 2 and 3 at Fukushima Daiichi, eight major accidents affecting nuclear power plants had occurred worldwide. This is a high figure compared with the one calculated by the experts. Observations in the field do not appear to fit the results of the probabilistic models of nuclear accidents produced since the 1970's. Oddly enough the number of major accidents is closer to the risk as perceived by the general public. In general we tend to overestimate any risk relating to rare, fearsome accidents. What are we to make of this divergence? How are we to reconcile

  7. Onshore preparedness for hazardous chemical marine vessel accidents: A case study

    Directory of Open Access Journals (Sweden)

    Faisel T. Illiyas

    2016-09-01

    Full Text Available Hazardous and noxious substances (HNS are widely transported in marine vessels to reach every part of the world. Bulk transportation of hazardous chemicals is carried out in tank container–carrying cargo ships or in designed vessels. Ensuring the safety of HNS containers during maritime transportation is critically important as the accidental release of any substance may be lethal to the on-board crew and marine environment. A general assumption in maritime accidents in open ocean is that it will not create any danger to the coastal population. The case study discussed in this article throws light on the dangers latent in maritime HNS accidents. An accident involving an HNS-carrying marine vessel in the Arabian Sea near the coast of Yemen became a safety issue to the coastal people of Kasargod District of Kerala, India. The ship carried more than 4000 containers, which were lost to the sea in the accident. Six HNS tank containers were carried by the waves and shored at the populated coast of Kasargod, more than 650 nautical miles east from the accident spot. The unanticipated sighting of tank containers in the coast and the response of the administration to the incident, the hurdles faced by the district administration in handling the case, the need for engaging national agencies and lessons learned from the incident are discussed in the article. This case study has proven that accidents in the open ocean have the potential to put the coastal areas at risk if the on-board cargo contains hazardous chemicals. Littoral nations, especially those close to the international waterlines, must include hazardous chemical spills to their oil spill contingency plans.

  8. Modeling emergency evacuation for major hazard industrial sites

    International Nuclear Information System (INIS)

    Georgiadou, Paraskevi S.; Papazoglou, Ioannis A.; Kiranoudis, Chris T.; Markatos, Nikolaos C.

    2007-01-01

    A model providing the temporal and spatial distribution of the population under evacuation around a major hazard facility is developed. A discrete state stochastic Markov process simulates the movement of the evacuees. The area around the hazardous facility is divided into nodes connected among themselves with links representing the road system of the area. Transition from node-to-node is simulated as a random process where the probability of transition depends on the dynamically changed states of the destination and origin nodes and on the link between them. Solution of the Markov process provides the expected distribution of the evacuees in the nodes of the area as a function of time. A Monte Carlo solution of the model provides in addition a sample of actual trajectories of the evacuees. This information coupled with an accident analysis which provides the spatial and temporal distribution of the extreme phenomenon following an accident, determines a sample of the actual doses received by the evacuees. Both the average dose and the actual distribution of doses are then used as measures in evaluating alternative emergency response strategies. It is shown that in some cases the estimation of the health consequences by the average dose might be either too conservative or too non-conservative relative to the one corresponding to the distribution of the received dose and hence not a suitable measure to evaluate alternative evacuation strategies

  9. Advance of Hazardous Operation Robot and its Application in Special Equipment Accident Rescue

    Science.gov (United States)

    Zeng, Qin-Da; Zhou, Wei; Zheng, Geng-Feng

    A survey of hazardous operation robot is given out in this article. Firstly, the latest researches such as nuclear industry robot, fire-fighting robot and explosive-handling robot are shown. Secondly, existing key technologies and their shortcomings are summarized, including moving mechanism, control system, perceptive technology and power technology. Thirdly, the trend of hazardous operation robot is predicted according to current situation. Finally, characteristics and hazards of special equipment accident, as well as feasibility of hazardous operation robot in the area of special equipment accident rescue are analyzed.

  10. Analysis of National Major Work Safety Accidents in China, 2003-2012.

    Science.gov (United States)

    Ye, Yunfeng; Zhang, Siheng; Rao, Jiaming; Wang, Haiqing; Li, Yang; Wang, Shengyong; Dong, Xiaomei

    2016-01-01

    This study provides a national profile of major work safety accidents in China, which cause more than 10 fatalities per accident, intended to provide scientific basis for prevention measures and strategies to reduce major work safety accidents and deaths. Data from 2003-2012 Census of major work safety accidents were collected from State Administration of Work Safety System (SAWS). Published literature and statistical yearbook were also included to implement information. We analyzed the frequency of accidents and deaths, trend, geographic distribution and injury types. Additionally, we discussed the severity and urgency of emergency rescue by types of accidents. A total of 877 major work safety accidents were reported, resulting in 16,795 deaths and 9,183 injuries. The numbers of accidents and deaths, mortality rate and incidence of major accidents have declined in recent years. The mortality rate and incidence was 0.71 and 1.20 per 10(6) populations in 2012, respectively. Transportation and mining contributed to the highest number of major accidents and deaths. Major aviation and railway accidents caused more casualties per incident, while collapse, machinery, electrical shock accidents and tailing dam accidents were the most severe situation that resulted in bigger proportion of death. Ten years' major work safety accident data indicate that the frequency of accidents and number of eaths was declined and several safety concerns persist in some segments.

  11. Major workplace related accidents in Singapore: A major trauma centre's experience.

    Science.gov (United States)

    Ng, Zhi Xu; Teo, Li Tserng; Go, Karen T S; Yeo, Yen Teng; Chiu, Ming Terk

    2010-12-01

    Major workplace related accidents pose a significant healthcare resource challenge in Singapore. Our study looks at the epidemiology of patients who were admitted for workplace related accidents, in a single institution, with an Injury Severity Score of >9. There were 196 cases of major workplace related accidents admitted between January 2006 and December 2007. The median age of patients admitted was 37 years with a large percentage being males (95.4%) and non-residents (57.1%). The most common ethnic group was Chinese (53.1%) followed by Indians (23.5%). The most common mechanism of injury was fall from height (66.3%) followed by injuries as a result of falling objects at work (21.9%). The percentage of patients who required surgical intervention was 69.9%. Patients admitted for major workplace related accidents had a median length of stay of 5 days in the hospital, a median length of 24 days of medical leave (ML), certifying them unfit for duty and the average cost of stay for each patient was S$11,000. We have a better understanding of the epidemiology and socio-economic impact of workplace related accidents through this study. Workplace related accidents result in significant number of man-days lost from work and monetary cost to employers, medical insurance and the hospital. With an improved understanding, we propose methods to prevent and reduce such accidents in future. A direct consequence of which will be the possible reduction of hospitalisation costs and better allocation of healthcare resources in the future.

  12. Major hazards onshore and offshore

    International Nuclear Information System (INIS)

    1992-01-01

    This symposium continues the tradition of bringing together papers on a topic of current interest and importance in terms of process safety - in this case, Major Hazards Onshore and Offshore. Lord Cullen in his report on the Piper Alpha disaster has, in effect, suggested that the experience gained in the control of major hazards onshore during the 1980s should be applied to improve safety offshore during the 1990s. This major three-day symposium reviews what has been learned so far with regard to major hazards and considers its present and future applications both onshore and offshore. The topics covered in the programme are wide ranging and deal with all aspects of legislation, the application of regulations, techniques for evaluating hazards and prescribing safety measures in design, construction and operation, the importance of the human factors, and recent technical developments in protective measures, relief venting and predicting the consequences of fires and explosions. (author)

  13. Learning lessons from Natech accidents - the eNATECH accident database

    Science.gov (United States)

    Krausmann, Elisabeth; Girgin, Serkan

    2016-04-01

    When natural hazards impact industrial facilities that house or process hazardous materials, fires, explosions and toxic releases can occur. This type of accident is commonly referred to as Natech accident. In order to prevent the recurrence of accidents or to better mitigate their consequences, lessons-learned type studies using available accident data are usually carried out. Through post-accident analysis, conclusions can be drawn on the most common damage and failure modes and hazmat release paths, particularly vulnerable storage and process equipment, and the hazardous materials most commonly involved in these types of accidents. These analyses also lend themselves to identifying technical and organisational risk-reduction measures that require improvement or are missing. Industrial accident databases are commonly used for retrieving sets of Natech accident case histories for further analysis. These databases contain accident data from the open literature, government authorities or in-company sources. The quality of reported information is not uniform and exhibits different levels of detail and accuracy. This is due to the difficulty of finding qualified information sources, especially in situations where accident reporting by the industry or by authorities is not compulsory, e.g. when spill quantities are below the reporting threshold. Data collection has then to rely on voluntary record keeping often by non-experts. The level of detail is particularly non-uniform for Natech accident data depending on whether the consequences of the Natech event were major or minor, and whether comprehensive information was available for reporting. In addition to the reporting bias towards high-consequence events, industrial accident databases frequently lack information on the severity of the triggering natural hazard, as well as on failure modes that led to the hazmat release. This makes it difficult to reconstruct the dynamics of the accident and renders the development of

  14. Analysis of National Major Work Safety Accidents in China, 2003–2012

    Science.gov (United States)

    YE, Yunfeng; ZHANG, Siheng; RAO, Jiaming; WANG, Haiqing; LI, Yang; WANG, Shengyong; DONG, Xiaomei

    2016-01-01

    Background: This study provides a national profile of major work safety accidents in China, which cause more than 10 fatalities per accident, intended to provide scientific basis for prevention measures and strategies to reduce major work safety accidents and deaths. Methods: Data from 2003–2012 Census of major work safety accidents were collected from State Administration of Work Safety System (SAWS). Published literature and statistical yearbook were also included to implement information. We analyzed the frequency of accidents and deaths, trend, geographic distribution and injury types. Additionally, we discussed the severity and urgency of emergency rescue by types of accidents. Results: A total of 877 major work safety accidents were reported, resulting in 16,795 deaths and 9,183 injuries. The numbers of accidents and deaths, mortality rate and incidence of major accidents have declined in recent years. The mortality rate and incidence was 0.71 and 1.20 per 106 populations in 2012, respectively. Transportation and mining contributed to the highest number of major accidents and deaths. Major aviation and railway accidents caused more casualties per incident, while collapse, machinery, electrical shock accidents and tailing dam accidents were the most severe situation that resulted in bigger proportion of death. Conclusion: Ten years’ major work safety accident data indicate that the frequency of accidents and number of eaths was declined and several safety concerns persist in some segments. PMID:27057515

  15. Analysis of root causes of major hazard precursors (hydrocarbon leaks) in the Norwegian offshore petroleum industry

    International Nuclear Information System (INIS)

    Vinnem, Jan Erik; Hestad, Jon Andreas; Kvaloy, Jan Terje; Skogdalen, Jon Espen

    2010-01-01

    The offshore petroleum industry in Norway reports major hazard precursors to the authorities, and data are available for the period 1996 through 2009. Barrier data have been reported since 2002, as have data from an extensive questionnaire survey covering working environment, organizational culture and perceived risk among all employees on offshore installations. Several attempts have been made to analyse different data sources in order to discover relations that may cast some light on possible root causes of major hazard precursors. These previous attempts were inconclusive. The study presented in this paper is the most extensive study performed so far. The data were analysed using linear regression. The conclusion is that there are significant correlations between number of leaks and safety climate indicators. The discussion points to possible root causes of major accidents.

  16. Barriers to learning from incidents and accidents

    NARCIS (Netherlands)

    Dechy, N.; Dien, Y.; Drupsteen, L.; Felicio, A.; Cunha, C.; Roed-Larsen, S.; Marsden, E.; Tulonen, T.; Stoop, J.; Strucic, M.; Vetere Arellano, A.L.; Vorm, J.K.J. van der; Benner, L.

    2015-01-01

    This document provides an overview of knowledge concerning barriers to learning from incidents and accidents. It focuses on learning from accident investigations, public inquiries and operational experience feedback, in industrial sectors that are exposed to major accident hazards. The document

  17. A calculational methodology for comparing the accident, occupational, and waste-disposal hazards of fusion reactor designs

    International Nuclear Information System (INIS)

    Fetter, S.

    1985-01-01

    A methodology has been developed for calculating indices of three classes of radiological hazards: reactor accidents, occupational exposures, and waste-disposal hazards. Radionuclide inventories, biological hazard potentials (BHP), and various dose-related indices are calculated. In the case of reactor accidents, the critical, 50-year and chronic dose are computed, as well as the number of early deaths and illnesses and late cancer fatalities. For occupational exposure, the contact dose rate is calculated for several times after reactor shutdown. In the case of waste-disposal hazards, the intruder dose and the intruder hazard potential (IHP) are calculated. Sample calculations for the MARS reactor design show the usefulness of the methodology in exploring design improvements

  18. Process hazards analysis (PrHA) program, bridging accident analyses and operational safety

    International Nuclear Information System (INIS)

    Richardson, J.A.; McKernan, S.A.; Vigil, M.J.

    2003-01-01

    Recently the Final Safety Analysis Report (FSAR) for the Plutonium Facility at Los Alamos National Laboratory, Technical Area 55 (TA-55) was revised and submitted to the US. Department of Energy (DOE). As a part of this effort, over seventy Process Hazards Analyses (PrHAs) were written and/or revised over the six years prior to the FSAR revision. TA-55 is a research, development, and production nuclear facility that primarily supports US. defense and space programs. Nuclear fuels and material research; material recovery, refining and analyses; and the casting, machining and fabrication of plutonium components are some of the activities conducted at TA-35. These operations involve a wide variety of industrial, chemical and nuclear hazards. Operational personnel along with safety analysts work as a team to prepare the PrHA. PrHAs describe the process; identi fy the hazards; and analyze hazards including determining hazard scenarios, their likelihood, and consequences. In addition, the interaction of the process to facility systems, structures and operational specific protective features are part of the PrHA. This information is rolled-up to determine bounding accidents and mitigating systems and structures. Further detailed accident analysis is performed for the bounding accidents and included in the FSAR. The FSAR is part of the Documented Safety Analysis (DSA) that defines the safety envelope for all facility operations in order to protect the worker, the public, and the environment. The DSA is in compliance with the US. Code of Federal Regulations, 10 CFR 830, Nuclear Safety Management and is approved by DOE. The DSA sets forth the bounding conditions necessary for the safe operation for the facility and is essentially a 'license to operate.' Safely of day-to-day operations is based on Hazard Control Plans (HCPs). Hazards are initially identified in the PrI-IA for the specific operation and act as input to the HCP. Specific protective features important to worker

  19. Study on integrated approach of Nuclear Accident Hazard Predicting, Warning, and Optimized Controlling System based on GIS

    International Nuclear Information System (INIS)

    Tang Lijuan; Huang Shunxiang; Wang Xinming

    2012-01-01

    The issue of nuclear safety becomes the attention focus of international society after the nuclear accident happened in Fukushima. Aiming at the requirements of the prevention and controlling of Nuclear Accident establishment of Nuclear Accident Hazard Predicting, Warning and optimized Controlling System (NAPWS) is a imperative project that our country and army are desiderating, which includes multiple fields of subject as nuclear physics, atmospheric science, security science, computer science and geographical information technology, etc. Multiplatform, multi-system and multi-mode are integrated effectively based on GIS, accordingly the Predicting, Warning, and Optimized Controlling technology System of Nuclear Accident Hazard is established. (authors)

  20. Evaluation of major polluting accidents in China-Results and perspectives

    International Nuclear Information System (INIS)

    Hou Yu; Zhang Tianzhu

    2009-01-01

    Lessons learnt from accidents are essential sources for updating state-of-the-art requirements in pollution accident prevention. To improve this input in the People's Republic of China in a systematic way, a database for collecting and evaluating major pollution accidents is being established. This is being done in co-operation with Chinese Society for Environment Sciences and other national Institutions. At the time of writing over 80 major events from 2002-2006 have been collected. In this paper, a summary evaluation on the major polluting events in China from 2002 to 2006 is presented and some basic lessons drawn shown. There is no a systematic pollution accident notification system currently in China. The results from root cause analysis underline the importance of emergency measures, maintenance, human factor issues and the role of safety organization. Chronic pollution, especially water pollution and air pollution should be paid the same attention as the sudden pollution. It is important to keep in mind that collecting information from major accidents represents a small percentage of the actual number of events taking place.

  1. Analysis on tank truck accidents involved in road hazardous materials transportation in china.

    Science.gov (United States)

    Shen, Xiaoyan; Yan, Ying; Li, Xiaonan; Xie, Chenjiang; Wang, Lihua

    2014-01-01

    Due to the sheer size and capacity of the tanker and the properties of cargo transported in the tank, hazmat tanker accidents are more disastrous than other types of vehicle accidents. The aim of this study was to provide a current survey on the situation of accidents involving tankers transporting hazardous materials in China. Detailed descriptions of 708 tanker accidents associated with hazmat transportation in China from 2004 to 2011 were analyzed to identify causes, location, types, time of occurrence, hazard class for materials involved, consequences, and the corresponding probability. Hazmat tanker accidents mainly occurred in eastern (38.1%) and southwest China (12.3%). The most frequent hazmat tanker accidents involved classes 2, 3, and 8. The predominant accident types were rollover (29.10%), run-off-the-road (16.67%), and rear-end collisions (13.28%), with a high likelihood of a large spill occurring. About 55.93% of the accidents occurred on freeways and class 1 roads, with the spill percentage reaching 75.00% and the proportion of spills that occurred in the total accidents amounting to 77.82%, of which 61.72% are considered large spills. The month with the highest accident probability was July (12.29%), and most crashes occurred during the early morning (4:00-6:00 a.m.) and midday (10:00 a.m.-12:00 p.m.) hours, 19.63% versus 16.10%. Human-related errors (73.8%) and vehicle-related defects (19.6%) were the primary reasons for hazmat tanker crashes. The most common outcomes of a hazmat tanker accident was a spill without further events (55.51%), followed by a release with fire (7.77%), and release with an explosion (2.54%). The safety situation of China's hazmat tanker transportation is grim. Such accidents not only have high spill percentages and consistently large spills but they can also cause serious consequences, such as fires and explosions. Improving the training of drivers and the quality of vehicles, deploying roll stability aids, enhancing

  2. Predicting Consequences of Technological Disasters from Natural Hazard Events: Challenges and Opportunities Associated with Industrial Accident Data Sources

    Science.gov (United States)

    Wood, M.

    2009-04-01

    The increased focus on the possibility of technological accidents caused by natural events (Natech) is foreseen to continue for years to come. In this case, experts in prevention, mitigation and preparation activities associated with natural events will increasingly need to borrow data and expertise traditionally associated with the technological fields to carry out the work. An important question is how useful is the data for understanding consequences from such natech events. Data and case studies provided on major industrial accidents tend to focus on lessons learned for re-engineering the process. While consequence data are reported at least nominally in most reports, their precision, quality and completeness is often lacking. Consequences that are often or sometimes available but not provided can include severity and type of injuries, distance of victims from the source, exposure measurements, volume of the release, population in potentially affected zones, and weather conditions. Yet these are precisely the type of data that will aid natural hazard experts in land-use planning and emergency response activities when a Natech event may be foreseen. This work discusses the results of a study of consequence data from accidents involving toxic releases reported in the EU's MARS accident database. The study analysed the precision, quality and completeness of three categories of consequence data reported: the description of health effects, consequence assessment and chemical risk assessment factors, and emergency response information. This work reports on the findings from this study and discusses how natural hazards experts might interact with industrial accident experts to promote more consistent and accurate reporting of the data that will be useful in consequence-based activities.

  3. Evaluation of methods to compare consequences from hazardous materials transportation accidents

    International Nuclear Information System (INIS)

    Rhoads, R.E.; Franklin, A.L.; Lavender, J.C.

    1986-10-01

    This report presents the results of a project to develop a framework for making meaningful comparisons of the consequences from transportation accidents involving hazardous materials. The project was conducted in two phases. In Phase I, methods that could potentially be used to develop the consequence comparisons for hazardous material transportation accidents were identified and reviewed. Potential improvements were identified and an evaluation of the improved methods was performed. Based on this evaluation, several methods were selected for detailed evaluation in Phase II of the project. The methods selected were location-dependent scenarios, figure of merit and risk assessment. This evaluation included application of the methods to a sample problem which compares the consequences of four representative hazardous materials - chlorine, propane, spent nuclear fuel and class A explosives. These materials were selected because they represented a broad class of hazardous material properties and consequence mechanisms. The sample case aplication relied extensively on consequence calculations performed in previous transportation risk assessment studies. A consultant was employed to assist in developing consequence models for explosives. The results of the detailed evaluation of the three consequence comparison methods indicates that methods are available to perform technically defensible comparisons of the consequences from a wide variety of hazardous materials. Location-dependent scenario and risk assessment methods are available now and the figure of merit method could be developed with additional effort. All of the methods require substantial effort to implement. Methods that would require substantially less effort were identified in the preliminary evaluation, but questions of technical accuracy preclude their application on a scale. These methods may have application to specific cases, however

  4. Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2011-07-01

    Consideration of severe accidents in nuclear power plants is an essential component of the defence in depth approach in nuclear safety. Severe accidents have very low probabilities of occurring, but may have significant consequences resulting from the degradation of nuclear fuel. The generation of hydrogen and the risk of hydrogen combustion, as well as other phenomena leading to overpressurization of the reactor containment in case of severe accidents, represent complex safety issues in relation to accident management. The combustion of hydrogen, produced primarily as a result of heated zirconium metal reacting with steam, can create short term overpressure or detonation forces that may exceed the strength of the containment structure. An understanding of these phenomena is crucial for planning and implementing effective accident management measures. Analysis of all the issues relating to hydrogen risk is an important step for any measure that is aimed at the prevention or mitigation of hydrogen combustion in reactor containments. The main objective of this publication is to contribute to the implementation of IAEA Safety Standards, in particular, two IAEA Safety Requirements: Safety of Nuclear Power Plants: Design and Safety of Nuclear Power Plants: Operation. These Requirements publications discuss computational analysis of severe accidents and accident management programmes in nuclear power plants. Specifically with regard to the risk posed by hydrogen in nuclear power reactors, computational analysis of severe accidents considers hydrogen sources, hydrogen distribution, hydrogen combustion and control and mitigation measures for hydrogen, while accident management programmes are aimed at mitigating hydrogen hazards in reactor containments.

  5. Hazard Prevention Regarding Occupational Accidents Involving Blue-Collar Foreign Workers: A Perspective of Taiwanese Manpower Agencies.

    Science.gov (United States)

    Chang, Huan-Cheng; Wang, Mei-Chin; Liao, Hung-Chang; Cheng, Shu-Fang; Wang, Ya-Huei

    2016-07-13

    Since 1989, blue-collar foreign workers have been permitted to work in Taiwanese industries. Most blue-collar foreign workers apply for jobs in Taiwan through blue-collar foreign workers' agencies. Because blue-collar foreign workers are not familiar with the language and culture in Taiwan, in occupational accident education and hazard prevention, the agencies play an important role in the coordination and translation between employees and blue-collar foreign workers. The purpose of this study is to establish the agencies' role in the occupational accidents education and hazard prevention for blue-collar foreign workers in Taiwan. This study uses a qualitative method-grounded theory-to collect, code, and analyze the data in order to understand the agencies' role in occupational accident education and hazard prevention for blue-collar foreign workers in Taiwan. The results show that the duty of agencies in occupational accident education and hazard prevention includes selecting appropriate blue-collar foreign workers, communicating between employees and blue-collar foreign workers, collecting occupational safety and health information, assisting in the training of occupational safety and health, and helping blue-collar foreign workers adapt to their lives in Taiwan. Finally, this study suggests seven important points and discusses the implementation process necessary to improve governmental policies. The government and employees should pay attention to the education/training of occupational safety and health for blue-collar foreign workers to eliminate unsafe behavior in order to protect the lives of blue-collar foreign workers.

  6. Hazard Prevention Regarding Occupational Accidents Involving Blue-Collar Foreign Workers: A Perspective of Taiwanese Manpower Agencies

    Directory of Open Access Journals (Sweden)

    Huan-Cheng Chang

    2016-07-01

    Full Text Available Since 1989, blue-collar foreign workers have been permitted to work in Taiwanese industries. Most blue-collar foreign workers apply for jobs in Taiwan through blue-collar foreign workers’ agencies. Because blue-collar foreign workers are not familiar with the language and culture in Taiwan, in occupational accident education and hazard prevention, the agencies play an important role in the coordination and translation between employees and blue-collar foreign workers. The purpose of this study is to establish the agencies’ role in the occupational accidents education and hazard prevention for blue-collar foreign workers in Taiwan. This study uses a qualitative method—grounded theory—to collect, code, and analyze the data in order to understand the agencies’ role in occupational accident education and hazard prevention for blue-collar foreign workers in Taiwan. The results show that the duty of agencies in occupational accident education and hazard prevention includes selecting appropriate blue-collar foreign workers, communicating between employees and blue-collar foreign workers, collecting occupational safety and health information, assisting in the training of occupational safety and health, and helping blue-collar foreign workers adapt to their lives in Taiwan. Finally, this study suggests seven important points and discusses the implementation process necessary to improve governmental policies. The government and employees should pay attention to the education/training of occupational safety and health for blue-collar foreign workers to eliminate unsafe behavior in order to protect the lives of blue-collar foreign workers.

  7. Global risk of radioactive fallout after major nuclear reactor accidents

    International Nuclear Information System (INIS)

    Lelieveld, J.; Kunkel, D.; Lawrence, M.G.

    2012-01-01

    Major reactor accidents of nuclear power plants are rare, yet the consequences are catastrophic. But what is meant by ''rare''? And what can be learned from the Chernobyl and Fukushima incidents? Here we assess the cumulative, global risk of exposure to radioactivity due to atmospheric dispersion of gases and particles following severe nuclear accidents (the most severe ones on the International Nuclear Event Scale, INES 7), using particulate "1"3"7Cs and gaseous "1"3"1I as proxies for the fallout. Our results indicate that previously the occurrence of INES 7 major accidents and the risks of radioactive contamination have been underestimated. Using a global model of the atmosphere we compute that on average, in the event of a major reactor accident of any nuclear power plant worldwide, more than 90% of emitted "1"3"7Cs would be transported beyond 50 km and about 50% beyond 1000 km distance before being deposited. This corroborates that such accidents have large-scale and trans-boundary impacts. Although the emission strengths and atmospheric removal processes of "1"3"7Cs and "1"3"1I are quite different, the radioactive contamination patterns over land and the human exposure due to deposition are computed to be similar. High human exposure risks occur around reactors in densely populated regions, notably in West Europe and South Asia, where a major reactor accident can subject around 30 million people to radioactive contamination. The recent decision by Germany to phase out its nuclear reactors will reduce the national risk, though a large risk will still remain from the reactors in neighbouring countries.

  8. Biomass accident investigations – missed opportunities for learning and accident prevention

    DEFF Research Database (Denmark)

    Hedlund, Frank Huess

    2017-01-01

    The past decade has seen a major increase in the production of energy from biomass. The growth has been mirrored in an increase of serious biomass related accidents involving fires, gas explosions, combustible dust explosions and the release of toxic gasses. There are indications that the number...... of bioenergy related accidents is growing faster than the energy production. This paper argues that biomass accidents, if properly investigated and lessons shared widely, provide ample opportunities for improving general hazard awareness and safety performance of the biomass industry. The paper examines...... selected serious accidents involving biogas and wood pellets in Denmark and argues that such opportunities for learning were missed because accident investigations were superficial, follow-up incomplete and information sharing absent. In one particularly distressing case, a facility saw a repeat accident...

  9. Industrial accidents triggered by lightning.

    Science.gov (United States)

    Renni, Elisabetta; Krausmann, Elisabeth; Cozzani, Valerio

    2010-12-15

    Natural disasters can cause major accidents in chemical facilities where they can lead to the release of hazardous materials which in turn can result in fires, explosions or toxic dispersion. Lightning strikes are the most frequent cause of major accidents triggered by natural events. In order to contribute towards the development of a quantitative approach for assessing lightning risk at industrial facilities, lightning-triggered accident case histories were retrieved from the major industrial accident databases and analysed to extract information on types of vulnerable equipment, failure dynamics and damage states, as well as on the final consequences of the event. The most vulnerable category of equipment is storage tanks. Lightning damage is incurred by immediate ignition, electrical and electronic systems failure or structural damage with subsequent release. Toxic releases and tank fires tend to be the most common scenarios associated with lightning strikes. Oil, diesel and gasoline are the substances most frequently released during lightning-triggered Natech accidents. Copyright © 2010 Elsevier B.V. All rights reserved.

  10. Protective Behaviour of Citizens to Transport Accidents Involving Hazardous Materials: A Discrete Choice Experiment Applied to Populated Areas nearby Waterways.

    Directory of Open Access Journals (Sweden)

    Esther W de Bekker-Grob

    Full Text Available To improve the information for and preparation of citizens at risk to hazardous material transport accidents, a first important step is to determine how different characteristics of hazardous material transport accidents will influence citizens' protective behaviour. However, quantitative studies investigating citizens' protective behaviour in case of hazardous material transport accidents are scarce.A discrete choice experiment was conducted among subjects (19-64 years living in the direct vicinity of a large waterway. Scenarios were described by three transport accident characteristics: odour perception, smoke/vapour perception, and the proportion of people in the environment that were leaving at their own discretion. Subjects were asked to consider each scenario as realistic and to choose the alternative that was most appealing to them: staying, seeking shelter, or escaping. A panel error component model was used to quantify how different transport accident characteristics influenced subjects' protective behaviour.The response was 44% (881/1,994. The predicted probability that a subject would stay ranged from 1% in case of a severe looking accident till 62% in case of a mild looking accident. All three transport accident characteristics proved to influence protective behaviour. Particularly a perception of strong ammonia or mercaptan odours and visible smoke/vapour close to citizens had the strongest positive influence on escaping. In general, 'escaping' was more preferred than 'seeking shelter', although stated preference heterogeneity among subjects for these protective behaviour options was substantial. Males were less willing to seek shelter than females, whereas elderly people were more willing to escape than younger people.Various characteristics of transport accident involving hazardous materials influence subjects' protective behaviour. The preference heterogeneity shows that information needs to be targeted differently depending on

  11. Current status and issues of external event PSA for extreme natural hazards after Fukushima accident

    International Nuclear Information System (INIS)

    Choi, In-Kil; Hahm, Daegi; Kim, Min Kyu

    2014-01-01

    Extreme external events is emerged as significant risk contributor to the nuclear power plants after Fukushima Daiichi accident due to the catastrophic earthquake followed by great tsunami greater than a design basis. This accident shows that the extreme external events have the potential to simultaneously affect redundant and diverse safety systems and thereby induce common cause failure or common cause initiators. The probabilistic risk assessment methodology has been used for the risk assessment and safety improvement against the extreme natural hazards. The earthquake and tsunami hazard is an important issue for the nuclear industry in Korea. In this paper, the role and application of probabilistic safety assessment for the post Fukushima action will be introduced. For the evaluation of the extreme natural hazard, probabilistic seismic and tsunami hazard analysis is being performed for the safety enhancement. The research activity on the external event PSA and its interim results will be introduced with the issues to be solved in the future for the reliability enhancement of the risk analysis results. (authors)

  12. The risk of major nuclear accident: calculation and perception of probabilities

    International Nuclear Information System (INIS)

    Leveque, Francois

    2013-01-01

    Whereas before the Fukushima accident, already eight major accidents occurred in nuclear power plants, a number which is higher than that expected by experts and rather close to that corresponding of people perception of risk, the author discusses how to understand these differences and reconcile observations, objective probability of accidents and subjective assessment of risks, why experts have been over-optimistic, whether public opinion is irrational regarding nuclear risk, and how to measure risk and its perception. Thus, he addresses and discusses the following issues: risk calculation (cost, calculated frequency of major accident, bias between the number of observed accidents and model predictions), perceived probabilities and aversion for disasters (perception biases of probability, perception biases unfavourable to nuclear), the Bayes contribution and its application (Bayes-Laplace law, statistics, choice of an a priori probability, prediction of the next event, probability of a core fusion tomorrow)

  13. Policy issues on the control of major accident hazards and the new Seveso II directive

    International Nuclear Information System (INIS)

    Porter, S.; Wettig, J.

    1999-01-01

    No one wants a major accident to occur! This paper describes the development of EC policies to convert this simple and obvious fact into a coherent prevention strategy which can deliver a high level of protection throughout the European Community. The Seveso II Directive is described in detail, being the relevant Community Instrument which Member States must implement in their national laws. The need to achieve the correct balance between setting general goals and being over prescriptive is discussed, commensurate with the intent to be flexible but yet consistent and effective at the same time. The main changes from Seveso I are discussed, including requirements related to the operator's management systems, the competent authority's systems for inspection, and information and consultation arrangements with the public. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  14. The assessment of risk in relation to major hazards, with particular reference to nuclear reactors

    International Nuclear Information System (INIS)

    Farmer, F.R.

    1981-01-01

    The article concentrates mainly on the developing pattern of safety thinking and safety practices which have been brought about by, and in turn have influenced, the growth of modern industrial technology, particularly in the nuclear field. The need to minimize the chance of accidents with serious consequences led to pursuit of safety by siting, by containment and by automatic built-in safety mechanisms; these are discussed. Codes of practice and safety guidelines are becoming linked with more quantitative goals to achieve desired objectives in safety and reliability. This is particularly important in the assessment of major hazards. (author)

  15. Status and functioning of the European Commission's major accident reporting system

    International Nuclear Information System (INIS)

    Kirchsteiger, C.

    1999-01-01

    This paper describes the background, functioning and status of the European Commission's Major Accident Reporting System (MARS), dedicated to collect, in a consistent way, data on major industrial accidents involving dangerous substances from the Member States of the European Union, to analyse and statistically process them, and to create subsets of all non-confidential accidents data and analysis results for export to all Member States. This modern information exchange and analysis tool is made up of two connected parts: one for each local unit (i.e., for the Competent Authority of each EU Member State), and one central part for the European Commission. The local, as well as the central parts of this information network, can serve both as data logging systems and, on different levels of complexity, as data analysis tools. The central database allows complex cluster and pattern analysis, identifying and analysing the succession of the disruptive factors leading to an accident. On this basis, 'lessons learned' can be formulated for the industry for the purposes of further accident prevention. Further, results from analysing data of major industrial accidents reported to MARS are presented. It can be shown that some of the main assumptions in the new 'Seveso II Directive' can directly be validated from MARS data. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  16. Emergency planning for industrial hazards

    International Nuclear Information System (INIS)

    Gow, H.B.F.; Kay, R.W.

    1988-01-01

    The European Communities have produced a Directive on the Major Accident Hazards of Certain Industrial Activities which sets out standards for the control and mitigation of the hazards presented by sites and storages which contain significant quantities of dangerous substances. An essential element of these controls is the provision of effective on-and off-site emergency plans. This conference explores the considerable research effort which is going on throughout the world in the improvement of systems for emergency planning. Attention was also drawn to areas where difficulties still exist, for example in predicting the consequences of an accident, the complexities of communication problems and the difficulties arising from involvement of the public. The proceedings are in six parts which deal with organizations implementing emergency planning: on- and off-site emergency planning and design; techniques for emergency plans; expenses and auditing of emergency plans; lessons learnt from the emergency management of major accidents; information to the public to and during emergencies. (author)

  17. Industrial Accidents Triggered by Natural Hazards: an Emerging Risk Issue

    Science.gov (United States)

    Renni, Elisabetta; Krausmann, Elisabeth; Basco, Anna; Salzano, Ernesto; Cozzani, Valerio

    2010-05-01

    Natural disasters such as earthquakes, tsunamis, flooding or hurricanes have recently and dramatically hit several countries worldwide. Both direct and indirect consequences involved the population, causing on the one hand a high number of fatalities and on the other hand so relevant economical losses that the national gross product may be affected for many years. Loss of critical industrial infrastructures (electricity generation and distribution, gas pipelines, oil refineries, etc.) also occurred, causing further indirect damage to the population. In several cases, accident scenarios with large releases of hazardous materials were triggered by these natural events, causing so-called "Natech events", in which the overall damage resulted from the simultaneous consequences of the natural event and of the release of hazardous substances. Toxic releases, large fires and explosions, as well as possible long-term environmental pollution, economical losses, and overloading of emergency systems were recognised by post-event studies as the main issues of these Natech scenarios. In recent years the increasing frequency and severity of some natural hazards due to climate change has slowly increased the awareness of Natech risk as an emerging risk among the stakeholders. Indeed, the iNTeg-Risk project, co-funded by the European Commission within the 7th Framework Program specifically addresses these scenarios among new technological issues on public safety. The present study, in part carried out within the iNTeg-Risk project, was aimed at the analysis and further development of methods and tools for the assessment and mitigation of Natech accidents. Available tools and knowledge gaps in the assessment of Natech scenarios were highlighted. The analysis mainly addressed the potential impact of flood, lightning and earthquake events on industrial installations where hazardous substances are present. Preliminary screening methodologies and more detailed methods based on

  18. Radiation hazard to children as a consequence of the Chernobyl reactor accident

    Energy Technology Data Exchange (ETDEWEB)

    Hoer, G; Maul, F D; Buell, U; Kriegel, H; Manegold, K H

    1986-01-01

    A flight in a modern jet across the Atlantic Ocean brings about a whole-body radiation dose of 2-5 mrem (Hall, Niklas). The average exposure of the population in West Germany as a result of the Chernobyl accident corresponds therefore to 100 trans-Atlantic flights. The article in hand is not intended to minimize the hazards emanating from radiation accidents - or nuclear weapons tests - but rather as a means of reducing fear that results from not knowing the real facts. Doctors seeking unbiased information will find a number of references and citations that will help them to pass on this information to patients. (orig./HSCH).

  19. Industrial hazard and safety handbook

    CERN Document Server

    King, Ralph W

    1979-01-01

    Industrial Hazard and Safety Handbook (Revised Impression) describes and exposes the main hazards found in industry, with emphasis on how these hazards arise, are ignored, are identified, are eliminated, or are controlled. These hazard conditions can be due to human stresses (for example, insomnia), unsatisfactory working environments, as well as secret industrial processes. The book reviews the cost of accidents, human factors, inspections, insurance, legal aspects, planning for major emergencies, organization, and safety measures. The text discusses regulations, codes of practice, site layou

  20. Emergency planning and the Control of Major Accident Hazards (COMAH/Seveso II) Directive: An approach to determine the public safety zone for toxic cloud releases

    International Nuclear Information System (INIS)

    O'Mahony, Mary T.; Doolan, Donal; O'Sullivan, Alice; Hession, Michael

    2008-01-01

    The EU Control of Major Accidents Hazards Directive (Seveso II) requires an external emergency plan for each top tier site. This paper sets out a method to build the protection of public health into emergency planning for Seveso sites in the EU. The method involves the review of Seveso site details prescribed under the directive. The site safety report sets out the potential accident scenarios. The safety report's worst-case scenario, and chemical involved, is used as the basis for the external emergency plan. A decision was needed on the appropriate threshold value to use as the level of concern to protect public health. The definitions of the regulatory standards (air quality standards and occupational standards) in use were studied, how they are derived and for what purpose. The 10 min acute exposure guideline level (AEGL) for a chemical is recommended as the threshold value to inform decisions taken to protect public health from toxic cloud releases. The area delimited by AEGL 1 defines the population who may be concerned about being exposed. They need information based on comprehensive risk assessment. The area delimited by AEGL 2 defines the population for long-term surveillance when indicated and may include first responders. The area delimited by AEGL 3 defines the population who may present acutely to the medical services. It ensures that the emergency responders site themselves safely. A standard methodology facilitates discussions with plant operators and concerned public. Examples show how the methodology can be adapted to suit explosive risk and response to fire

  1. Public worry and question about radiation hazard. Analysis of JHPS web-site opinion on Fukushima I accident

    International Nuclear Information System (INIS)

    Shimo, Michikuni

    2011-01-01

    This is a tentative interim report of worry and question appeared in Japan Health Physics Society (JHPS) web-site, which formally started from Mar. 25 in 2011 and had origins of voluntary activity by JHPS members from Mar. 16 and of subsequent Japan MECSST requirement on Mar. 18 concerning the Fukushima Daiichi Power Plant Accident (Fukushima I, Mar. 12). Replying to the health risk in the web essentially stood on the stance that the risk always exists, uncertainty is not unavoidable and risk concerns about public, not about individuals. Major two problems generated were solved by the answering with the manager name not with the responsible individual expert, and by the careful, detailed explanation (long sentence) about the safety dose standards. Questioners were thought mostly to be women of ages between 20 and 40 y. Their living addresses written were Tokyo, Chiba, Fukushima areas and so on, although they were mostly unwritten. The number of questions was 709 (10/day) until July 1; their major three items, when classified in 48, were related to the comparison with the nuclear explosion experiments, Chernobyl Accident and released nuclides from the Fukushima I; and their major key words contained were child (39 questions), health hazard and concern (25), food and water (16), etc. It has become clear that sufficient carefulness is necessary in telling non-experts who scarcely have the fundamental, systematic and mechanistic knowledge, about the assessment of the radiation health risk, where quantitativeness is highly important. The author hopes to publish answers not only as a documentary of the Accident but also as a system of concerned knowledge. (T.T.)

  2. [Investigation of emergency capacities for occupational hazard accidents in silicon solar cell producing enterprises].

    Science.gov (United States)

    Yang, D D; Xu, J N; Zhu, B L

    2016-11-20

    Objective: To investigate and analyze the influential factors of occupational hazard acci-dents, emergency facilities and emergency management in Silicon solar cell producing enterprises, then to pro-vide scientific strategies. Methods: The methods of occupationally healthy field investigating, inspecting of ven-tilation effectiveness, setup of emergency program and wearing chemical suit were used. Results: The mainly occupational hazard accidents factors in the process of Silicon solar cell producing included poisoning chemi-cals, high temperature, onizing radiation and some workplaces. The poisoning chemicals included nitric acid, hydrofluoric acid, sulfuric acid, hydrochloric acid, sodium hydroxide, potassium hydroxide, chlorine, phos-phorus oxychloride, phosphorus pentoxide, nitrogen dioxide, ammonia, silane, and so on; the workplaces in-cluded the area of producing battery slides and auxiliary producing area. Among the nine enterprises, gas detec-tors were installed in special gas supplying stations and sites, but the height, location and alarmvalues of gas detectors in six enterprises were not according with standard criteria; emergency shower and eyewash equip-ment were installed in workplaces with strong corrosive chemicals, but the issues of waste water were not solved; ventilation systems were set in the workplaces with ammonia and silane, but not qualified with part lo-cations and parameters in two enterprises; warehouses with materials of acid, alkali, chemical ammonia and phosphorus oxychloride were equipped with positive - pressure air respirator resuscitator and emergency cabi-nets, but with insufficient quantity in seven enterprises and expiration in part of products. The error rate of set-up emergency program and wearing chemical cloth were 30%~100% and 10%~30%, respectively. Among the nine enterprises, there were emergency rescue plans for dangerous chemical accidents, but without profession-al heatstroke and irradiation accident emergency plans

  3. Assessment of chemical loadings to Newark Bay, New Jersey from petroleum and hazardous chemical accidents occurring from 1986 to 1991

    International Nuclear Information System (INIS)

    Gunster, D.G.; Bonnevie, N.L.; Gillis, C.A.; Wenning, R.J.

    1993-01-01

    Newark Bay, New Jersey, is particularly vulnerable to ecological damage from accidental petroleum and chemical spills due to the enclosed nature of the bay and the large volume of chemical and petroleum commerce within the region. A review of the New Jersey Department of Environmental Protection and Energy's database of hazardous chemical spills in New Jersey waterways was conducted to determine the frequency and volume of chemical and petroleum spills in Newark Bay and its major tributaries. Accidents reported from 1986 to 1991 were extracted from the database and summarized. The compilation of records indicated that 1400 incidents, resulting in the release of more than 18 million gallons of hazardous materials to the estuary had been reported to state officials. The bulk of the chemicals released to the aquatic environment were petroleum products, specifically No. 2 Fuel Oil (4,636,512 gallons) and No. 6 Fuel Oil (12,600,683 gallons). The majority of the reported incidents occurred in the Arthur Kill and its tributaries. The results indicate that accidental discharge of petroleum and other hazardous chemicals to Newark Bay represents a significant ongoing source of chemical pollution

  4. An operational centre for managing major chemical industrial accidents.

    Science.gov (United States)

    Kiranoudis, C T; Kourniotis, S P; Christolis, M; Markatos, N C; Zografos, K G; Giannouli, I M; Androutsopoulos, K N; Ziomas, I; Kosmidis, E; Simeonidis, P; Poupkou, N

    2002-01-28

    The most important characteristic of major chemical accidents, from a societal perspective, is their tendency to produce off-site effects. The extent and severity of the accident may significantly affect the population and the environment of the adjacent areas. Following an accident event, effort should be made to limit such effects. Management decisions should be based on rational and quantitative information based on the site specific circumstances and the possible consequences. To produce such information we have developed an operational centre for managing large-scale industrial accidents. Its architecture involves an integrated framework of geographical information system (GIS) and RDBMS technology systems equipped with interactive communication capabilities. The operational centre was developed for Windows 98 platforms, for the region of Thriasion Pedion of West Attica, where the concentration of industrial activity and storage of toxic chemical is immense within areas of high population density. An appropriate case study is given in order to illuminate the use and necessity of the operational centre.

  5. Prevention of "simple accidents at work" with major consequences

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2016-01-01

    broadly. This review identifies gaps in the prevention of simple accidents, relating to safety barriers for risk control and the management processes that need to be in place to deliver those risk controls in a continuingly effective state. The article introduces the ‘‘INFO cards’’ as a tool......The concept ‘‘simple accidents’’ is understood as traumatic events with one victim. In the last 10 years many European countries have seen a decline in the number of fatalities, but there still remain many severe accidents at work. In the years 2009–2010 in European countries 2.0–2.4 million...... occupational accidents a year were notified leading to 4500 fatalities and 90,000 permanent disabilities each year. The article looks at the concept ‘‘accident’’ to find similarities and distinctions between major and simple accident characteristics. The purpose is to find to what extent the same kinds...

  6. Application of risk assessment techniques to 'major hazard' pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Cox, R A

    1982-12-01

    A risk analysis for a hazardous-material pipeline (carrying LPG, ammonia, or high-pressure gas) is presented. The analysis gives results in a form that will assist the decisionmaker in pipeline planning and route selection. The large inventory of hazardous materials in such pipelines means that risks exist even though the accident record of pipeline transportation compares favorably with that for competing modes of transport. Risk analysis techniques - commonly used in the civil aviation, nuclear, and process industries - can be equally well applied to pipelines and can produce results that not only give a measure of the risk but also indicate the principal sources of risk and possible areas for improvement. A number of pipeline risk analyses have demonstrated the viability of the technique and its usefulness as an aid to practical engineering in design, planning, and maintenance/repair phases.

  7. Traffic Accidents in Kosovo – A Major Concern for Kosovo

    Directory of Open Access Journals (Sweden)

    Merita Muharremi

    2017-03-01

    Full Text Available The number of traffic c accidents in Kosovo is increasing rapidly from year to year. As a result of traffi c accidents the number of injured and deaths has increased. During the period of January-December 2016 there were 18541 accidents, which resulted in 110 casualties (Kosovo Police Annual Reports. Campaigns undertaken by the Government of Kosovo, Ministry of Infrastructure and Transport and the Kosovo Police, as well as various video-spots intended to raise awareness of the dangers of traffic c accidents have not accomplished the expected results and did not reduce the number of accidents. Therefore, we can conclude that the number of accidents taking place in Kosovo is concerning. Despite the best efforts of relevant institutions, despite the increased engagement to pass legislation, which would be in line with the European standards, and despite substantial improvements and major investments on the infrastructure, and despite all the measures taken, reducing the number of road accidents remains a significant challenge. With this paper, I will try to draw attention to the actions, measures and activities that I consider the relevant institutions of Kosovo should focus on in order to prevent and to reduce the high number of traffic accidents.

  8. Job safety analysis and hazard identification for work accident prevention in para rubber wood sawmills in southern Thailand.

    Science.gov (United States)

    Thepaksorn, Phayong; Thongjerm, Supawan; Incharoen, Salee; Siriwong, Wattasit; Harada, Kouji; Koizumi, Akio

    2017-11-25

    We utilized job safety analysis (JSA) and hazard identification for work accident prevention in Para rubber wood sawmills, which aimed to investigate occupational health risk exposures and assess the health hazards at sawmills in the Trang Province, located in southern Thailand. We conducted a cross-sectional study which included a walk-through survey, JSA, occupational risk assessment, and environmental samplings from March through September 2015 at four Para rubber wood sawmills. We identified potential occupational safety and health hazards associated with six main processes, including: 1) logging and cutting, 2) sawing the lumber into sheets, 3) planing and re-arranging, 4) vacuuming and wood preservation, 5) drying and planks re-arranging, and 6) grading, packing, and storing. Working in sawmills was associated with high risk of wood dust and noise exposure, occupational accidents injuring hands and feet, chemicals and fungicide exposure, and injury due to poor ergonomics or repetitive work. Several high-risk areas were identified from JSA and hazard identification of the working processes, especially high wood dust and noise exposure when sawing lumber into sheets and risk of occupational accidents of the hands and feet when struck by lumber. All workers were strongly recommended to use personal protective equipment in any working processes. Exposures should be controlled using local ventilation systems and reducing noise transmission. We recommend that the results from the risk assessment performed in this study be used to create an action plan for reducing occupational health hazards in Para rubber sawmills.

  9. The radiation hazard to children as a consequence of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hoer, G.; Maul, F.D.; Buell, U.; Kriegel, H.; Manegold, K.H.

    1986-01-01

    A flight in a modern jet across the Atlantic Ocean brings about a whole-body radiation dose of 2-5 mrem (Hall, Niklas). The average exposure of the population in West Germany as a result of the Chernobyl accident corresponds therefore to 100 trans-Atlantic flights. The article in hand is not intended to minimize the hazards emanating from radiation accidents - or nuclear weapons tests - but rather as a means of reducing fear that results from not knowing the real facts. Doctors seeking unbiased information will find a number of references and citations that will help them to pass on this information to patients. (orig./HSCH) [de

  10. Hazards and hazard combinations relevant for the safety of nuclear power plants

    Science.gov (United States)

    Decker, Kurt; Brinkman, Hans; Raimond, Emmanuel

    2017-04-01

    The potential of the contemporaneous impact of different, yet causally related, hazardous events and event cascades on nuclear power plants is a major contributor to the overall risk of nuclear installations. In the aftermath of the Fukushima accident, which was caused by a combination of severe ground shaking by an earthquake, an earthquake-triggered tsunami and the disruption of the plants from the electrical grid by a seismically induced landslide, hazard combinations and hazard cascades moved into the focus of nuclear safety research. We therefore developed an exhaustive list of external hazards and hazard combinations which pose potential threats to nuclear installations in the framework of the European project ASAMPSAE (Advanced Safety Assessment: Extended PSA). The project gathers 31 partners from Europe, North Amerika and Japan. The list comprises of exhaustive lists of natural hazards, external man-made hazards, and a cross-correlation matrix of these hazards. The hazard list is regarded comprehensive by including all types of hazards that were previously cited in documents by IAEA, the Western European Nuclear Regulators Association (WENRA), and others. 73 natural hazards and 24 man-made external hazards are included. Natural hazards are grouped into seismotectonic hazards, flooding and hydrological hazards, extreme values of meteorological phenomena, rare meteorological phenomena, biological hazards / infestation, geological hazards, and forest fire / wild fire. The list of external man-made hazards includes industry accidents, military accidents, transportation accidents, pipeline accidents and other man-made external events. The large number of different hazards results in the extremely large number of 5.151 theoretically possible hazard combinations (not considering hazard cascades). In principle all of these combinations are possible to occur by random coincidence except for 82 hazard combinations that - depending on the time scale - are mutually

  11. A survey on hazardous materials accidents during road transport in China from 2000 to 2008

    International Nuclear Information System (INIS)

    Yang Jie; Li Fengying; Zhou Jingbo; Zhang Ling; Huang Lei; Bi Jun

    2010-01-01

    A study of 322 accidents that occurred during the road transport of hazardous materials (hazmat) in China from 2000 to 2008 was carried out. The results showed an increase in the frequency of accidents from 2000 to 2007 and a decline in 2008. More than 63% of the accidents occurred in the eastern coastal areas, 25.5% in the central inland areas, and only 10.9% in the western remote areas. The most frequent types of accident were releases (84.5%), followed by gas clouds (13.0%), fires (10.2%), no substance released due to timely measures (9.9%), and explosions (5.9%). The spatial distribution, the causes and consequences of the accidents related to the population (e.g., number of people killed, injured, evacuated, or poisoned), and environment elements were analyzed. Finally, conclusions are drawn concerning the need to improve certain safety measures in the road transport of hazmat in China.

  12. National response plan - Major nuclear or radiological accidents

    International Nuclear Information System (INIS)

    2014-02-01

    France has been implementing stringent radiation protection and nuclear safety and security measures for many years. However, this does not mean that the country is exempt from having to be prepared to deal with an emergency. Changes in France, Europe and other parts of the globe have made it necessary for France to reconsider how it responds to nuclear and radiological emergencies. As the potential impact of a nuclear or radiological accident can affect a wide range of activities, the plan described herein is based on a cross-sector and inter-ministerial approach to emergency response. The Chernobyl and Fukushima-Daiichi disasters are proof that the consequences of a major nuclear or radiological accident can affect all levels of society. These challenges are substantial and relate to: public health: An uncontrolled nuclear accident can have immediate consequences (death, injury, irradiation) as well as long-term consequences that can lead to increased risk of developing radiation-induced diseases (such as certain types of cancer); environmental quality: Radiation contamination can last for several decades and, in some cases, can result in an area being closed off permanently to the public; economic and social continuity: Nuclear accidents bring human activity to a halt in contaminated areas, disrupting the economic and social order of the entire country. It may therefore be necessary to adapt economic and social systems and carry out clean-up operations if people and businesses have been displaced; quality of international relations: Related to fulfillment of obligations to alert and inform European and international partners. This international dimension also covers the protection of French nationals present in countries stricken by a nuclear accident. This national plan provides reference information on how to prepare for a nuclear or radiological emergency and make the appropriate decisions in the event of an emergency. It covers the emergency phase (including

  13. Occupational hazards in hospitals: accidents, radiation, exposure to noxious chemicals, drug addiction and psychic problems, and assault

    Energy Technology Data Exchange (ETDEWEB)

    Gestal, J.J.

    1987-08-01

    Except for infectious diseases all the main occupational hazards affecting health workers are reviewed: accidents (explosions, fires, electrical accidents, and other sources of injury); radiation (stochastic and non-stochastic effects, protective measures, and personnel most at risk); exposure to noxious chemicals, whose effects may be either local (allergic eczema) or generalised (cancer, mutations), particular attention being paid to the hazards presented by formol, ethylene oxide, cytostatics, and anaesthetic gases; drug addiction (which is more common among health workers than the general population) and psychic problems associated with promotion, shift work, and emotional stress; and assault (various types of assault suffered by health workers, its causes, and the characterisation of the most aggressive patients).

  14. Occupational hazards in hospitals: accidents, radiation, exposure to noxious chemicals, drug addiction and psychic problems, and assault

    International Nuclear Information System (INIS)

    Gestal, J.J.

    1987-01-01

    Except for infectious diseases all the main occupational hazards affecting health workers are reviewed: accidents (explosions, fires, electrical accidents, and other sources of injury); radiation (stochastic and non-stochastic effects, protective measures, and personnel most at risk); exposure to noxious chemicals, whose effects may be either local (allergic eczema) or generalised (cancer, mutations), particular attention being paid to the hazards presented by formol, ethylene oxide, cytostatics, and anaesthetic gases; drug addiction (which is more common among health workers than the general population) and psychic problems associated with promotion, shift work, and emotional stress; and assault (various types of assault suffered by health workers, its causes, and the characterisation of the most aggressive patients). (author)

  15. A DOE-STD-3009 hazard and accident analysis methodology for non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    MAHN, JEFFREY A.; WALKER, SHARON ANN

    2000-01-01

    This paper demonstrates the use of appropriate consequence evaluation criteria in conjunction with generic likelihood of occurrence data to produce consistent hazard analysis results for nonreactor nuclear facility Safety Analysis Reports (SAR). An additional objective is to demonstrate the use of generic likelihood of occurrence data as a means for deriving defendable accident sequence frequencies, thereby enabling the screening of potentially incredible events ( -6 per year) from the design basis accident envelope. Generic likelihood of occurrence data has been used successfully in performing SAR hazard and accident analyses for two nonreactor nuclear facilities at Sandia National Laboratories. DOE-STD-3009-94 addresses and even encourages use of a qualitative binning technique for deriving and ranking nonreactor nuclear facility risks. However, qualitative techniques invariably lead to reviewer requests for more details associated with consequence or likelihood of occurrence bin assignments in the test of the SAR. Hazard analysis data displayed in simple worksheet format generally elicits questions about not only the assumptions behind the data, but also the quantitative bases for the assumptions themselves (engineering judgment may not be considered sufficient by some reviewers). This is especially true where the criteria for qualitative binning of likelihood of occurrence involves numerical ranges. Oftentimes reviewers want to see calculations or at least a discussion of event frequencies or failure probabilities to support likelihood of occurrence bin assignments. This may become a significant point of contention for events that have been binned as incredible. This paper will show how the use of readily available generic data can avoid many of the reviewer questions that will inevitably arise from strictly qualitative analyses, while not significantly increasing the overall burden on the analyst

  16. Probabilistic Approach to Conditional Probability of Release of Hazardous Materials from Railroad Tank Cars during Accidents

    Science.gov (United States)

    2009-10-13

    This paper describes a probabilistic approach to estimate the conditional probability of release of hazardous materials from railroad tank cars during train accidents. Monte Carlo methods are used in developing a probabilistic model to simulate head ...

  17. Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

    During the 1960's and 70's the expanded use of nuclear materials to generate electricity, to provide medical benefits, and for research purposes continued to grow in the United States. While substantial effort went into constructing plants and facilities and providing for a number of redundant backup systems for safety purposes, little effort went into the development of emergency response plans for possible major radiological accidents. Unfortunately, adequate plans and procedures had not been developed to co-ordinate either state or federal emergency response assets and personnel should a major radiological accident occur. This situation became quite evident following the Three Mile Island Nuclear Reactor accident in 1979. An accident of that magnitude had not been adequately prepared for and Pennsylvania's limited emergency radiological resources and capabilities were quickly exhausted. Several federal agencies with statutory responsibilities for emergency response, including the U.S. Environmental Protection Agency (EPA), U.S. Department of Energy (DOE), Federal Emergency Management Agency (FEMA), Nuclear Regulatory Commission (NRC), and others provided extensive assistance and support during the accident. However, the assistance was not fully co-ordinated nor controlled. Following the Three Mile Island incident 13 federal agencies worked co-operatively to develop an agreement called the Federal Radiological Emergency Response Plan (FRERP). Signed in November 1985, this plan delineated the statutory responsibilities and authorities of each federal agency signatory to the FRERP. In the event of a major radiological accident, the FRERP would be activated to ensure that a co-ordinated federal emergency response would be available to respond to any major radiological accident scenario. The FRERP encompasses a wide variety of radiological accidents, not just those stemming from nuclear power plants. Activation of the FRERP could occur from major accidents involving

  18. Keynote on lessons from major radiation accidents

    International Nuclear Information System (INIS)

    Ortiz, P.; Oresegun, M.; Wheatley, J.

    2000-01-01

    Generic lessons have been learned from a relatively large number of accidents in the most relevant practices (a set of analysis have been made on about 90 radiotherapy events, 43 industrial radiography and nine from industrial irradiations); more specific lessons have been drawn from in-depth investigations of individual accidents. The body of knowledge is grouped as follows: a) radiotherapy is very unique in that humans (patients) are purposely given very high radiation doses (20-75 Gy) by placing them in the radiation beam or by placing radioactive sources in contact with tissues. Intended deterministic effects are the essence of the normal radiotherapy practice and relatively small deviation from the intended doses, i.e,, slightly higher or lower than intended may cause increased rate of severe complication or reduce probability of cure. Consequences of major accidents have been devastating, affecting tens, even hundreds of patients and causing death (directly or indirectly) to a large number of them; b) accidents involving industrial radiography are the most frequent cause of overexposure to workers (radiographers); c) accidents with industrial irradiators have lower probability of occurrence, however, they are deemed to be fatal, especially when whole body exposure to panoramic gamma irradiators occur; partial body irradiation from industrial or research accelerator beams has led to amputation of hands and legs; d) when control of sources was relinquished ('orphan' sources) this has resulted in severe injuries, in some cases death and widespread contamination of the environment. A tool for further dissemination of lessons will be an international reporting system of unusual radiation events (RADEV), being introduced world-wide. Accidents were rarely due to a single human error or isolated equipment failure. In most cases there was a combination of elements such as: a) unawareness of the potential for an accident, b) poor education, which usually did not

  19. The ARIPAR project: analysis of the major accident risks connected with industrial and transportation activities in the Ravenna area

    International Nuclear Information System (INIS)

    Egidi, Demetrio; Foraboschi, Franco P.; Spadoni, Gigliola; Amendola, Aniello

    1995-01-01

    The paper describes the ARIPAR project aimed at the assessment of the major accident risks connected with storage, process and transportation of dangerous substances in the densely populated Ravenna area in Italy, which includes a large complex of chemical and petrochemical plants and minor industries, essentially distributed around an important commercial port. Large quantities of dangerous goods are involved in various transportation forms connected with the industrial and commercial activity of the port. The project started by making a complete inventory of fixed installations and transportation activities capable of provoking major fire, explosion and toxic release events; then relevant accident scenarios were developed for the single hazard sources; probabilities were assigned to the events and consequences were evaluated; finally iso-risk contours and F-N diagrams were evaluated both for the single sources and for the overall area. This required the development of a particular methodology for analysis of area risk and of associated software packages which allowed examination of the relative importance of the different activities and typologies of materials involved. The methodological approach and the results have proved to be very useful for the priority-ranking of risk mitigating interventions and physical planning in a complex area

  20. Hazard Analysis Database Report

    Energy Technology Data Exchange (ETDEWEB)

    GAULT, G.W.

    1999-10-13

    The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The FSAR is part of the approved TWRS Authorization Basis (AB). This document describes, identifies, and defines the contents and structure of the TWRS FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The TWRS Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The database supports the preparation of Chapters 3,4, and 5 of the TWRS FSAR and the USQ process and consists of two major, interrelated data sets: (1) Hazard Evaluation Database--Data from the results of the hazard evaluations; and (2) Hazard Topography Database--Data from the system familiarization and hazard identification.

  1. Would ISO 9000 have prevented the two major radiotherapy accidents in the UK?

    International Nuclear Information System (INIS)

    McKenzie, A.L.

    1997-01-01

    There have been two major accidents in the UK. In Exeter, 207 patients were overdosed by 25%, and, in Stoke-on-Trent, just under 1000 patients were underdoses by about the same amount. The ISO 9000 quality assurance system should create an environment and a culture where the risk of such an accident is minimized. In this presentation, the background to the two accidents is analysed in the light of the question - would these accidents have occurred if ISO 9000 had been in place in the two centres?

  2. Industrial Safety and Accidents Prevention

    International Nuclear Information System (INIS)

    Sajjad Akbar

    2006-01-01

    Accident Hazards, dangers, losses and risk are what we would to like to eliminate, minimize or avoid in industry. Modern industries have created many opportunities for these against which man's primitive instincts offer no protection. In today's complex industrial environment safety has become major preoccupation, especially after the realization that there is a clear economic incentive to do so. Industrial hazards may cause by human error or by physical or mechanical malfunction, it is very often possible to eliminate the worst consequences of human error by engineering modification. But the modification also needs checking very thoroughly to ensue that it has not introduced some new and unsuspected hazard. (author)

  3. Environmental Risk Assessment: Spatial Analysis of Chemical Hazards and Risks in South Korea

    Science.gov (United States)

    Yu, H.; Heo, S.; Kim, M.; Lee, W. K.; Jong-Ryeul, S.

    2017-12-01

    This study identified chemical hazard and risk levels in Korea by analyzing the spatial distribution of chemical factories and accidents. The number of chemical factories and accidents in 5-km2 grids were used as the attribute value for spatial analysis. First, semi-variograms were conducted to examine spatial distribution patterns and to identify spatial autocorrelation of chemical factories and accidents. Semi-variograms explained that the spatial distribution of chemical factories and accidents were spatially autocorrelated. Second, the results of the semi-variograms were used in Ordinary Kriging to estimate chemical hazard and risk level. The level values were extracted from the Ordinary Kriging result and their spatial similarity was examined by juxtaposing the two values with respect to their location. Six peaks were identified in both the hazard and risk estimation result, and the peaks correlated with major cities in Korea. Third, the estimated hazard and risk levels were classified with geometrical interval and could be classified into four quadrants: Low Hazard and Low Risk (LHLR), Low Hazard and High Risk (LHHR), High Hazard and Low Risk (HHLR), and High Hazard and High Risk (HHHR). The 4 groups identified different chemical safety management issues in Korea; relatively safe LHLR group, many chemical reseller factories were found in HHLR group, chemical transportation accidents were in the LHHR group, and an abundance of factories and accidents were in the HHHR group. Each quadrant represented different safety management obstacles in Korea, and studying spatial differences can support the establishment of an efficient risk management plan.

  4. Hazard Analysis Database Report

    CERN Document Server

    Grams, W H

    2000-01-01

    The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for U S . Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR). The FSAR is part of the approved Authorization Basis (AB) for the River Protection Project (RPP). This document describes, identifies, and defines the contents and structure of the Tank Farms FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The Hazard Analysis Database supports the preparation of Chapters 3 ,4 , and 5 of the Tank Farms FSAR and the Unreviewed Safety Question (USQ) process and consists of two major, interrelated data sets: (1) Hazard Analysis Database: Data from t...

  5. Domino effect in chemical accidents: main features and accident sequences

    OpenAIRE

    Casal Fàbrega, Joaquim; Darbra Roman, Rosa Maria

    2010-01-01

    The main features of domino accidents in process/storage plants and in the transportation of hazardous materials were studied through an analysis of 225 accidents involving this effect. Data on these accidents, which occurred after 1961, were taken from several sources. Aspects analyzed included the accident scenario, the type of accident, the materials involved, the causes and consequences and the most common accident sequences. The analysis showed that the most frequent causes a...

  6. Effects of the Chernobyl accident on public perceptions of nuclear plant accident risks

    International Nuclear Information System (INIS)

    Lindell, M.K.; Perry, R.W.

    1990-01-01

    Assessments of public perceptions of the characteristics of a nuclear power plant accident and affective responses to its likelihood were conducted 5 months before and 1 month after the Chernobyl accident. Analyses of data from 69 residents of southwestern Washington showed significant test-retest correlations for only 10 of 18 variables--accident likelihood, three measures of impact characteristics, three measures of affective reactions, and hazard knowledge by governmental sources. Of these variables, only two had significant changes in mean ratings; frequency of thought and frequency of discussion about a nearby nuclear power plant both increased. While there were significant changes only for two personal consequences (expectations of cancer and genetic effects), both of these decreased. The results of this study indicate that more attention should be given to assessing the stability of risk perceptions over time. Moreover, the data demonstrate that experience with a major accident can actually decrease rather than increase perceptions of threat

  7. Managing major chemical accidents in China: Towards effective risk information

    NARCIS (Netherlands)

    He, G.; Zhang, L.; Lu, Y.; Mol, A.P.J.

    2011-01-01

    Chemical industries, from their very inception, have been controversial due to the high risks they impose on safety of human beings and the environment. Recent decades have witnessed increasing impacts of the accelerating expansion of chemical industries and chemical accidents have become a major

  8. Setting the scenario - potential hazards of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Berry, R.J.; McPhail, N.

    1989-01-01

    The range of nuclear fuel cycle services provided by the various plants belonging to BNFL throughout the UK are described. The Sellafield Reprocessing Plant as the site which has the greatest potential for radiological hazard is then considered in more detail. In particular the safety cycle designed to prevent radiological accidents at Sellafield, emergency planning, the consequences of a major accident at Sellafield and the medical arrangements in the event of an accident are all discussed. (UK)

  9. Natural hazard impacts on transport systems: analyzing the data base of transport accidents in Russia

    Science.gov (United States)

    Petrova, Elena

    2015-04-01

    We consider a transport accident as any accident that occurs during transportation of people and goods. It comprises of accidents involving air, road, rail, water, and pipeline transport. With over 1.2 million people killed each year, road accidents are one of the world's leading causes of death; another 20-50 million people are injured each year on the world's roads while walking, cycling, or driving. Transport accidents of other types including air, rail, and water transport accidents are not as numerous as road crashes, but the relative risk of each accident is much higher because of the higher number of people killed and injured per accident. Pipeline ruptures cause large damages to the environment. That is why safety and security are of primary concern for any transport system. The transport system of the Russian Federation (RF) is one of the most extensive in the world. It includes 1,283,000 km of public roads, more than 600,000 km of airlines, more than 200,000 km of gas, oil, and product pipelines, 115,000 km of inland waterways, and 87,000 km of railways. The transport system, especially the transport infrastructure of the country is exposed to impacts of various natural hazards and weather extremes such as heavy rains, snowfalls, snowdrifts, floods, earthquakes, volcanic eruptions, landslides, snow avalanches, debris flows, rock falls, fog or icing roads, and other natural factors that additionally trigger many accidents. In June 2014, the Ministry of Transport of the RF has compiled a new version of the Transport Strategy of the RF up to 2030. Among of the key pillars of the Strategy are to increase the safety of the transport system and to reduce negative environmental impacts. Using the data base of technological accidents that was created by the author, the study investigates temporal variations and regional differences of the transport accidents' risk within the Russian federal regions and a contribution of natural factors to occurrences of different

  10. On-site transportation and handling of uranium-233 special nuclear material: Preliminary hazards and accident analysis. Final

    International Nuclear Information System (INIS)

    Solack, T.; West, D.; Ullman, D.; Coppock, G.; Cox, C.

    1995-01-01

    U-233 Special Nuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 Special Nuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards

  11. Prediction accident triangle in maintenance of underground mine facilities using Poisson distribution analysis

    Science.gov (United States)

    Khuluqi, M. H.; Prapdito, R. R.; Sambodo, F. P.

    2018-04-01

    In Indonesia, mining is categorized as a hazardous industry. In recent years, a dramatic increase of mining equipment and technological complexities had resulted in higher maintenance expectations that accompanied by the changes in the working conditions, especially on safety. Ensuring safety during the process of conducting maintenance works in underground mine is important as an integral part of accident prevention programs. Accident triangle has provided a support to safety practitioner to draw a road map in preventing accidents. Poisson distribution is appropriate for the analysis of accidents at a specific site in a given time period. Based on the analysis of accident statistics in the underground mine maintenance of PT. Freeport Indonesia from 2011 through 2016, it is found that 12 minor accidents for 1 major accident and 66 equipment damages for 1 major accident as a new value of accident triangle. The result can be used for the future need for improving the accident prevention programs.

  12. Major hazard risk indicators for monitoring of trends in the Norwegian offshore petroleum sector

    International Nuclear Information System (INIS)

    Vinnem, Jan Erik; Aven, Terje; Husebo, Torleif; Seljelid, Jorunn; Tveit, Odd J.

    2006-01-01

    The Petroleum Safety Authority Norway (PSA, formerly Norwegian Petroleum Directorate) took in 1999 the initiative to develop a method in order to assess trends and status for the risk levels in the Norwegian offshore petroleum industry. A method was developed, and a pilot study report was issued in April 2001, covering the period 1996-2000. Annual updates have been performed since then, and the latest report covers the period 1996-2004. The statistical approach is based on recording occurrence of near misses and relevant incidents, performance of barriers and results from risk assessments. Of similar importance is an evaluation of safety culture, motivation, communication and perceived risk. This is covered through the use of social science methods, such as questionnaire surveys and a number of interviews, audit and inspection reports as well as accident and incident investigations. There are also indicators for occupational accidents and occupational illness/-physical working environment factors. The focus is on the major hazard risk components for personnel staying on the offshore installations. An overview of the indicators used to illustrate these risk aspects is presented, followed by a discussion of the analytical approach used for these indicators. Results from the risk assessment for the Norwegian Continental Shelf in the period 1996-2004 are used throughout for illustration, and discussion of challenges

  13. Fatal accidents in nighttime vs. daytime highway construction work zones.

    Science.gov (United States)

    Arditi, David; Lee, Dong-Eun; Polat, Gul

    2007-01-01

    Awareness about worker safety in nighttime construction has been a major concern because it is believed that nighttime construction creates hazardous work conditions. However, only a few studies provide valuable comparative information about accident characteristics of nighttime and daytime highway construction activities. This study investigates fatal accidents that occurred in Illinois highway work zones in the period 1996-2001 in order to determine the safety differences between nighttime and daytime highway construction. The lighting and weather conditions were included into the study as control parameters to see their effects on the frequency of fatal accidents occurring in work zones. According to this study, there is evidence that nighttime construction is more hazardous than daytime construction. The inclusion of a weather parameter into the analysis has limited effect on this finding. The study justifies establishing an efficient work zone accident reporting system and taking all necessary measures to enhance safety in nighttime work zones.

  14. Detection and analysis of accident black spots with even small accident figures.

    NARCIS (Netherlands)

    Oppe, S.

    1982-01-01

    Accident black spots are usually defined as road locations with high accident potentials. In order to detect such hazardous locations we have to know the probability of an accident for a traffic situation of some kind, or the mean number of accidents for some unit of time. In almost all procedures

  15. Checking of seismic and tsunami hazard for coastal NPP of Chinese continent after Fukushima nuclear accident

    Institute of Scientific and Technical Information of China (English)

    Chang Xiangdong; Zhou Bengang; Zhao Lianda

    2013-01-01

    A checking on seismic and tsunami hazard for coastal nuclear power plant (NPP) of Chinese continent has been made after Japanese Fukushima nuclear accident caused by earthquake tsunami.The results of the checking are introduced briefly in this paper,including the evaluations of seismic and tsunami hazard in NPP siting period,checking results on seismic and tsunami hazard.Because Chinese coastal area belongs to the continental shelf and far from the boundary of plate collision,the tsunami hazard is not significant for coastal area of Chinese continent.However,the effect from tsunami still can' t be excluded absolutely since calculated result of Manila trench tsunami source although the tsunami wave is lower than water level from storm surge.The research about earthquake tsunami will continue in future.The tsunami warning system and emergency program of NPP will be established based on principle of defense in depth in China.

  16. Analysis on the nitrogen drilling accident of Well Qionglai 1 (I: Major inducement events of the accident

    Directory of Open Access Journals (Sweden)

    Yingfeng Meng

    2015-12-01

    Full Text Available Nitrogen drilling in poor tight gas sandstone should be safe because of very low gas production. But a serious accident of fire blowout occurred during nitrogen drilling of Well Qionglai 1. This is the first nitrogen drilling accident in China, which was beyond people's knowledge about the safety of nitrogen drilling and brought negative effects on the development of gas drilling technology still in start-up phase and resulted in dramatic reduction in application of gas drilling. In order to form a correct understanding, the accident was systematically analyzed, the major events resulting in this accident were inferred. It is discovered for the first time that violent ejection of rock clasts and natural gas occurred due to the sudden burst of downhole rock when the fractured tight gas zone was penetrated during nitrogen drilling, which has been named as “rock burst and blowout by gas bomb”, short for “rock burst”. Then all the induced events related to the rock burst are as following: upthrust force on drilling string from rock burst, bridging-off formed and destructed repeatedly at bit and centralizer, and so on. However, the most direct important event of the accident turns out to be the blockage in the blooie pipe from rock burst clasts and the resulted high pressure at the wellhead. The high pressure at the wellhead causes the blooie pipe to crack and trigged blowout and deflagration of natural gas, which is the direct presentation of the accident.

  17. National plan of response to a major nuclear or radiological accident

    International Nuclear Information System (INIS)

    2014-02-01

    The first part of this document presents the response strategies and principles to be applied in the case of a major nuclear or radiological accident. It presents the general framework and the 8 reference situations which are used as references for the plan. It presents the general organisation of crisis management by the State (initial organisation, organisation at the national level, communication channel, international channels, case of transport of radioactive materials, responsibility of the various actors). Then, it presents the strategies of response, i.e., a global strategy and more specific strategies applicable in different sectors or fields: for the control of the concerned installation or transport, in the case of transport of radioactive materials, for the protection of the population, for the taking into care, for communication, for the continuity of social and economic life, at the European level, for the post-accidental management. The second part is a guide which contains sheets describing reactions in different situations: uncertainty, accident in an installation resulting in an either immediate and short, or immediate and long, or delayed and long release, accident in a transport of radioactive materials with potential release, accident occurring abroad which may have a more or less significant impact in France, and accident at sea

  18. Light water reactor accidents - is there really a major public risk

    Energy Technology Data Exchange (ETDEWEB)

    Levenson, M [Bechtel Power Corp., San Francisco, CA (USA)

    1983-04-01

    During the past decade, a major mismatch has developed between the actual public risk from nuclear power and the public perception of that risk. Extensive analyses have been performed on the probability of accidents at nuclear power plants, but such analyses have used assumed consequences rather than those that have been scientifically derived. The assumed consequences have been overstated and needlessly scare the public or lead to unwarranted evacuations. The 40 years of experience in research, development and testing, and the history of actual accidents, provide a sound basis for assessment-a basis that has not been utilized.

  19. Potentialities of robots in major accident situations

    International Nuclear Information System (INIS)

    Chevallier, M.

    2013-01-01

    The INTRA group was founded in 1988, 2 years after the Chernobyl accident with the purpose of a cooperation between EDF, Cogema and CEA in order to develop and operate a fleet of robots able to intervene and replace man in a nuclear facility in case of major accident. Now INTRA disposes of 5 types of equipment: first, robots for the inside of buildings (they can overcome 40 cm high obstacles, open doors, go upstairs) they are wire-guided and enjoy a battery life of 6 to 8 hours. Secondly, robots for the open air that are able to move in very degraded grounds, they are remote controlled through radio-waves and their autonomy range nears 5 km. Thirdly, public works vehicles, INTRA has developed an excavator and a dump truck, both are remote controlled, they allow the making of any earth work. Fourthly, INTRA has developed 2 systems of contamination measurement: Skylink and Helinuc. Skylink is a system of 20 radiation monitors that can be dispatched on the contaminated zone, their data is collected through radio waves. Helinuc is a kind of gamma spectrometer that is helicopter-borne and can draw a map of the contamination around the installation. Fifthly, 2 drones are being tested, they will be fitted with radiation monitors. (A.C.)

  20. Contribution to evaluating nuclear power plant accidents

    International Nuclear Information System (INIS)

    Razga, J.; Horacek, P.

    1990-01-01

    Large-scale accidents pose the highest risk in the use of nuclear power. They are the major factor that has to be taken into account when assessing the effect of nuclear power plants on human health and on the environment. In Czechoslovak conditions, the effectiveness of provisions made to reduce the hazard of large-scale nuclear power plant accidents must be considered from the following aspects: effect on human health, consequences of long-term disabling of the infrastructure, potential of human and material reserves in coping with the accident, consequences of power failure for the electricity system, effect on agricultural production and catering, risk of ground and surface water contamination in the Labe or Danube river basin, and international political aspects. (Z.M.). 3 tabs., 18 refs

  1. Safety and man in light of the analysis of major technical accidents

    International Nuclear Information System (INIS)

    Carnino, A.

    1990-01-01

    Up to the seventies, it was not easy to admit human failure as a cause of industrial accidents. Man was considered as reliable. With the perfection of materials, technical systems and industrial processes though, man has become the weakest link in the chain of technical events. He is and stays a remarkably reliable being, with a roughly estimated average failure quota of 1:1000 manipulations. If the hypothetical risk should be kept very low, this value can become a problem. Instead of judging a mistake as a punishable crime, as the present tendency will have it, a more differentiated, systematical approach is called for. By means of an analysis of four major accidents - Chernobyl, Three Mile Island, Challenger and Bhopal - interesting parallels between the causes of such accidents can be found. Human failure, e.g. of a surgeon, is in most cases, the direct cause of an accident. A whole series of further causes, which can be assigned to different areas of influence but are usually interdependent, also play a role. While the human factor must be viewed as more or less predetermined, far reaching improvements can be made to reduce the risk of accident. Today, thanks to modern technology and new findings, it is possible to practically neutralize human error. This creates more costs and necessitates giving up short term production maximization. It also requires the willingness to give safety absolute priority. The name 'culture de surete' (safety culture) is used to describe this concept. Surprising similarities between the causes of the four mentioned major accidents were discovered. Certain circumstances, such as the time of day, played a role. The concept of a plant, resp. technical process has an essential influence, as well as company policy (importance of safety, preparation of emergency procedures, training, maintenance, company rules) and management (evaluation and realization of foreign and the company's own operation experiences and error alarms). (author) 7

  2. Economic consequences of major accidents in the industrial plants: The case of a nuclear power plant

    International Nuclear Information System (INIS)

    Fraix, J.

    1989-09-01

    These last years, newspapers head-lines have reported various accidents (Mexico City, Bhopal, Chernobyl, ...) which have drawn attention to the fact that the major technological risk is now a reality and that, undoubtedly, industrial decision-makers ought to integrate it into their preoccupations. In addition to the sometimes considerable human problems such accidents engender, their economic consequences may be such that they become significant on a national or even international scale. The aim of the present paper is to analyse these economic effects by using the particular context of a nuclear power plant. The author has deliberately limited his subject to the consequences of a major accident, that is to say a sudden event, theoretically unforeseen and beyond man's control. The qualification major means an accident of which the consequences extend far beyond the industrial plant itself. The direct and indirect economic consequences are analysed from the responsibility point of view as well as from the national and international community's point of view. A paragraph explains how the coverage of the costs can rely on the cooperation of a number of parties: responsible company, state, insurers, customers, etc. The study is broadly based on the experience resulting from the two major accidents which happened in the nuclear industry these last years (Three Mile Island in 1979 and Chernobyl in 1986) and makes use of more theoretical considerations, for example in the field of the economic evaluation of human life. (author). 58 refs, 2 figs, 12 tabs

  3. Utilization of accident databases and fuzzy sets to estimate frequency of HazMat transport accidents

    International Nuclear Information System (INIS)

    Qiao Yuanhua; Keren, Nir; Mannan, M. Sam

    2009-01-01

    Risk assessment and management of transportation of hazardous materials (HazMat) require the estimation of accident frequency. This paper presents a methodology to estimate hazardous materials transportation accident frequency by utilizing publicly available databases and expert knowledge. The estimation process addresses route-dependent and route-independent variables. Negative binomial regression is applied to an analysis of the Department of Public Safety (DPS) accident database to derive basic accident frequency as a function of route-dependent variables, while the effects of route-independent variables are modeled by fuzzy logic. The integrated methodology provides the basis for an overall transportation risk analysis, which can be used later to develop a decision support system.

  4. Frequent flyer business travelers: major exposure hazards.

    Science.gov (United States)

    Tompkins, Olga S; Randolph, Susan A; Ostendorf, Judith S

    2005-02-01

    Bagshaw (2004) notes "the modern commercial aircraft cabin is maintained with adequate environmental control for the comfort of most healthy individuals" (p. 417). Occupational health nurses frequently deal with a population that may include unhealthy individuals or those with pre-existing conditions. It is critical for occupational health nurses to stay current with major hazards faced by frequent flyer business travelers to assist in identifying and preventing adverse health effects associated with these exposures.

  5. Hazard management at the workplace

    International Nuclear Information System (INIS)

    Hasfazilah Hassan; Azimawati Ahmad; Syed Asraf Fahlawi Wafa S M Ghazi; Hairul Nizam Idris

    2005-01-01

    Failure to ensure health and safety environment at workplace will cause an accident involving loss to the time, human resource, finance and for the worse case effect the moral value of an organization. If we go through to the cause of the accident, it is impossible to have a totally safety workplace. It is because every process in work activities has it own hazard elements. The purpose of this paper is to discuss the best action to prevent from the hazard with a comprehensive and effectiveness hazard management. Hazard management is the one of the pro-active hazard control. With this we manage to identify and evaluate the hazard and control the hazard risk. Therefore, hazard management should be screened constantly and continuously to make sure work hazard always in control. (Author)

  6. Identification of reference accident scenarios in SEVESO establishments

    International Nuclear Information System (INIS)

    Delvosalle, C.; Fievez, C.; Pipart, A.; Fabrega, J. Casal; Planas, E.; Christou, M.; Mushtaq, F.

    2005-01-01

    In the frame of the ESREL special session on ARAMIS project, this paper aims at presenting the work carried out in the first Work Package, devoted to the definition of accident scenarios. This topic is a key-point in risk assessment, and serves as basis for the whole risk quantification. A first part of the work aims at building a Methodology for the Identification of Major Accident Hazards (MIMAH), which is carried out with the development of generic fault and event trees based on a typology of equipment and substances. This work is coupled with an historical analysis of accidents. In a second part, influence of safety devices and policies will be considered, in order to build a Methodology for the Identification of Reference Accident Scenarios (MIRAS). This last one will take into account safety systems and lead to obtain more realistic scenarios

  7. Using MFM methodology to generate and define major accident scenarios for quantitative risk assessment studies

    DEFF Research Database (Denmark)

    Hua, Xinsheng; Wu, Zongzhi; Lind, Morten

    2017-01-01

    to calculate likelihood of each MAS. Combining the likelihood of each scenario with a qualitative risk matrix, each major accident scenario is thereby ranked for consideration for detailed consequence analysis. The methodology is successfully highlighted using part of BMA-process for production of hydrogen......Generating and defining Major Accident Scenarios (MAS) are commonly agreed as the key step for quantitative risk assessment (QRA). The aim of the study is to explore the feasibility of using Multilevel Flow Modeling (MFM) methodology to formulating MAS. Traditionally this is usually done based...

  8. 49 CFR 195.50 - Reporting accidents.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Reporting accidents. 195.50 Section 195.50 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY... PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.50 Reporting accidents. An accident...

  9. Assessment of major technical hazards in the insurance business

    International Nuclear Information System (INIS)

    Huppmann, H.

    1981-01-01

    Major technical hazards are covered by means of demand premium rates and subjective corrections according to the degree of innovation and different environmental impacts. The insurer compensates remaining risks by compensatory payments or he moderates them at least in their effects. (DG) [de

  10. Offsite transportation hazards assessment

    International Nuclear Information System (INIS)

    Burnside, M.E.

    1997-01-01

    This report documents the emergency preparedness Hazards Assessment for the offsite transportation of hazardous material from the Hanford Site. The assessment is required by the US Department of Energy (DOE) Order 151.1. Offsite transportation accidents are categorized using the DOE system to assist communication within the DOE and assure that appropriate assistance is provided to the people in charge at the scene. The assistance will initially include information about the load and the potential hazards. Local authorities will use the information to protect the public following a transportation accident. This Hazards Assessment will focus on the material being transported from the Hanford Site. Shipments coming to Hanford are the responsibility of the shipper and the carrier and, therefore, are not included in this Hazards Assessment, unless the DOE elects to be the shipper of record

  11. Hazardous waste storage facility accident scenarios for the U.S. Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    Policastro, A.; Roglans-Ribas, J.; Marmer, D.; Lazaro, M.; Mueller, C.; Freeman, W.

    1994-01-01

    This paper presents the methods for developing accident categories and accident frequencies for internally initiated accidents at hazardous waste storage facilities (HWSFs) at US Department of Energy (DOE) sites. This categorization is a necessary first step in evaluating the risk of accidents to workers and the general population at each of the sites. This risk evaluation is part of the process of comparing alternative management strategies in DOE's Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS). Such strategies involve regionalization, decentralization, and centralization of waste treatment, storage, and disposal activities. Potential accidents at the HWSFs at the DOE sites are divided into categories of spill alone, spill plus fire, and other event combinations including spill plus fire plus explosion, fire only, spill and explosion, and fire and explosion. One or more accidents are chosen to represent the types of accidents for FY 1992 for 12 DOE sites were studied to determine the most representative set of possible accidents at all DOE sites. Each accident scenario is given a probability of occurrence that is adjusted, depending on the throughput and waste composition that passes through the HWSF at the particular site. The justification for the probabilities chosen is presented

  12. Hazardous waste storage facility accident scenarios for the U.S. Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

    Energy Technology Data Exchange (ETDEWEB)

    Policastro, A.; Roglans-Ribas, J.; Marmer, D.; Lazaro, M.; Mueller, C. [Argonne National Lab., IL (United States); Freeman, W. [Univ. of Illinois, Chicago, IL (United States). Dept. of Chemistry

    1994-03-01

    This paper presents the methods for developing accident categories and accident frequencies for internally initiated accidents at hazardous waste storage facilities (HWSFs) at US Department of Energy (DOE) sites. This categorization is a necessary first step in evaluating the risk of accidents to workers and the general population at each of the sites. This risk evaluation is part of the process of comparing alternative management strategies in DOE`s Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS). Such strategies involve regionalization, decentralization, and centralization of waste treatment, storage, and disposal activities. Potential accidents at the HWSFs at the DOE sites are divided into categories of spill alone, spill plus fire, and other event combinations including spill plus fire plus explosion, fire only, spill and explosion, and fire and explosion. One or more accidents are chosen to represent the types of accidents for FY 1992 for 12 DOE sites were studied to determine the most representative set of possible accidents at all DOE sites. Each accident scenario is given a probability of occurrence that is adjusted, depending on the throughput and waste composition that passes through the HWSF at the particular site. The justification for the probabilities chosen is presented.

  13. Normal accidents

    International Nuclear Information System (INIS)

    Perrow, C.

    1989-01-01

    The author has chosen numerous concrete examples to illustrate the hazardousness inherent in high-risk technologies. Starting with the TMI reactor accident in 1979, he shows that it is not only the nuclear energy sector that bears the risk of 'normal accidents', but also quite a number of other technologies and industrial sectors, or research fields. The author refers to the petrochemical industry, shipping, air traffic, large dams, mining activities, and genetic engineering, showing that due to the complexity of the systems and their manifold, rapidly interacting processes, accidents happen that cannot be thoroughly calculated, and hence are unavoidable. (orig./HP) [de

  14. Domino effect in chemical accidents: main features and accident sequences.

    Science.gov (United States)

    Darbra, R M; Palacios, Adriana; Casal, Joaquim

    2010-11-15

    The main features of domino accidents in process/storage plants and in the transportation of hazardous materials were studied through an analysis of 225 accidents involving this effect. Data on these accidents, which occurred after 1961, were taken from several sources. Aspects analyzed included the accident scenario, the type of accident, the materials involved, the causes and consequences and the most common accident sequences. The analysis showed that the most frequent causes are external events (31%) and mechanical failure (29%). Storage areas (35%) and process plants (28%) are by far the most common settings for domino accidents. Eighty-nine per cent of the accidents involved flammable materials, the most frequent of which was LPG. The domino effect sequences were analyzed using relative probability event trees. The most frequent sequences were explosion→fire (27.6%), fire→explosion (27.5%) and fire→fire (17.8%). Copyright © 2010 Elsevier B.V. All rights reserved.

  15. Radiological consequences of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.

    2003-01-01

    The reactor accident at unit 4 of the Chernobyl nuclear power plant in Ukraine has deeply affected the living conditions of millions of people. Especially the health consequences have been of public concern up to the present and also been the subject of sometimes absurd claims. The current knowledge on the radiological consequences of the accident is reviewed. Though an increased hazard for some risk groups with high radiation exposure, e.g., liquidators, still cannot be totally excluded for the future, the majority of the population shows no statistically significant indication of radiation-induced illnesses. The contribution of the Research Center Juelich to the assessment of the post-accidental situation and psychological relief of the population is reported. The population groups still requiring special attention include, in particular, children growing up in highly contaminated regions and the liquidators of the years 1986 and 1987 deployed immediately after the accident. (author)

  16. ARAMIS project: A comprehensive methodology for the identification of reference accident scenarios in process industries

    International Nuclear Information System (INIS)

    Delvosalle, Christian; Fievez, Cecile; Pipart, Aurore; Debray, Bruno

    2006-01-01

    In the frame of the Accidental Risk Assessment Methodology for Industries (ARAMIS) project, this paper aims at presenting the work carried out in the part of the project devoted to the definition of accident scenarios. This topic is a key-point in risk assessment and serves as basis for the whole risk quantification. The first result of the work is the building of a methodology for the identification of major accident hazards (MIMAH), which is carried out with the development of generic fault and event trees based on a typology of equipment and substances. The term 'major accidents' must be understood as the worst accidents likely to occur on the equipment, assuming that no safety systems are installed. A second methodology, called methodology for the identification of reference accident scenarios (MIRAS) takes into account the influence of safety systems on both the frequencies and possible consequences of accidents. This methodology leads to identify more realistic accident scenarios. The reference accident scenarios are chosen with the help of a tool called 'risk matrix', crossing the frequency and the consequences of accidents. This paper presents both methodologies and an application on an ethylene oxide storage

  17. List of external hazards to be considered in ASAMPSA-E

    International Nuclear Information System (INIS)

    Decker, Kurt; Brinkman, Hans

    2016-01-01

    The current report includes an exhaustive list of external hazards posing potential threats to nuclear installations. The list comprises of both, natural and man-made external hazards. Also, a cross correlation matrix of the hazards is presented. The list is the starting point for the hazard analysis process in Level 1 PSA as outlined by IAEA (2010; SSG-3) and the definition of design basis as required by WENRA (2014; Reference Levels for Existing Reactors). The list is regarded comprehensive by including all types of hazards that were previously cited in documents by IAEA and WENRA-RHWG. 73 natural hazards (N1 to N73) and 24 man-made external hazards (M1 to M24) are included. Natural hazards are grouped into seismo-tectonic hazards, flooding and hydrological hazards, extreme values of meteorological phenomena, rare meteorological phenomena, biological hazards / infestation, geological hazards, and forest fire. The list of external man-made hazards includes industry accidents, military accidents, transportation accidents, pipeline accidents and other man-made external events. The dataset further contains information on hazard correlations. 577 correlations between individual hazards are identified and shown in a cross-correlation chart. Correlations discriminate between: (1) Causally connected hazards (cause-effect relation) where one hazard (e.g., liquefaction) may be caused by another hazard (e.g., earthquake); or where one hazard (e.g., high wind) is a prerequisite for a correlated hazard (e.g., storm surge). (authors)

  18. Psychological aspects of accident prevention in mines

    Energy Technology Data Exchange (ETDEWEB)

    Lukestikova, M

    1981-04-01

    This paper duscusses ways of preventing work accidents and increasing work safety in underground black coal mines. Specific conditions of underground operations in coal mines are stressed. Elements of work accident prevention are analyzed: reducing hazards by introducing safer technology, automation and mechanization of operations associated with hazards, introducing special measures within the framework of safety engineering. Dependence of accident rate on such factors as personnel training, age, motivation, qualifications, and labor discipline is discussed. Investigations indicate that miner motivation plays a significant role in accident prevention. A high degree of labor motivation successfully reduces accident rate and a low degree of motivation increases accident rate. Role of labor collective in labor motivation as well as a correct system of wage incentives are evaluated. Methods of personnel training aimed at reducing accident rate are described. Role of a technique by which a group of miners attempts to find a solution to a work safety problem by amassing all ideas spontaneously contributed by participants is stressed.

  19. Evaluation of external hazards to nuclear power plants in the United States: Other external events

    International Nuclear Information System (INIS)

    Kimura, C.Y.; Prassinos, P.G.

    1989-02-01

    In support of implementation of the Nuclear Regulatory Commission's Severe Accident Policy, the Lawrence Livermore National Laboratory (LLNL) has performed a study of the risk of core damage to nuclear power plants in the United States due to ''other external events.'' The broad objective has been to gain an understanding of whether ''other external events'' (the hazards not covered by previous reports) are among the major potential accident initiators that may pose a threat of severe reactor core damage or of large radioactive release to the environment from the reactor. The ''other external events'' covered in this report are nearby industrial/military facility accidents, on site hazardous material storage accidents, severe temperature transients, severe weather storms, lightning strikes, external fires, extraterrestrial activity, volcanic activity, earth movement, and abrasive windstorms. The analysis was based on two figures-of-merit, one based on core damage frequency and the other based on the frequency of large radioactive releases. 37 refs., 8 tabs

  20. PSA modeling of long-term accident sequences

    International Nuclear Information System (INIS)

    Georgescu, Gabriel; Corenwinder, Francois; Lanore, Jeanne-Marie

    2014-01-01

    In the context of the extension of PSA scope to include external hazards, in France, both operator (EDF) and IRSN work for the improvement of methods to better take into account in the PSA the accident sequences induced by initiators which affect a whole site containing several nuclear units (reactors, fuel pools,...). These methodological improvements represent an essential prerequisite for the development of external hazards PSA. However, it has to be noted that in French PSA, even before Fukushima, long term accident sequences were taken into account: many insight were therefore used, as complementary information, to enhance the safety level of the plants. IRSN proposed an external events PSA development program. One of the first steps of the program is the development of methods to model in the PSA the long term accident sequences, based on the experience gained. At short term IRSN intends to enhance the modeling of the 'long term' accident sequences induced by the loss of the heat sink or/and the loss of external power supply. The experience gained by IRSN and EDF from the development of several probabilistic studies treating long term accident sequences shows that the simple extension of the mission time of the mitigation systems from 24 hours to longer times is not sufficient to realistically quantify the risk and to obtain a correct ranking of the risk contributions and that treatment of recoveries is also necessary. IRSN intends to develop a generic study which can be used as a general methodology for the assessment of the long term accident sequences, mainly generated by external hazards and their combinations. This first attempt to develop this generic study allowed identifying some aspects, which may be hazard (or combinations of hazards) or related to initial boundary conditions, which should be taken into account for further developments. (authors)

  1. Development of hydrogeological modelling approaches for assessment of consequences of hazardous accidents at nuclear power plants

    International Nuclear Information System (INIS)

    Rumynin, V.G.; Mironenko, V.A.; Konosavsky, P.K.; Pereverzeva, S.A.

    1994-07-01

    This paper introduces some modeling approaches for predicting the influence of hazardous accidents at nuclear reactors on groundwater quality. Possible pathways for radioactive releases from nuclear power plants were considered to conceptualize boundary conditions for solving the subsurface radionuclides transport problems. Some approaches to incorporate physical-and-chemical interactions into transport simulators have been developed. The hydrogeological forecasts were based on numerical and semi-analytical scale-dependent models. They have been applied to assess the possible impact of the nuclear power plants designed in Russia on groundwater reservoirs

  2. Reconfigurable mobile manipulation for accident response

    International Nuclear Information System (INIS)

    Anderson, Robert J.; Morse, William D.; Shirey, David L.; Cdebaca, DanielL M.; Hoffman, John P. Jr.; Lucy, William E.

    2000-01-01

    The need for a telerobotic vehicle with hazard sensing and integral manipulation capabilities has been identified for use in transportation accidents where nuclear weapons are involved. The Accident Response Mobile Manipulation System (ARMMS) platform has been developed to provide remote dexterous manipulation and hazard sensing for the Accident Response Group (ARG) at Sandia National Laboratories. The ARMMS' mobility platform is a military HMMWV [High Mobility Multipurpose Wheeled Vehicle] that is teleoperated over RF or Fiber Optic communication channels. ARMMS is equipped with two high strength Schilling Titan II manipulators and a suite of hazardous gas and radiation sensors. Recently, a modular telerobotic control architecture call SMART (Sandia Modular Architecture for Robotic and Teleoperation) has been applied to ARMMS. SMART enables input devices and many system behaviors to be rapidly configured in the field for specific mission needs. This paper summarizes current SMART developments applied to ARMMS

  3. 40 CFR 68.42 - Five-year accident history.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Five-year accident history. 68.42... (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Hazard Assessment § 68.42 Five-year accident history. (a) The owner or operator shall include in the five-year accident history all accidental releases from...

  4. Hazard evaluation of The International Fusion Materials Irradiation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Burgazzi, Luciano [ENEA-Centro Ricerche ' Ezio Clementel' , Advanced Physics Technology Division, Via Martiri di Monte Sole, 4, 40129 Bologna (Italy)]. E-mail: burgazzi@bologna.enea.it

    2005-01-15

    The International Fusion Materials Irradiation Facility (IFMIF) is aimed to provide an intense neutron source by a high current deuteron linear accelerator and a high-speed lithium flow target, for testing candidate materials for fusion. Liquid lithium is being circulated through a loop and is kept at a temperature above its freezing point. In the frame of the design phase called Key Element technology Phase (KEP), jointly performed by an international team to verify the most important risk factors, safety assessment of the whole plant has been required in order to identify the hazards associated with the plant operation. This paper discusses the safety assessments that were performed and their outcome: Failure Mode and Effect Analysis (FMEA) approach has been adopted in order to accomplish the task. Main conclusions of the study is that, on account of the safety and preventive measures adopted, potential plant related hazards are confined within the IFMIF security boundaries and great care must be exercised to protect workers and site personnel from operating the plant. The analysis has provided as a result a set of Postulated Initiating Events (PIEs), that is off-normal events, that could result in hazardous consequences for the plant, together with the total frequency and the list of component failures which could induce the PIE: this assures the exhaustive list of major initiating events of accident sequences, helpful to the further accident sequence analysis phase. Finally, for each one of the individuated PIEs, the evaluation of the accident evolution, in terms of effects on the plant and relative countermeasures, has allowed to verify that adequate measures are being taken both to prevent the accident occurrence and to cope with the accident consequences, thus assuring the fulfilment of the safety requirements.

  5. ROAD ACCIDENT AND SAFETY STUDY IN SYLHET REGION OF BANGLADESH

    Directory of Open Access Journals (Sweden)

    B. K. BANIK

    2011-08-01

    Full Text Available Roads, highways and streets are fundamental infrastructure facilities to provide the transportation for passenger travel and goods movement from one place to another in Sylhet, north–eastern division of Bangladesh with rapid growth of road vehicle, being comparatively developed economic tourist prone area faces severe road traffic accident. Such severe road accidents cause harsh safety hazards on the roads of Sylhet area. This research work presents an overview of the road traffic accident and degraded road safety situation in Sylhet zone which in particular, discusses the key road accident problem characteristics identifying the hazardous roads and spots, most responsible vehicles and related components, conditions of drivers and pedestrians, most victims of accident, effects of accident on society, safety priorities and options available in Sylhet. In this regard, a comprehensive questionnaire survey was conducted on the concerned groups of transportation and detailed accident data was collected from a popular local newspaper. Analysis of the study reveals that Dhaka- Sylhet highway is the most hazardous in road basis and Sylhet Sador thana is the most vulnerable in thana basis in Sylhet region.

  6. Report by the Delegate for major risks for 2010

    International Nuclear Information System (INIS)

    Michel, Laurent

    2011-01-01

    The first part of this report comments the major natural and industrial disasters which occurred in 2010 in France (Xynthia tempest, flooding, and forest fires) and in other countries. It also proposes some lessons from these disasters. The second part discusses the evolution towards a resilient society by a combined approach of sustainable development, of cultural good safeguarding, and person protection. It also discusses a prospective approach regarding natural hazards and technological accidents, adapted procedures, governance and land planning, the evolution of information and alarm systems, and emerging risks. The third part addresses the adaptation to natural hazards: frameworks and strategies, actions (regulatory prevention, flooding management, safety of hydraulic works, seismic plan). It assesses the financial and budgetary means brought by the State and its partners, and discusses some perspectives. It addresses the technological risks: legal and regulatory evolutions, safety of hazardous industrial installations, consequences of technological accidents. The next part deals with the control of civilian nuclear installations by the ASN. The last part presents the different involved structures and authorities

  7. Risk management: Role of societal factors in major industrial accidents

    International Nuclear Information System (INIS)

    Hovden, J.; Rausand, M.; Sergeev, G.

    1995-01-01

    The paper discusses factors influencing the occurrence of major accidents in complex technological systems. Societal factors are identified as most significant in this context. Important types of societal factors are pin-pointed and discussed. The safety situation in the former Soviet Union and in today's Russian is described. The calamities at Chernobyl, Three Mile Island, and partly also Bhopal are discussed, and the role of societal factors identified. A main point of view is that it is not surprising that these catastrophes happened in the then existing conditions. What is surprising is that they did not happen earlier exclamation point

  8. Emotional stress and traffic accidents: the impact of separation and divorce.

    Science.gov (United States)

    Lagarde, Emmanuel; Chastang, Jean-François; Gueguen, Alice; Coeuret-Pellicer, Mireille; Chiron, Mireille; Lafont, Sylviane

    2004-11-01

    Personal responses to stressful life events are suspected of increasing the risk of serious traffic accidents. We analyzed data from a French cohort study (the GAZEL cohort), including a retrospective driving behavior questionnaire, from 13,915 participants (10,542 men age 52-62 years and 3373 women age 47-62 years in 2001). Follow-up data covered 1993-2000. Hazard ratios for serious accidents (n = 713) were computed by Cox's proportional hazard regression with time-dependent covariates. Separate analyses were also performed to consider only at-fault accidents. Marital separation or divorce was associated with an increased risk of a serious accident (all serious accidents: hazard ratio 2.9, 95% confidence interval = 1.7-5.0; at-fault accidents: 4.4, 2.3-8.3). The impact of separation and divorce did not differ according to alcohol consumption levels. Other life events associated with increased risk of serious accident were a child leaving home (all accidents: 1.2, 0.97-1.6; at-fault accidents: 1.5, 1.1-2.1), an important purchase (all accidents: 1.4, 1.1-1.7; at-fault accidents: 1.6, 1.2-2.1), and hospitalization of the partner (all accidents: 1.4, 1.1-2.0). This study suggests that recent separation and divorce are associated with an increase in serious traffic accidents.

  9. Application of systems and control theory-based hazard analysis to radiation oncology.

    Science.gov (United States)

    Pawlicki, Todd; Samost, Aubrey; Brown, Derek W; Manger, Ryan P; Kim, Gwe-Ya; Leveson, Nancy G

    2016-03-01

    Both humans and software are notoriously challenging to account for in traditional hazard analysis models. The purpose of this work is to investigate and demonstrate the application of a new, extended accident causality model, called systems theoretic accident model and processes (STAMP), to radiation oncology. Specifically, a hazard analysis technique based on STAMP, system-theoretic process analysis (STPA), is used to perform a hazard analysis. The STPA procedure starts with the definition of high-level accidents for radiation oncology at the medical center and the hazards leading to those accidents. From there, the hierarchical safety control structure of the radiation oncology clinic is modeled, i.e., the controls that are used to prevent accidents and provide effective treatment. Using STPA, unsafe control actions (behaviors) are identified that can lead to the hazards as well as causal scenarios that can lead to the identified unsafe control. This information can be used to eliminate or mitigate potential hazards. The STPA procedure is demonstrated on a new online adaptive cranial radiosurgery procedure that omits the CT simulation step and uses CBCT for localization, planning, and surface imaging system during treatment. The STPA procedure generated a comprehensive set of causal scenarios that are traced back to system hazards and accidents. Ten control loops were created for the new SRS procedure, which covered the areas of hospital and department management, treatment design and delivery, and vendor service. Eighty three unsafe control actions were identified as well as 472 causal scenarios that could lead to those unsafe control actions. STPA provides a method for understanding the role of management decisions and hospital operations on system safety and generating process design requirements to prevent hazards and accidents. The interaction of people, hardware, and software is highlighted. The method of STPA produces results that can be used to improve

  10. Seveso II directive in prevention and mitigation of consequences of chemical terrorism, safety management systems in hazardous installations

    International Nuclear Information System (INIS)

    Klicek, M.

    2009-01-01

    Mayor accidents caused by hazardous substances are great threat to public. The consequences are often very severe with great number of injured people or even deaths and a great material damage. Statistic data shows that the main cause of accidents in hazardous installations is 'human factor', including the possibility of terrorist attack, or classic military operations. In order to ensure effective chemical safety, the actions should be taken by industry, public authorities, communities and other stake holders to prevent industrial accidents. Safety should be an integral part of the business activities of an enterprise, and all hazardous installations should strive to reach the ultimate goal of zero incidents. Safety management systems (SMS) should include appropriate technology and processes, as well as establishing an effective organisational structure. To mitigate consequences of accidents, emergency planning, land-use planning and risk communication is necessary. Adequate response in the event of accident should limit adverse consequences to health, environment and property. Follow-up actions are needed to learn from the accidents and other unexpected events, in order to reduce future incidents. In this paper the author will discus the implementing of SEVESO II directive in obtaining two main goals: major accident prevention and mitigation of consequences for men and environment in case of possible terrorist actions or military activities. Some Croatian experiences in implementing of UNEP APELL Programme, and its connection with SEVESO II directive will be shown.(author)

  11. PREVENTION OF OCCUPATIONAL ACCIDENTS

    Directory of Open Access Journals (Sweden)

    Jovica Jovanovic

    2004-01-01

    Full Text Available Medical services, physicians and nurses play an essential role in the plant safety program through primary treatment of injured workers and by helping to identify workplace hazards. The physician and nurse should participate in the worksite investigations to identify specific hazard or stresses potentially causing the occupational accidents and injuries and in planning the subsequent hazard control program. Physicians and nurses must work closely and cooperatively with supervisors to ensure the prompt reporting and treatment of all work related health and safety problems. Occupational accidents, work related injuries and fatalities result from multiple causes, affect different segments of the working population, and occur in a myriad of occupations and industrial settings. Multiple factors and risks contribute to traumatic injuries, such as hazardous exposures, workplace and process design, work organization and environment, economics, and other social factors. With such a diversity of theories, it will not be difficult to understand that there does not exist one single theory that is considered right or correct and is universally accepted. These theories are nonetheless necessary, but not sufficient, for developing a frame of reference for understanding accident occurrences. Prevention strategies are also varied, and multiple strategies may be applicable to many settings, including engineering controls, protective equipment and technologies, management commitment to and investment in safety, regulatory controls, and education and training. Research needs are thus broad, and the development and application of interventions involve many disciplines and organizations.

  12. Key Characteristics of Combined Accident including TLOFW accident for PSA Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bo Gyung; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [Khalifa University of Science, Technology and Research, Abu Dhabi (United Arab Emirates)

    2015-05-15

    The conventional PSA techniques cannot adequately evaluate all events. The conventional PSA models usually focus on single internal events such as DBAs, the external hazards such as fire, seismic. However, the Fukushima accident of Japan in 2011 reveals that very rare event is necessary to be considered in the PSA model to prevent the radioactive release to environment caused by poor treatment based on lack of the information, and to improve the emergency operation procedure. Especially, the results from PSA can be used to decision making for regulators. Moreover, designers can consider the weakness of plant safety based on the quantified results and understand accident sequence based on human actions and system availability. This study is for PSA modeling of combined accidents including total loss of feedwater (TLOFW) accident. The TLOFW accident is a representative accident involving the failure of cooling through secondary side. If the amount of heat transfer is not enough due to the failure of secondary side, the heat will be accumulated to the primary side by continuous core decay heat. Transients with loss of feedwater include total loss of feedwater accident, loss of condenser vacuum accident, and closure of all MSIVs. When residual heat removal by the secondary side is terminated, the safety injection into the RCS with direct primary depressurization would provide alternative heat removal. This operation is called feed and bleed (F and B) operation. Combined accidents including TLOFW accident are very rare event and partially considered in conventional PSA model. Since the necessity of F and B operation is related to plant conditions, the PSA modeling for combined accidents including TLOFW accident is necessary to identify the design and operational vulnerabilities.The PSA is significant to assess the risk of NPPs, and to identify the design and operational vulnerabilities. Even though the combined accident is very rare event, the consequence of combined

  13. The Radiological Accident in Lia, Georgia

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-12-15

    The use of radioactive material offers a wide range of benefits to medicine, research and industry throughout the world. Precautions are necessary, however, to limit the exposure of people to the radiation emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy or industrial radiography sources, great care is required to prevent accidents which could have severe consequences. Nevertheless, in spite of the precautions taken, serious accidents involving radiation sources continue to occur, albeit infrequently. The IAEA conducts follow-up reviews of such serious accidents to provide an account of their circumstances and consequences, from which organizations with responsibilities for radiation protection, safety of sources and emergency preparedness and response may learn. A serious radiological accident occurred in Georgia on 2 December 2001, when three inhabitants of the village of Lia found two metal objects in the forest while collecting firewood. These objects were {sup 90}Sr sources with an activity of 1295 TBq. The three inhabitants used the objects as heaters when spending the night in the forest. The major cause of the accident was the improper and unauthorized abandonment of radiation sources in Georgia and the absence of clear labels or radiation signs on the sources warning of the potential radiation hazard. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), the Georgian authorities requested assistance from the IAEA to advise on the dose assessment, source recovery and medical management of those involved in the accident. This publication describes the circumstances and events surrounding the accident, its management and the medical treatment of the people exposed. It also describes the dose reconstruction calculations and biodosimetry assessments conducted. A number of uncertainties remain relating to some details of the accident. However

  14. The Radiological Accident in Lia, Georgia

    International Nuclear Information System (INIS)

    2014-12-01

    The use of radioactive material offers a wide range of benefits to medicine, research and industry throughout the world. Precautions are necessary, however, to limit the exposure of people to the radiation emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy or industrial radiography sources, great care is required to prevent accidents which could have severe consequences. Nevertheless, in spite of the precautions taken, serious accidents involving radiation sources continue to occur, albeit infrequently. The IAEA conducts follow-up reviews of such serious accidents to provide an account of their circumstances and consequences, from which organizations with responsibilities for radiation protection, safety of sources and emergency preparedness and response may learn. A serious radiological accident occurred in Georgia on 2 December 2001, when three inhabitants of the village of Lia found two metal objects in the forest while collecting firewood. These objects were 90 Sr sources with an activity of 1295 TBq. The three inhabitants used the objects as heaters when spending the night in the forest. The major cause of the accident was the improper and unauthorized abandonment of radiation sources in Georgia and the absence of clear labels or radiation signs on the sources warning of the potential radiation hazard. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), the Georgian authorities requested assistance from the IAEA to advise on the dose assessment, source recovery and medical management of those involved in the accident. This publication describes the circumstances and events surrounding the accident, its management and the medical treatment of the people exposed. It also describes the dose reconstruction calculations and biodosimetry assessments conducted. A number of uncertainties remain relating to some details of the accident. However, sufficient

  15. Evaluation of external hazards to nuclear power plants in the United States

    International Nuclear Information System (INIS)

    Kimura, C.Y.; Budnitz, R.J.

    1987-12-01

    The Lawrence Livermore National Laboratory (LLNL) has performed a study of the risk of core damage to nuclear power plants in the United States due to externally initiated events. The broad objective has been to gain an understanding of whether or not each external initiator is among the major potential accident initiators that may pose a threat of severe reactor core damage or of large radioactive release to the environment from the reactor. Four external hazards were investigated in this report. These external hazards are internal fires, high winds/tornadoes, external floods, and transportation accidents. Analysis was based on two figures-of-merit, one based on core damage frequency and the other based on the frequency of large radioactive releases. Using these two figures-of-merit as evaluation criteria, it has been feasible to ascertain whether the risk from externally initiated accidents is, or is not, an important contributor to overall risk for the US nuclear power plants studied. This has been accomplished for each initiator separately. 208 refs., 17 figs., 45 tabs

  16. The Chernobyl accident

    International Nuclear Information System (INIS)

    Berg, J.O.; Christensen, G.; Lingjaerde, R.; Smidt Olsen, H.; Wethe, P.I.

    1986-10-01

    In connection with the Chernobyl accident the report gives a description of the technical features of importance to the accident, the course of events, and the estimated health hazards in the local environment. Dissimilarities in western and Sovjet reactor safety philosophy are dealt with, as well as conceivable concequences in relation to technology and research in western nuclear power programmes. Results of activity level measurements of air and foodstuff, made in Norway by Institute for Energy Technology, are given

  17. Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

    International Nuclear Information System (INIS)

    McKenna, T.J.; Martin, J.A. Jr.; Giitter, J.G.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Watkins

    1987-02-01

    Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

  18. Accidents on vessels transporting liquid gases and responder's concerns : the Galerne Project

    International Nuclear Information System (INIS)

    Cabioc'h, F.; De Castelet, D.; Penelon, T.; Pagnon, S.; Peuch, A.; Bonnardot, F.; Duhart, J.; Drevet, D.; Estiez, C.; Dernat, M.; Hermand, J.C.

    2009-01-01

    In 2006, the French Ministry of Research financed the Galerne project to provide responders at sea with relevant information on the hazards posed by liquid gas chemicals on vessels disabled at sea. Thirty-one chemicals are transported as liquids in order to facilitate handling and lower transport costs. Temperature and pressure parameters are manipulated in order to generate the liquefaction of the gases. Members of the Galerne project are producers and handlers of liquefied gases and are experts in atmospheric modelling, ship structure, risk assessment, hazards assessment and operations. Several simulations and experiments were performed in an effort to produce operational information for responders and headquarters. For practical and financial reasons, it was not possible to consider all 31 chemicals described in the IGC code. Only 4 liquid gases were chosen for the Galerne project, notably methane liquefied natural gas (LNG); propane LNG; ammonia; and vinyl chloride monomer (VCM). They were chosen on the basis of their transport characteristics and behaviour. This paper outlined the physical characteristics of the transported products verses their volume in standard conditions; the type of ship dedicated to transporting gases in liquid forms; and various response phases. It also included a brief review of several ship incidents and accidents. It was concluded that as far as the LNG carriers are concerns, a few accidents at sea have occurred in more than 28 years, but no major accidents involving the cargo have been reported. Handling LNG at terminals can lead to serious accidents. Accidents have occurred at sea, but without any accidental spillage of cargo. It was concluded that response teams on-board disabled liquefied gas carriers need to know the main characteristics of the cargo and the potential hazards. 3 tabs., 6 figs

  19. Decision support systems for major accident prevention in the chemical process industry : A developers' survey

    NARCIS (Netherlands)

    Reniers, Genserik L L; Ale, B. J.M.; Dullaert, W.; Foubert, B.

    2006-01-01

    Solid major accident prevention management is characterized by efficient and effective risk assessments. As a means of addressing the efficiency aspect, decision support analysis software is becoming increasingly available. This paper discusses the results of a survey of decision support tools for

  20. Phebus FP. An international severe accident research programme

    International Nuclear Information System (INIS)

    Hardt, P.; Tattegrain, A.

    1995-01-01

    The main hazard during a hypothetical severe nuclear reactor accident resides in its fission product (FP) inventory. For this reason, the behaviour of FPs has been extensively studied, with the aim of determining the potential source to the environment. The Phebus FP programme proposes a novel, integral approach to this research. After 5 years of construction and of analytical preparation the Phebus FP programme has been supplying a large volume of new experimental data. Their processing by code calculations is presently a major challenge to all partners. The intense collaboration of 25 organizations from 15 countries has proven to be a major asset of Phebus FP. (author). 6 refs., 2 figs

  1. Hazard classification criteria for non-nuclear facilities

    International Nuclear Information System (INIS)

    Mahn, J.A.; Walker, S.A.

    1997-01-01

    Sandia National Laboratories' Integrated Risk Management Department has developed a process for establishing the appropriate hazard classification of a new facility or operation, and thus the level of rigor required for the associated authorization basis safety documentation. This process is referred to as the Preliminary Hazard Screen. DOE Order 5481.1B contains the following hazard classification for non-nuclear facilities: high--having the potential for onsite or offsite impacts to large numbers of persons or for major impacts to the environment; moderate--having the potential for considerable onsite impacts but only minor offsite impacts to people or the environment; low--having the potential for only minor onsite and negligible offsite impacts to people or the environment. It is apparent that the application of such generic criteria is more than likely to be fraught with subjective judgment. One way to remove the subjectivity is to define health and safety classification thresholds for specific hazards that are based on the magnitude of the hazard, rather than on a qualitative assessment of possible accident consequences. This paper presents the results of such an approach to establishing a readily usable set of non-nuclear facility hazard classifications

  2. Determining cutoff distances for assessing risks from transportation accident radiation releases

    International Nuclear Information System (INIS)

    Sandquist, G.M.; Slaughter, D.M.; Kimura, C.Y.; Brumburgh, G.

    1995-01-01

    The transportation of radioactive materials throughout the United States and the world is a ubiquitous and sometimes controversial activity. Almost universally, these transportation activities have been performed without major incident, and the safety record for transportation of radioactive material is outstanding compared with the transportation of other hazardous materials. Nevertheless, concerns still exist regarding adequate regulation of radioactive material transportation and accurate assessment of the health risks associated with accidents. These concerns are addressed through certification by the cognizant regulatory authority over the transportation container or the performance of a transportation risk assessment. In a transportation risk assessment, accident situations are examined, frequencies are estimated, and consequences resulting from the accident are analyzed and evaluated for acceptance. A universal question with any transportation risk assessment that examines the radiological consequences from release accidents is, At what distance may the dispersion analysis be terminated? This paper examines cutoff distances and their consequences for assessing health risks from radiological transportation releases

  3. Natural phenomena risk analysis - an approach for the tritium facilities 5480.23 SAR natural phenomena hazards accident analysis

    International Nuclear Information System (INIS)

    Cappucci, A.J. Jr.; Joshi, J.R.; Long, T.A.; Taylor, R.P.

    1997-01-01

    A Tritium Facilities (TF) Safety Analysis Report (SAR) has been developed which is compliant with DOE Order 5480.23. The 5480.23 SAR upgrades and integrates the safety documentation for the TF into a single SAR for all of the tritium processing buildings. As part of the TF SAR effort, natural phenomena hazards (NPH) were analyzed. A cost effective strategy was developed using a team approach to take advantage of limited resources and budgets. During development of the Hazard and Accident Analysis for the 5480.23 SAR, a strategy was required to allow maximum use of existing analysis and to develop a cost effective graded approach for any new analysis in identifying and analyzing the bounding accidents for the TF. This approach was used to effectively identify and analyze NPH for the TF. The first part of the strategy consisted of evaluating the current SAR for the RTF to determine what NPH analysis could be used in the new combined 5480.23 SAR. The second part was to develop a method for identifying and analyzing NPH events for the older facilities which took advantage of engineering judgment, was cost effective, and followed a graded approach. The second part was especially challenging because of the lack of documented existing analysis considered adequate for the 5480.23 SAR and a limited budget for SAR development and preparation. This paper addresses the strategy for the older facilities

  4. Historical evolution of process safety and major-accident hazards prevention in Spain. Contribution of the pioneer Joaquim Casal.

    OpenAIRE

    Planas Cuchi, Eulàlia; Arnaldos Viger, Josep; Darbra Roman, Rosa Maria; Muñoz Messineo, Miguel Ángel; Pastor Ferrer, Elsa; Vílchez Sánchez, Juan Antonio

    2013-01-01

    This paper aims at presenting the evolution of process safety in Spain from various points of view. In first place, a study of the accidents occurred in this country in the process industry and in the transportation of chemical substances is presented. After this, the starting point of the process safety research in Spain and its evolution during the years are explained. The importance of this topic has also been reflected in the chemical engineering studies in some Spanish universities. Ther...

  5. Medical care of radiation accidents

    International Nuclear Information System (INIS)

    Nakao, Isamu

    1986-02-01

    This monograph, divided into six chapters, focuses on basic knowledge and medical strategies for radiation accidents. Chapters I to V deal with practice in emergency care for radiation exposure, covering 1) medical strategies for radiation accidents, 2) personnel dosimetry and monitoring, 3) nuclear facilities and their surrounding areas with the potential for creating radiation accidents, and emergency medical care for exposed persons, 4) emergency care procedures for radiation exposure and radioactive contamination, and 5) radiation hazards and their treatment. The last chapter provides some references. (Namekawa, K.)

  6. Accident Analysis and Highway Safety

    Directory of Open Access Journals (Sweden)

    Omar Noorliyana

    2017-01-01

    Full Text Available Since 2010, Federal Route FT050 (Jalan Batu Pahat-Kluang has undergone many changes, including the improvement of geometric features (i.e., construction of median, dedicated U-turns and additional lanes and upgrading the quality of the road surface. Unfortunately, even with these enhancements, accidents continue to occur along this route. This study covered both accident analysis and blackspot study. Accident point weightage was used to identify blackspot locations. The results reveal hazardous road locations and blackspot ranking along the route.

  7. Evaluation of severe accident risks: Quantification of major input parameters: MAACS [MELCOR Accident Consequence Code System] input

    International Nuclear Information System (INIS)

    Sprung, J.L.; Jow, H-N; Rollstin, J.A.; Helton, J.C.

    1990-12-01

    Estimation of offsite accident consequences is the customary final step in a probabilistic assessment of the risks of severe nuclear reactor accidents. Recently, the Nuclear Regulatory Commission reassessed the risks of severe accidents at five US power reactors (NUREG-1150). Offsite accident consequences for NUREG-1150 source terms were estimated using the MELCOR Accident Consequence Code System (MACCS). Before these calculations were performed, most MACCS input parameters were reviewed, and for each parameter reviewed, a best-estimate value was recommended. This report presents the results of these reviews. Specifically, recommended values and the basis for their selection are presented for MACCS atmospheric and biospheric transport, emergency response, food pathway, and economic input parameters. Dose conversion factors and health effect parameters are not reviewed in this report. 134 refs., 15 figs., 110 tabs

  8. Assessment and comparison of two early warning indicator methods in the perspective of prevention of atypical accident scenarios

    International Nuclear Information System (INIS)

    Paltrinieri, Nicola; Øien, Knut; Cozzani, Valerio

    2012-01-01

    Some severe major accidents occurred in Europe in recent years (e.g. the Vapour Cloud Explosion at Buncefield in 2005), which were not foreseen by their site “Seveso-II” safety reports. Detailed analyses of such “atypical” scenarios demonstrated that they are the result of a number of failures at different technical and organizational levels. Thus, their prevention is a major challenge and must be coordinated through different kinds of approaches, among which improved early detection plays an important role. Proactive methodologies for the development of early warning indicators can unveil early deviations in the causal chain. Two examples are the Resilience-based Early Warning Indicator (REWI) method and the so-called “Dual Assurance” method. The aim of this study was to analyse the possible integration of early warning indicators in the hazard identification process. A Buncefield-like site was analysed to obtain indicators that were compared with the actual causes that led to the accident at Buncefield (and to similar accident scenarios). The results show that indicators from both methods could have prevented the accidents from happening. However, one main difference is related to the issue of hazard identification, which is fundamental for the prevention of atypical accident scenarios. The REWI method is not dependent on the outcome of the hazard identification process. Instead it provides complementarities to the first prevention approach (improved identification of atypical scenarios), demonstrating that a mutual activity would be an effective strategy in which human, organizational, cultural and technical factors are treated in an integrated manner. - Highlights: ► Early warning indicators were created through 2 methods for the Buncefield oil depot. ► A general capacity to cover causes of atypical events was demonstrated. ► The Dual Assurance method showed to mainly cover operability failures. ► The REWI method showed to promote acts

  9. 49 CFR 195.52 - Telephonic notice of certain accidents.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Telephonic notice of certain accidents. 195.52... TRANSPORTATION OF HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.52 Telephonic notice of certain accidents. (a) At the earliest practicable moment following discovery of a...

  10. Recent severe accident research synthesis of the major outcomes from the SARNET network

    Energy Technology Data Exchange (ETDEWEB)

    Van Dorsselaere, J.-P., E-mail: jean-pierre.van-dorsselaere@irsn.fr [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-lez-Durance (France); Auvinen, A. [VTT Technical Research Centre, Espoo (Finland); Beraha, D. [Gesellschaft für Anlagen- und Reaktorsicherheit mbH (GRS), Köln (Germany); Chatelard, P. [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-lez-Durance (France); Herranz, L.E. [Centro de Investigaciones Energéticas MedioAmbientales y Tecnológicas (CIEMAT), Madrid (Spain); Journeau, C. [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), Paris (France); Klein-Hessling, W. [Gesellschaft für Anlagen- und Reaktorsicherheit mbH (GRS), Köln (Germany); Kljenak, I. [Jozef Stefan Institute (JSI), Ljubljana (Slovenia); Miassoedov, A. [Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Paci, S. [University of Pisa, Pisa (Italy); Zeyen, R. [European Commission Joint Research Centre, Institute for Energy (JRC/IET), Petten (Netherlands)

    2015-09-15

    Highlights: • SARNET network of excellence integration mid-2013 in the NUGENIA Association. • Progress of knowledge on corium behaviour, hydrogen explosion and source term. • Further development of ASTEC integral code to capitalize knowledge. • Ranking of next R&D high priority issues accounting for international research. • Dissemination of knowledge through education courses and ERMSAR conferences. - Abstract: The SARNET network (Severe Accident Research NETwork of excellence), co-funded by the European Commission from 2004 to 2013, has allowed to significantly improve the knowledge on severe accidents and to disseminate it through courses and ERMSAR conferences. The major investigated topics, involving more than 250 researchers from 22 countries, were in- and ex-vessel corium/debris coolability, molten-core–concrete-interaction, steam explosion, hydrogen combustion and mitigation in containment, impact of oxidising conditions on source term, and iodine chemistry. The ranking of the high priority issues was updated to account for the results of recent international research and for the impact of Fukushima nuclear accidents in Japan. In addition, the ASTEC integral code was further developed to capitalize the new knowledge. The network has reached self-sustainability by integration in mid-2013 into the NUGENIA Association. The main activities and outcomes of the network are presented.

  11. Recent severe accident research synthesis of the major outcomes from the SARNET network

    International Nuclear Information System (INIS)

    Van Dorsselaere, J.-P.; Auvinen, A.; Beraha, D.; Chatelard, P.; Herranz, L.E.; Journeau, C.; Klein-Hessling, W.; Kljenak, I.; Miassoedov, A.; Paci, S.; Zeyen, R.

    2015-01-01

    Highlights: • SARNET network of excellence integration mid-2013 in the NUGENIA Association. • Progress of knowledge on corium behaviour, hydrogen explosion and source term. • Further development of ASTEC integral code to capitalize knowledge. • Ranking of next R&D high priority issues accounting for international research. • Dissemination of knowledge through education courses and ERMSAR conferences. - Abstract: The SARNET network (Severe Accident Research NETwork of excellence), co-funded by the European Commission from 2004 to 2013, has allowed to significantly improve the knowledge on severe accidents and to disseminate it through courses and ERMSAR conferences. The major investigated topics, involving more than 250 researchers from 22 countries, were in- and ex-vessel corium/debris coolability, molten-core–concrete-interaction, steam explosion, hydrogen combustion and mitigation in containment, impact of oxidising conditions on source term, and iodine chemistry. The ranking of the high priority issues was updated to account for the results of recent international research and for the impact of Fukushima nuclear accidents in Japan. In addition, the ASTEC integral code was further developed to capitalize the new knowledge. The network has reached self-sustainability by integration in mid-2013 into the NUGENIA Association. The main activities and outcomes of the network are presented

  12. TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

    International Nuclear Information System (INIS)

    KRIPPS, L.J.

    2006-01-01

    This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls

  13. The development of an inherent safety approach to the prevention of domino accidents.

    Science.gov (United States)

    Cozzani, Valerio; Tugnoli, Alessandro; Salzano, Ernesto

    2009-11-01

    The severity of industrial accidents in which a domino effect takes place is well known in the chemical and process industry. The application of an inherent safety approach for the prevention of escalation events leading to domino accidents was explored in the present study. Reference primary scenarios were analyzed and escalation vectors were defined. Inherent safety distances were defined and proposed as a metric to express the intensity of the escalation vectors. Simple rules of thumb were presented for a preliminary screening of these distances. Swift reference indices for layout screening with respect to escalation hazard were also defined. Two case studies derived from existing layouts of oil refineries were selected to understand the potentialities coming from the application in the methodology. The results evidenced that the approach allows a first comparative assessment of the actual domino hazard in a layout, and the identification of critical primary units with respect to escalation events. The methodology developed also represents a useful screening tool to identify were to dedicate major efforts in the design of add-on measures, optimizing conventional passive and active measures for the prevention of severe domino accidents.

  14. Relative consequences of transporting hazardous materials

    International Nuclear Information System (INIS)

    Fullwood, R.R.; Rhyne, W.R.; Simmons, J.A.; Reese, R.T.

    1980-01-01

    The objective of this paper is to discuss methods under study at Transportation Technology Center to develop a perspective on how technical measures of hazard and risk relate to perception of hazards, harm, and risks associated with transporting hazardous materials. This paper is concerned with two major aspects of the relative hazards problem. The first aspect is the analyses of the possible effects associated with exposure to hazardous materials as contained in the following two parts: outlines of possible problems and controversies that could be encountered in the evaluation and comparisons of hazards and risks; and description of the various measures of harm (hazards or dangers) and subsequent comparisons thereof. The second aspect of this paper leads into a presentation of the results of a study which had the following purposes: to develop analytical techniques for a consistent treatment of the phenomenology of the consequences of a release of hazardous materials; to reduce the number of variables in the consequence analyses by development of transportation accident scenarios which have the same meteorological conditions, demography, traffic and population densities, geographical features and other appropriate conditions and to develop consistent methods for presenting the results of studies and analyses that describe the phenomenology and compare hazards. The results of the study are intended to provide a bridge between analytical certainty and perception of the hazards involved. Understanding the differences in perception of hazards resulting from transport of various hazardous materials is fraught with difficulties in isolating the qualitative and quantitative features of the problem. By relating the quantitative impacts of material hazards under identical conditions, it is hoped that the perceived differences in material hazards can be delineated and evaluated

  15. An approach for estimating the radiological significance of a hypothetical major nuclear accident over long distance transboundary scales

    Energy Technology Data Exchange (ETDEWEB)

    Mitrakos, D., E-mail: dimitris.mitrakos@eeae.gr; Potiriadis, C.; Housiadas, C.

    2016-04-15

    Highlights: • Actions may be warranted after a major nuclear accident even at long distances. • Distance may not be the decisive parameter for longer term radiological impact. • Remote impact may vary orders of magnitude depending on the meteorological conditions. • The potential impact can be assessed using computationally inexpensive calculations. - Abstract: After the Fukushima accident important initiatives were taken in European level to enhance the nuclear safety level of the existing and planned nuclear reactors, such as the so-called nuclear “stress-tests” and the amendment of the Nuclear Safety Directive. A recent work of HERCA and WENRA focused on the need for a more consistent and harmonized response in a transboundary context in case of a hypothetical major nuclear accident in Europe. Such an accident, although very improbable, cannot be totally excluded and so, should be considered in emergency preparedness arrangements among the various European countries. In case of a hypothetical severe Fukushima-like accident in Europe, the role of the neighboring countries may be important, since the authorities should be able to provide information and advice to the government and the public, but also can contribute to the overall assessment of the situation be their own means. In this work we assess the radiological significance of a hypothetical major nuclear accident for distances longer than 300 km that are not typically covered by the internationally accepted emergency planning zones. The approach is simple and computationally inexpensive, since it is based on the calculation of only a few release scenarios at dates selected within a whole year on the basis of bounding the deposition levels at long distances in relation to the occurrence of precipitation. From the calculated results it is evident that distance is not the only decisive parameter in estimating the potential radiological significance of a severe nuclear accident. The hypothetical

  16. Application of a hazard and operability study method to hazard evaluation of a chemical unit of the power station.

    Science.gov (United States)

    Habibi, E; Zare, M; Barkhordari, A; Mirmohammadi, Sj; Halvani, Ghh

    2008-12-28

    The aim of this study was to identify the hazards, evaluate their risk factors and determine the measure for promotion of the process and reduction of accidents in the chemical unit of the power station. In this case and qualitative study, HAZOP technique was used to recognize the hazards and problems of operations on the chemical section at power station. Totally, 126 deviations were documented with various causes and consequences. Ranking and evaluation of identified risks indicate that the majority of deviations were categorized as "acceptable" and less than half of that were "unacceptable". The highest calculated risk level (1B) related to both the interruption of acid entry to the discharge pumps and an increased density of the acid. About 27% of the deviations had the lowest risk level (4B). The identification of hazards by HAZOP indicates that it could, systemically, assess and criticize the process of consumption or production of acid and alkali in the chemical unit of power plant.

  17. 40 CFR 68.50 - Hazard review.

    Science.gov (United States)

    2010-07-01

    ... Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 2 Prevention Program § 68.50 Hazard review. (a) The owner or operator shall conduct a review of the hazards associated with the regulated substances, process, and...

  18. Accidents on vessels transporting liquid gases and responder's concerns : the Galerne Project

    Energy Technology Data Exchange (ETDEWEB)

    Cabioc' h, F. [Centre de Documentation, de Recherche et d' Experimentations, Brest (France); De Castelet, D. [Veritas, Paris (France); Penelon, T.; Pagnon, S. [Ineris, Verneuil en Halatte (France); Peuch, A.; Bonnardot, F. [Meteo France, Toulouse (France); Duhart, J. [GdF-Suez, Paris (France); Drevet, D. [French Ministry of Transport, Paris (France). Sea Accident Investigation Bureau; Cerutti, C. [French Navy, Brest (France); Estiez, C. [French Civil Security, Paris (France); Dernat, M. [Total Gaz and New Energy, Paris (France); Hermand, J.C. [Total PetroChemicals, Paris (France)

    2009-07-01

    In 2006, the French Ministry of Research financed the Galerne project to provide responders at sea with relevant information on the hazards posed by liquid gas chemicals on vessels disabled at sea. Thirty-one chemicals are transported as liquids in order to facilitate handling and lower transport costs. Temperature and pressure parameters are manipulated in order to generate the liquefaction of the gases. Members of the Galerne project are producers and handlers of liquefied gases and are experts in atmospheric modelling, ship structure, risk assessment, hazards assessment and operations. Several simulations and experiments were performed in an effort to produce operational information for responders and headquarters. For practical and financial reasons, it was not possible to consider all 31 chemicals described in the IGC code. Only 4 liquid gases were chosen for the Galerne project, notably methane liquefied natural gas (LNG); propane LNG; ammonia; and vinyl chloride monomer (VCM). They were chosen on the basis of their transport characteristics and behaviour. This paper outlined the physical characteristics of the transported products verses their volume in standard conditions; the type of ship dedicated to transporting gases in liquid forms; and various response phases. It also included a brief review of several ship incidents and accidents. It was concluded that as far as the LNG carriers are concerns, a few accidents at sea have occurred in more than 28 years, but no major accidents involving the cargo have been reported. Handling LNG at terminals can lead to serious accidents. Accidents have occurred at sea, but without any accidental spillage of cargo. It was concluded that response teams on-board disabled liquefied gas carriers need to know the main characteristics of the cargo and the potential hazards. 3 tabs., 6 figs.

  19. Health hazard of the Tokai mura nuclear accident. Unnecessary fear and improper health checks should be eliminated

    International Nuclear Information System (INIS)

    Takebe, Hiraku

    2000-01-01

    Three workers were heavily exposed to radiations in the Tokai mura nuclear accident, and one of them died due to the acute effects of radiations. Doses for the heavily exposed persons were estimated to be 2.5, 10 and 18 Sv, according to the Science and Technology Agency. Workers who tried to stop the chain reaction by breaking the water pipe were estimated to have been exposed up to 120 mSv. Possible doses for other workers and residents in the neighborhoods were estimated to be less than 10 mSv, with a few workers with slightly higher film badge records. After the accident, many reports in mass-media warned that the exposed persons may develop cancers and leukemias in future and follow-up healthcare should be needed. Judging from our knowledge of the extensive epidemiological survey of the atomic bomb survivors in Hiroshima and Nagasaki, these reports are very misleading. There would be absolutely no or extremely small possibility of developing any health hazard among the workers and the residents except for the three unfortunate heavily exposed workers. If so-called follow-up health checks would involve x-ray diagnosis for cancers, the radiation doses by the diagnosis would exceed the exposure by the accident. Also, the test for the DNA damage applied to some workers and residents is not reliable at all, and could cause unnecessary fear among the persons who were mistakingly said to be of high-risk. (author)

  20. Lessons learned from EU stress tests evaluations with regard to external hazards

    International Nuclear Information System (INIS)

    Misak, J.

    2014-01-01

    The presentation was oriented to critical review of the lessons learned from the European Union (EU) Stress Test focusing on NPP robustness against external hazards. These lessons addressed: - organization of the stress tests, - scope and objectives of the stress tests, - peer review findings, recommendations and implications on the design in the area of external hazards, - further studies recommended in the area of external hazards and PSA, - relevant research areas identified by the SNETP Task Group in response to Fukushima accident. Some important conclusions were made in the final part of the presentation: - Vulnerability to the Fukushima Dai-ichi reactor accidents caused by external hazards and including their secondary effects was underestimated, - Lessons learned from Fukushima Dai-ichi reactor accidents, from the EU Stress Test and from peer reviews are to be reflected in safety improvements of operating plants and considered in new designs, - while no completely new phenomena were revealed from the Fukushima Dai-ichi reactor accidents, improvements in specific research areas (including external hazards and use of PSA) should be considered with high priority

  1. The costs of failure: A preliminary assessment of major energy accidents, 1907-2007

    International Nuclear Information System (INIS)

    Sovacool, Benjamin K.

    2008-01-01

    A combination of technical complexity, tight coupling, speed, and human fallibility contribute to the unexpected failure of large-scale energy technologies. This study offers a preliminary assessment of the social and economic costs of major energy accidents from 1907 to 2007. It documents 279 incidents that have been responsible for $41 billion in property damage and 182,156 deaths. Such disasters highlight an often-ignored negative externality to energy production and use, and emphasize the need for further research

  2. Major Differences in Rates of Occupational Accidents between Different nationalities of Seafarers

    DEFF Research Database (Denmark)

    Hansen, Henrik Lyngbeck; Laursen, Lise Hedegaard; Frydberg, Morten

    2008-01-01

    . Differences in approach to safety and risk taking between South East Asian and European seafarers should be identified and positives attitudes included in accident preventing programmes. Main messages Seafarers from South East Asia, mainly the Philippines, seem to have a genuine lower risk of occupational...... sources on occurrence of accidents were used and to identify specific causes of excess accident rates among certain nationalities. METHODS: Occupational accidents aboard Danish merchant ships during one year were identified from four different sources. These included accidents reported to the maritime...... including only more serious accidents, IRR for South East Asians rose to 0.36 (0.26-0.48). DISCUSSION: This study indicates that seafarers from South East Asia, mainly the Philippines, may have a genuine lower risk of occupational accidents in comparison with seafarers from Western and Eastern Europe...

  3. Risk assessment of hazardous waste transport - perspectives of GIS application

    International Nuclear Information System (INIS)

    Lazar, R.E.; Dumitrescu, M.; Stefanescu, I.

    2001-01-01

    Due to the increasing public awareness of the potential risks associated with waste transport, the environmental impact assessment of this activity has become an issue of major importance. This paper presents a project proposal, which can establish a national action plan for waste transport evaluation. Such a programme is sustained by the necessity to obtain an adequate method for the rapid and efficient estimation of individual and social risks due to the transport of hazardous substances in Romania. The main objective is to develop regional strategies for risk assessment in comprising: establishing the areas that must be investigated and their particular characteristics; identifying the transport activities in the areas; determining hazards; establishing the analysis criteria and prioritizing the study areas; evaluating continuous emissions; studying major accidents; studying population health; classifying the risks; establishing regional strategies; implementing political and regulatory measures. The project expectation is to provide a decision tool for risk managers and authorities in order to control or limit transportation and the storage of hazardous substances.(author)

  4. Report by the 'Fukushima Dai-Ichi major accident' nuclear subgroup

    International Nuclear Information System (INIS)

    Brezin, Edouard; Balibar, Sebastien; Candel, Sebastien; Cesarsky, Catherine; Dautray, Robert; Gratias, Denis; Guillaumont, Robert; Laval, Guy; Quere, Yves; Tissot, Bernard; Zaoui, Andre; Brechet, Yves; Carpentier, Alain; Duplessy, Jean-Claude; Jerome, Denis; Bamberger, Yves; Barre, Bertrand; Comets, Marie-Pierre; Jamet, Philippe; Schwarz, Michel; Baumont, David; Guilhem, Gilbert; Repussard, Jacques; Billot, Philippe; Boullis, Bernard; Gauche, Francois; Zaetta, Alan; Pouget-Abadie, Xavier

    2011-06-01

    This report comprises a description of the succession of events in the Fukushima-Dai-Ichi power plant, a discussion of the situation of the nuclear industry and energy in France after this accident (French nuclear stock, security organisation), and a discussion on the fuel cycle and on future opportunities (comparison with EPR - Gen II safety measures, perspectives beyond the EPR). Numerous appendices are proposed, made of documents from different bodies involved in nuclear industry, energy and safety. They deal with the Fukushima accident, with light water and pressurized water reactors, with severe accidents in PWRs, and so on

  5. Introduction of the Amendment of IAEA Safety Requirements Reflected Lessons Learned from Fukushima Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sang-Kyu; Ahn, Hyung-Joon; Kim, Sun-Hae; Cheong, Jae-Hak [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The following five Safety Requirements publications were amended: Governmental, Legal and Regulatory Framework for Safety (GSR Part 1, 2010), Site Evaluation for Nuclear Installations (NS-R-3, 2003), Safety of Nuclear Power Plants: Design (SSR-2/1, 2012), Safety of Nuclear Power Plants: Commissioning and Operation (SSR-2/2, 2011), and Safety Assessment for Facilities and Activities (GSR Part 4, 2009). Figure 1 shows IAEA Safety Standards Categories Major amendments of five Safety Requirements publications were introduced and analyzed in this study. The five IAEA safety requirements publications which are GSR Part 1 and 4, NS-R-3 and SSR-2/1 and 2, were amended to reflect the lesson learned from the Fukushima accident and other operating experiences. Specially, 36 provisions were modified and the new 29 provision with 1 requirement (No. 67: Emergency response facilities on the site) of the SSR-2/1 were established. Since the Fukushima accident happened, a new word, design extension conditions (DECs) which cover substantially the beyond design basis accidents (BDBA), including severe accident conditions, was created and more elaborated by the world nuclear experts. Design extension conditions could include conditions in events without significant fuel degradation and conditions with core melting. Figure 2 shows the range of the DECs. The amendment of the five IAEA safety requirements publications are focused at the prevention of initiating events, which would lead to the DECs, and mitigation of the consequences of DECs by the enhanced defense in depth principle. The following examples of the IAEA requirements to prevent the initiating events are: margins for withstanding external events; margins for avoiding cliff edge effects; safety assessment for multiple facilities or activities at a single site; safety assessment in cases where resources at a facility are shared; consideration of the potential occurrence of events in combination; establishing levels of hazard

  6. Effects on accidents of changes in the use of studded tyres in major cities in Norway

    DEFF Research Database (Denmark)

    Elvik, Rune; Fridstrøm, Lasse; Kaminska, Joanna

    2013-01-01

    This paper reports the findings of two studies made eleven years apart in Norway (0035 and 0025) to evaluate effects on accidents of changes in the use of studded tyres in major cities in Norway. The first study covered the period from 1991 to 2000, the second study covered the period from 2002...... to 2009. In both these periods, large changes in the percentage of cars using studded tyres were found in the cities that were included in the study. There was, in most cities, a tendency for the use of studded tyres to go down. Effects of these changes on injury accidents were evaluated by means...... of negative binomial regression models, using city and day as the unit of analysis, and including more than twenty explanatory variables in order to control for confounding factors. The effects of changes in the percentage of cars using studded tyres were well described by an accident modification function...

  7. Chernobyl - an evaluation of health hazards. 3. enl. and rev. ed.

    International Nuclear Information System (INIS)

    Huber, E.E.; Dersee, T.; Iwert, B.

    1986-01-01

    The pamphlet abstracted contains some general information about the radiation hazards and health risks of nuclear power plants. The consequences of the Chernobyl reactor accident are dealt with by way of summarizing the events and by evaluating the health risks and damage the public should be prepared for. This topical report is completed by a popular presentation of the risks of nuclear power and by definitions of the major terms and measuring units. (DG) [de

  8. Hazards evaluation of plutonium metal opening and stabilization

    International Nuclear Information System (INIS)

    JOHNSON, L.E.

    1999-01-01

    Hazards evaluation is the analysis of the significance of hazardous situations associated with an activity OK process. The HE used qualitative techniques of Hazard and Operability (HazOp) analysis and What-If analysis to identify those elements of handling and thermal stabilization processing that could lead to accidents

  9. Pattern of accident distribution in the telecommunications industry.

    Science.gov (United States)

    Davis, P R; Sheppard, N J

    1980-05-01

    Examination of the accident records from the telecommunication industry covering some 100 000 engineers over a 12-month period showed that 25% of accidents resulting in more than three days' sick leave gave rise to back injuries. Handling accidents and falls accounted for 65% of three-day-plus accidents; handling accidents alone gave rise to 65% of back injuries. The absolute numbers of accidents have been compared with the total population of engineers to estimate the effects of age or occupation on levels of hazard; certain occupations constituting 33% of the engineers' population suffered 70% of all three-day-plus accidents. Accidents occurred most frequently in the group aged from 31 to 48 years. Other significant factors affecting the occurrence of accidents were time of year and duty experience of the workers.

  10. EDITORIAL Road traffic accident: A major public health problem in ...

    African Journals Online (AJOL)

    admin

    Damen Haile Mariam1. One of the articles in this issue demonstrates how road traffic accident is a serious, but neglected, health problem in Ethiopia using secondary data collected by the Amhara National Regional State. Police Commission from 2007-2011 (1). Fatalities due to traffic accidents are reported to be among.

  11. Nitrous Oxide Explosive Hazards

    Science.gov (United States)

    2008-05-01

    concentrations of N2O. A test program is suggested that could answer questions about decomposition propagation control in large N2O systems and hazards...accident. OSHA fined Scaled Composites for not training their workers informing them about N2O hazards, instructing them on safe procedures, and...seemed present that could produce temperatures in excess of the autogeneous ignition temperature (AIT) for the polymers? Autogeneous ignition

  12. Technical basis document for natural event hazards

    International Nuclear Information System (INIS)

    CARSON, D.M.

    2003-01-01

    This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for natural event hazards (NEH)-initiated representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

  13. Canister storage building hazard analysis report

    International Nuclear Information System (INIS)

    POWERS, T.B.

    1999-01-01

    This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the CSB final safety analysis report (FSAR) and documents the results. The hazard analysis was performed in accordance with the DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', and meets the intent of HNF-PRO-704, ''Hazard and Accident Analysis Process''. This hazard analysis implements the requirements of DOE Order 5480.23, ''Nuclear Safety Analysis Reports''

  14. Multiple external hazards compound level 3 PSA methods research of nuclear power plant

    Science.gov (United States)

    Wang, Handing; Liang, Xiaoyu; Zhang, Xiaoming; Yang, Jianfeng; Liu, Weidong; Lei, Dina

    2017-01-01

    2011 Fukushima nuclear power plant severe accident was caused by both earthquake and tsunami, which results in large amount of radioactive nuclides release. That accident has caused the radioactive contamination on the surrounding environment. Although this accident probability is extremely small, once such an accident happens that is likely to release a lot of radioactive materials into the environment, and cause radiation contamination. Therefore, studying accidents consequences is important and essential to improve nuclear power plant design and management. Level 3 PSA methods of nuclear power plant can be used to analyze radiological consequences, and quantify risk to the public health effects around nuclear power plants. Based on multiple external hazards compound level 3 PSA methods studies of nuclear power plant, and the description of the multiple external hazards compound level 3 PSA technology roadmap and important technical elements, as well as taking a coastal nuclear power plant as the reference site, we analyzed the impact of off-site consequences of nuclear power plant severe accidents caused by multiple external hazards. At last we discussed the impact of off-site consequences probabilistic risk studies and its applications under multiple external hazards compound conditions, and explained feasibility and reasonableness of emergency plans implementation.

  15. Overview of results and perspectives from the Shoreham major common-cause initiating events study

    International Nuclear Information System (INIS)

    Joksimovich, V.; Orvis, D.D.; Paccione, R.J.

    1986-01-01

    This study represents the continuation of a large effort by LILCO to fully understand the potential hazards posed by future operation of the Shoreham Nuclear Power Stations (SNPS). The Shoreham Probabilistic Risk Assessment, a level 3 PRA without external events, provided a characterization of the accident sequences that could leave the core in a condition in which it would be vulnerable to severe damage if further mitigating actions were not taken. It estimated the frequency and magnitude of the potential radioactivity releases associated with such sequences. The study was limited to accident sequences initiated by so called internal events to the plant including a loss of offsite power. It also characterized the public risk associated with those accident sequences. The ''Major Common-Cause Initiating Events Study'' (MCCI) for the Shoreham plant was performed to obtain insights into the plant's susceptibility to, and inherent defenses against, certain MCCIs. Major common-cause initiating events are occurrences which have the potential to initiate a plant transient or LOCA and, also, damage one or more plant systems needed to mitigate the effects of a transient or LOCA. The scope of the MCCI study included detailed analyses of seismic events and fires through the severe core damage and bounding analyses of aircraft crashes, windstorms, turbine missiles and release of hazardous materials near the plant

  16. The significance of domino effect in chemical accidents

    OpenAIRE

    Hemmatian, Behrouz; Abdolhamidzadeh, B; Darbra Roman, Rosa Maria; Casal Fàbrega, Joaquim

    2014-01-01

    A historical survey was performed on 330 accidents involving domino effect, occurred in process/storage plants and in the transportation of hazardous materials; only accidents occurred after 1st-January-1961 have been considered. The main features – geographical location, type of accident, materials involved, origin and causes, consequences, domino sequences – were analyzed, with special consideration to the situation in the developing countries and compared to those from other previous surve...

  17. Accident selection methodology for TA-55 FSAR

    International Nuclear Information System (INIS)

    Letellier, B.C.; Pan, P.Y.; Sasser, M.K.

    1995-01-01

    In the past, the selection of representative accidents for refined analysis from the numerous scenarios identified in hazards analyses (HAs) has involved significant judgment and has been difficult to defend. As part of upgrading the Final Safety Analysis Report (FSAR) for the TA-55 plutonium facility at the Los Alamos National Laboratory, an accident selection process was developed that is mostly mechanical and reproducible in nature and fulfills the requirements of the Department of Energy (DOE) Standard 3009 and DOE Order 5480.23. Among the objectives specified by this guidance are the requirements that accident screening (1) consider accidents during normal and abnormal operating conditions, (2) consider both design basis and beyond design basis accidents, (3) characterize accidents by category (operational, natural phenomena, etc.) and by type (spill, explosion, fire, etc.), and (4) identify accidents that bound all foreseeable accident types. The accident selection process described here in the context of the TA-55 FSAR is applicable to all types of DOE facilities

  18. Analysis of accidents in nine Iranian gas refineries: 2007-2011.

    Science.gov (United States)

    Mehrdad, R; Bolouri, A; Shakibmanesh, A R

    2013-10-01

    Occupational accidents are one of the major health hazards in industries and associated with high mortality, morbidity, spiritual damage and economic losses in the world. To determine the incidence of occupational accidents in 9 Iranian gas refineries between March 2007 and February 2011. Data on all occupational accidents occurred between March 2007 and February 2011, as well as other possible associated variables including time of accident, whether the accident was due to a personal or systemic fault, type of accident and its outcomes, age and gender of the victim, the injured parts of the body, job experience, and type of employment, were extracted from HSE reports and notes of health care services. Based on these data, we calculated the incidence rate of accidents and assessed the associated factors. During the 5 studied years, 1129 accidents have been recorded. The incidence of fatal accidents was 1.64 per 100 000 and of nonfatal accidents was 1857 per 100 000 workers per year. 99.4% of injured workers were male. The mean±SD age of injured people was 29.6±7.3 years. Almost 70% of injured workers aged under 30 years. The mean±SD job experience was 5.3±5.3 years. Accidents occurred more commonly around 10:00. More than 60% of accidents happened between 8:00 and 15:00. July had the highest incidence rate. The most common type of accident was being struck by an object (48%). More than 94% of accidents are caused by personal rather than systemic faults. Hands and wrists were the most common injured parts and involved in more than one-third of accidents. 70% of injured workers needed medical treatment and returned to work after primary treatment. The pattern of occupational accidents in Iranian gas refineries is similar to other previous reports in many ways. The incidence did not change significantly over the study period. Establishment of an online network for precise registration, notification and meticulous data collection seems necessary.

  19. Pilot Domain Task Experience in Night Fatal Helicopter Emergency Medical Service Accidents.

    Science.gov (United States)

    Aherne, Bryan B; Zhang, Chrystal; Newman, David G

    2016-06-01

    In the United States, accident and fatality rates in helicopter emergency medical service (HEMS) operations increase significantly under nighttime environmentally hazardous operational conditions. Other studies have found pilots' total flight hours unrelated to HEMS accident outcomes. Many factors affect pilots' decision making, including their experience. This study seeks to investigate whether pilot domain task experience (DTE) in HEMS plays a role against likelihood of accidents at night when hazardous operational conditions are entered. There were 32 flights with single pilot nighttime fatal HEMS accidents between 1995 and 2013 with findings of controlled flight into terrain (CFIT) and loss of control (LCTRL) due to spatial disorientation (SD) identified. The HEMS DTE of the pilots were compared with industry survey data. Of the pilots, 56% had ≤2 yr of HEMS experience and 9% had >10 yr of HEMS experience. There were 21 (66%) accidents that occurred in non-visual flight rules (VFR) conditions despite all flights being required to be conducted under VFR. There was a statistically significant increase in accident rates in pilots with pilots with >10 yr HEMS DTE. HEMS DTE plays a preventive role against the likelihood of a night operational accident. Pilots with limited HEMS DTE are more likely to make a poor assessment of hazardous conditions at night, and this will place HEMS flight crew at high risk in the VFR night domain.

  20. Optimization of emergency response to major nuclear accidents

    International Nuclear Information System (INIS)

    Papazoglou, I.A.; Christou, M.D.

    1991-01-01

    A methodology for the optimization of the short-term emergency response in the event of a nuclear accident has been developed. The method aims at an optimum combination of protective actions in the presence of a multitude of conflicting objectives and under uncertainty. Conflicting objectives arise when the minimization of the potential adverse effects of an accident and the simultaneous minimization of the associated socioeconomic impacts is attempted. Additional conflicting objectives appear whenever an emergency plan tends to decrease a particular health effect (e.g. acute deaths) while at the same time it increases another (e.g. latent deaths). The uncertainty is due to the multitude of the possible accident scenarios and their respective probability of occurrence, the stochastic variability in the weather conditions and in the variability and/or lack of knowledge in the parameters of the risk assessment models. A multiobjective optimization approach is adopted in a dynamic programming scheme. An emergency protective plan consists of defining a protective action (e.g. evacuation, sheltering) at each spatial cell around the plant. Three criteria (evaluators) are used as the objective functions of the problem, namely, acute fatalities, latent effects and socioeconomic cost. The optimization procedure defines the efficient frontier, i.e. all emergency plans that are not dominated by another in all three criteria. No value trade-offs are necessary up to this point

  1. Improving aircraft accident forecasting for an integrated plutonium storage facility

    International Nuclear Information System (INIS)

    Rock, J.C.; Kiffe, J.; McNerney, M.T.; Turen, T.A.

    1998-06-01

    Aircraft accidents pose a quantifiable threat to facilities used to store and process surplus weapon-grade plutonium. The Department of Energy (DOE) recently published its first aircraft accident analysis guidelines: Accident Analysis for Aircraft Crash into Hazardous Facilities. This document establishes a hierarchy of procedures for estimating the small annual frequency for aircraft accidents that impact Pantex facilities and the even smaller frequency of hazardous material released to the environment. The standard establishes a screening threshold of 10 -6 impacts per year; if the initial estimate of impact frequency for a facility is below this level, no further analysis is required. The Pantex Site-Wide Environmental Impact Statement (SWEIS) calculates the aircraft impact frequency to be above this screening level. The DOE Standard encourages more detailed analyses in such cases. This report presents three refinements, namely, removing retired small military aircraft from the accident rate database, correcting the conversion factor from military accident rates (accidents per 100,000 hours) to the rates used in the DOE model (accidents per flight phase), and adjusting the conditional probability of impact for general aviation to more accurately reflect pilot training and local conditions. This report documents a halving of the predicted frequency of an aircraft impact at Pantex and points toward further reductions

  2. Investigations of Human and Organizational Factors in hazardous vapor accidents

    International Nuclear Information System (INIS)

    Wang Yanfu; Faghih Roohi, Shahrzad; Hu Xiuming; Xie Min

    2011-01-01

    Highlights: → HFACS provides a systematic guideline in accident investigations. The hierarchal structure of HFACS forces investigators to seek out latent HOFs. → Bayesian Network enhances the ability of the HFACS by allowing experts to quantify the degree of relationships among the HOFs. → The fuzzy AHP helps to reduce the subjective biases by avoiding the need to give explicit probability values for the variables' states. - Abstract: This paper presents a model to assess the contribution of Human and Organizational Factor (HOF) to accidents. The proposed model is made up of two phases. The first phase is the qualitative analysis of HOF responsible for accidents, which utilizes Human Factors Analysis and Classification System (HFACS) to seek out latent HOFs. The hierarchy of HOFs identified in the first phase provides inputs for the analysis in the second phase, which is a quantitative analysis using Bayesian Network (BN). BN enhances the ability of HFACS by allowing investigators or domain experts to measure the degree of relationships among the HOFs. In order to estimate the conditional probabilities of BN, fuzzy analytical hierarchy process and decomposition method are applied in the model. Case studies show that the model is capable of seeking out critical latent human and organizational errors and carrying out quantitative analysis of accidents. Thereafter, corresponding safety prevention measures are derived.

  3. Seminar on Comparative assessment of the environmental impact of radionuclides released during three major nuclear accidents: Kyshtym, Windscale, Chernobyl. Vol. 1

    International Nuclear Information System (INIS)

    1991-01-01

    These proceedings of seminar on comparative assessment of the environmental impact of radionuclides released during three major nuclear accidents (Kyshtym, Windscale, Chernobyl) are divided into 5 parts bearing on: part 1: accident source terms; part 2: atmospheric dispersion, resuspension, chemical and physical forms of contamination; part 3: environmental contamination and transfer; part 4: radiological implications for man and his environment; part 5: countermeasures

  4. Major Factors Affecting Incidence of Childhood Thyroid Cancer in Belarus after the Chernobyl Accident: Do Nitrates in Drinking Water Play a Role?

    OpenAIRE

    Drozd, Valentina M.; Saenko, Vladimir A.; Brenner, Alina V.; Drozdovitch, Vladimir; Pashkevich, Vasilii I.; Kudelsky, Anatoliy V.; Demidchik, Yuri E.; Branovan, Igor; Shiglik, Nikolay; Rogounovitch, Tatiana I.; Yamashita, Shunichi; Biko, Johannes; Reiners, Christoph

    2015-01-01

    One of the major health consequences of the Chernobyl Nuclear Power Plant accident in 1986 was a dramatic increase in incidence of thyroid cancer among those who were aged less than 18 years at the time of the accident. This increase has been directly linked in several analytic epidemiological studies to iodine-131 (131I) thyroid doses received from the accident. However, there remains limited understanding of factors that modify the 131I-related risk. Focusing on post-Chernobyl pediatric thy...

  5. Preliminary Hazard Classification for the 105-B Reactor

    International Nuclear Information System (INIS)

    Kerr, N.R.

    1997-08-01

    This document summarizes the inventories of radioactive and hazardous materials present within the 105-B Reactor and uses the inventory information to determine the preliminary hazard classification for the surveillance and maintenance activities of the facility. The result of this effort was the preliminary hazard classification for the 105-B Building surveillance and maintenance activities. The preliminary hazard classification was determined to be Nuclear Category 3. Additional hazard and accident analysis will be documented in a separate report to define the hazard controls and final hazard classification

  6. 78 FR 14877 - Pipeline Safety: Incident and Accident Reports

    Science.gov (United States)

    2013-03-07

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID PHMSA-2013-0028] Pipeline Safety: Incident and Accident Reports AGENCY: Pipeline and Hazardous Materials... PHMSA F 7100.2--Incident Report--Natural and Other Gas Transmission and Gathering Pipeline Systems and...

  7. Estimating inhalation hazards for space nuclear power systems

    International Nuclear Information System (INIS)

    Hoover, M.D.; Cuddihy, R.G.; Seiler, F.Z.

    1989-01-01

    Minimizing inhalation hazards is a major consideration in the design, development, transportation, handling, testing, storage, launch, use, and ultimate disposition of nuclear space power systems (NSPSs). An accidental dispersion of 238 Pu is of concern for missions involving the radioisotope thermoelectric generators (RTGs) or lightweight radioisotope heater units. Materials of concern for missions involving a nuclear reactor might include other radionuclides, such as uranium, or chemically toxic materials, such as beryllium or lithium. This paper provides an overview of some of the current approaches and uncertainties associated with estimating inhalation hazards from potential NSPS accidents. The question of whether inhalation risks can be acceptable for nuclear space power systems is still open and active. The inherently low toxicity of the uranium fuel of a space nuclear reactor is a desirable feature of that option. The extensive engineering and testing that have contributed to the current generation of plutonium RTGs provide a measure of confidence that dispersion of the RTG fuel would be unlikely in an accident. The use of nuclear reactors or RTGs in space, however, requires society to assume a risk (albeit low) for dispersion of the fuel material. It can be argued that any additional risks from the use of nuclear power in space are far less than the risks we face daily

  8. AN ANALYSIS OF ACCIDENT TRENDS AND MODELING OF SAFETY INDICES IN AN INDIAN CONSTRUCTION ORGANIZATION

    Directory of Open Access Journals (Sweden)

    Sunku Venkata Siva Rajaprasad

    2016-09-01

    Full Text Available Construction industry has been recognized as a hazardous industry in many countries due to distinct nature of execution of works.The accident rate in construction sector is high all over the world due to dynamic nature of work activities. Occurrence of accidents and its severity in construction industry is several times higher than the manufacturing industries. The study was limited to a major construction organization in India to examine the trends in construction accidents for the period 2008-2014. In India, safety performance is gauged basing on safety indices; frequency, severity and incidence rates. It is not practicable to take decisions or to implement safety strategies on the basis of indices. The data used for this study was collected from a leading construction organization involved in execution of major construction activities all over India and abroad. The multiple regression method was adopted to model the pattern of safety indices wise .The pattern showed that significant relationships exist between the three safety indices and the related independent variables.

  9. The use of hazards analysis in the development of training

    Energy Technology Data Exchange (ETDEWEB)

    Houghton, F.K.

    1998-12-01

    A hazards analysis identifies the operation hazards and the positive measures that aid in the mitigation or prevention of the hazard. If the tasks are human intensive, the hazard analysis often credits the personnel training as contributing to the mitigation of the accident`s consequence or prevention of an accident sequence. To be able to credit worker training, it is important to understand the role of the training in the hazard analysis. Systematic training, known as systematic training design (STD), performance-based training (PBT), or instructional system design (ISD), uses a five-phase (analysis, design, development, implementation, and evaluation) model for the development and implementation of the training. Both a hazards analysis and a training program begin with a task analysis that documents the roles and actions of the workers. Though the tasks analyses are different in nature, there is common ground and both the hazard analysis and the training program can benefit from a cooperative effort. However, the cooperation should not end with the task analysis phase of either program. The information gained from the hazards analysis should be used in all five phases of the training development. The training evaluation, both of the individual worker and institutional training program, can provide valuable information to the hazards analysis effort. This paper will discuss the integration of the information from the hazards analysis into a training program. The paper will use the installation and removal of a piece of tooling that is used in a high-explosive operation. This example will be used to follow the systematic development of a training program and demonstrate the interaction and cooperation between the hazards analysis and training program.

  10. Report of the Fukushima nuclear accident by the National Academy of Science. Lessons learned from the Fukushima nuclear accident for improving safety of U.S. nuclear plants

    International Nuclear Information System (INIS)

    Nariai, Hideki

    2014-01-01

    U.S. National Academy of Science investigated the accident at the Fukushima Daiichi nuclear plant initiated by the Great East Japan Earthquake for two years and published a draft report in July 24, 2014. Investigation results were summarized in nine new findings and made ten recommendations in a wide horizon; (1) hardware countermeasures against severe accidents and training of operators, (2) upgrade of risk assessment capability for beyond design basis accident, (3) incorporation of new information about hazards in safety regulations, (4) needed improvement of off-site emergency preparedness, and (5) improvements of nuclear safety culture. New information about hazards related with tsunami assessment, new risk assessment for beyond design basis accident, advice of foreigner resident evacuations, regulatory capture, and safety culture and regulator's specialty were discussed as Japanese issues. (T. Tanaka)

  11. Identification of Potential Hazard using Hazard Identification and Risk Assessment

    Science.gov (United States)

    Sari, R. M.; Syahputri, K.; Rizkya, I.; Siregar, I.

    2017-03-01

    This research was conducted in the paper production’s company. These Paper products will be used as a cigarette paper. Along in the production’s process, Company provides the machines and equipment that operated by workers. During the operations, all workers may potentially injured. It known as a potential hazard. Hazard identification and risk assessment is one part of a safety and health program in the stage of risk management. This is very important as part of efforts to prevent occupational injuries and diseases resulting from work. This research is experiencing a problem that is not the identification of potential hazards and risks that would be faced by workers during the running production process. The purpose of this study was to identify the potential hazards by using hazard identification and risk assessment methods. Risk assessment is done using severity criteria and the probability of an accident. According to the research there are 23 potential hazard that occurs with varying severity and probability. Then made the determination Risk Assessment Code (RAC) for each potential hazard, and gained 3 extreme risks, 10 high risks, 6 medium risks and 3 low risks. We have successfully identified potential hazard using RAC.

  12. Deep Borehole Emplacement Mode Hazard Analysis Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-08-07

    This letter report outlines a methodology and provides resource information for the Deep Borehole Emplacement Mode Hazard Analysis (DBEMHA). The main purpose is identify the accident hazards and accident event sequences associated with the two emplacement mode options (wireline or drillstring), to outline a methodology for computing accident probabilities and frequencies, and to point to available databases on the nature and frequency of accidents typically associated with standard borehole drilling and nuclear handling operations. Risk mitigation and prevention measures, which have been incorporated into the two emplacement designs (see Cochran and Hardin 2015), are also discussed. A key intent of this report is to provide background information to brief subject matter experts involved in the Emplacement Mode Design Study. [Note: Revision 0 of this report is concentrated more on the wireline emplacement mode. It is expected that Revision 1 will contain further development of the preliminary fault and event trees for the drill string emplacement mode.

  13. The economics of nuclear energy revisited: lessons from the use of a complex technology subject to major accidents

    International Nuclear Information System (INIS)

    Finon, D.

    2012-01-01

    The Fukushima accident again raises the issue of the social and economic viability of nuclear technology. To reassess this viability, we analyze the methods used to internalize the external costs of nuclear energy. These have over time become increasingly complex technologically and specifically affected by major accidents. This combination has served to upset the classical learning curve, calling into question nuclear cost base, social acceptance in the face of climate change and profitability for investors. It has become essential to put in place independent institutions to regulate the safety aspect of nuclear technology and these form a hindrance to its standardization, in turn affecting competitiveness. Nevertheless, the paper argues that the new sequence of internalization of external costs triggered by Fukushima will have limited effects on overall costs, because of previous measures already taken to improve safety. The complexity of nuclear technology is reaching its asymptote: the challenge of 'learning from major accidents' will decrease. On the other hand, the independence and competence of nuclear safety authorities in all countries must be revamped to maximize safety and minimize residual risks. This cannot just be done by decree. However, it is the only way to preserve this global public good - the social acceptance of nuclear technology

  14. National emergency plan for nuclear accidents

    International Nuclear Information System (INIS)

    1992-10-01

    The national emergency plan for nuclear accidents is a plan of action designed to provide a response to accidents involving the release or potential release of radioactive substances into the environment, which could give rise to radiation exposure to the public. The plan outlines the measures which are in place to assess and mitigate the effects of nuclear accidents which might pose a radiological hazard in ireland. It shows how accident management will operate, how technical information and monitoring data will be collected, how public information will be provided and what measures may be taken for the protection of the public in the short and long term. The plan can be integrated with the Department of Defence arrangements for wartime emergencies

  15. Quantitative occupational risk model: Single hazard

    International Nuclear Information System (INIS)

    Papazoglou, I.A.; Aneziris, O.N.; Bellamy, L.J.; Ale, B.J.M.; Oh, J.

    2017-01-01

    A model for the quantification of occupational risk of a worker exposed to a single hazard is presented. The model connects the working conditions and worker behaviour to the probability of an accident resulting into one of three types of consequence: recoverable injury, permanent injury and death. Working conditions and safety barriers in place to reduce the likelihood of an accident are included. Logical connections are modelled through an influence diagram. Quantification of the model is based on two sources of information: a) number of accidents observed over a period of time and b) assessment of exposure data of activities and working conditions over the same period of time and the same working population. Effectiveness of risk reducing measures affecting the working conditions, worker behaviour and/or safety barriers can be quantified through the effect of these measures on occupational risk. - Highlights: • Quantification of occupational risk from a single hazard. • Influence diagram connects working conditions, worker behaviour and safety barriers. • Necessary data include the number of accidents and the total exposure of worker • Effectiveness of risk reducing measures is quantified through the impact on the risk • An example illustrates the methodology.

  16. Generalized railway tank car safety design optimization for hazardous materials transport: Addressing the trade-off between transportation efficiency and safety

    International Nuclear Information System (INIS)

    Saat, Mohd Rapik; Barkan, Christopher P.L.

    2011-01-01

    North America railways offer safe and generally the most economical means of long distance transport of hazardous materials. Nevertheless, in the event of a train accident releases of these materials can pose substantial risk to human health, property or the environment. The majority of railway shipments of hazardous materials are in tank cars. Improving the safety design of these cars to make them more robust in accidents generally increases their weight thereby reducing their capacity and consequent transportation efficiency. This paper presents a generalized tank car safety design optimization model that addresses this tradeoff. The optimization model enables evaluation of each element of tank car safety design, independently and in combination with one another. We present the optimization model by identifying a set of Pareto-optimal solutions for a baseline tank car design in a bicriteria decision problem. This model provides a quantitative framework for a rational decision-making process involving tank car safety design enhancements to reduce the risk of transporting hazardous materials.

  17. Recent developments in the external hazard risk assessment in Ukraine

    International Nuclear Information System (INIS)

    2000-01-01

    Ukrainian legislation prescribes safety analysis reports for all operating and future NPPs. Apart from main report they must include: safety analysis supplement; design basis accident analysis; beyond design basis accident analysis; probabilistic safety assessment (PSA); technical; substantiation of safety. Regulatory requirements to PSA contents cover the criteria for core damage frequency and large radioactive release frequency. Initiating events taken into account are internal events; internal hazards and external hazards. External hazards to be considered are seismic events, external fires, external floods, extreme ambient temperatures, aircraft crashes, etc. Current status of PSA development is related to operating WWER-440 and WWER-1000 NPPs and NPPs under construction. This presentation describes in detail the external hazard risk assessment for South Ukraine including methodology applied and expected future activities

  18. Research on preventive technologies for bed-separation water hazard in China coal mines

    Science.gov (United States)

    Gui, Herong; Tong, Shijie; Qiu, Weizhong; Lin, Manli

    2018-03-01

    Bed-separation water is one of the major water hazards in coal mines. Targeted researches on the preventive technologies are of paramount importance to safe mining. This article studied the restrictive effect of geological and mining factors, such as lithological properties of roof strata, coal seam inclination, water source to bed separations, roof management method, dimensions of mining working face, and mining progress, on the formation of bed-separation water hazard. The key techniques to prevent bed-separation water-related accidents include interception, diversion, destructing the buffer layer, grouting and backfilling, etc. The operation and efficiency of each technique are corroborated in field engineering cases. The results of this study will offer reference to countries with similar mining conditions in the researches on bed-separation water burst and hazard control in coal mines.

  19. The Tokai-mura JCO criticality accident and the activities of the accident countermeasure support team of Electric Power Companies, Japan

    International Nuclear Information System (INIS)

    Ogawa, Junko

    2000-01-01

    A criticality accident occurred at the JCO Tokai-mura nuclear fuel processing plant on September 30, 1999. This accident brought the damages which were unrivaled in the history of atomic energy development in Japan, seriously influencing the citizen life to such an extent as requesting for 320,000 inhabitants within 10 kilometers radius to stay indoors for as long as 18 hours. However, it could be said that though three workers suffered fatal injuries, no substantial hazards were made upon the regional inhabitants due to little release of radioactive substances. This video recorded the activities of the Accident Countermeasure Support Team of the Electric Power Companies immediately after the accident occurred, showing the chronological overview of the particulars of the accident. (author)

  20. Report by the Delegate for major risks for 2010; Rapport 2010 du delegue aux risques majeurs

    Energy Technology Data Exchange (ETDEWEB)

    Michel, Laurent [Ministere de l' Ecologie, du Developpement durable, des Transports et du Logement, Grande Arche, Tour Pascal A et B, 92055 La Defense Cedex (France)

    2011-07-01

    The first part of this report comments the major natural and industrial disasters which occurred in 2010 in France (Xynthia tempest, flooding, and forest fires) and in other countries. It also proposes some lessons from these disasters. The second part discusses the evolution towards a resilient society by a combined approach of sustainable development, of cultural good safeguarding, and person protection. It also discusses a prospective approach regarding natural hazards and technological accidents, adapted procedures, governance and land planning, the evolution of information and alarm systems, and emerging risks. The third part addresses the adaptation to natural hazards: frameworks and strategies, actions (regulatory prevention, flooding management, safety of hydraulic works, seismic plan). It assesses the financial and budgetary means brought by the State and its partners, and discusses some perspectives. It addresses the technological risks: legal and regulatory evolutions, safety of hazardous industrial installations, consequences of technological accidents. The next part deals with the control of civilian nuclear installations by the ASN. The last part presents the different involved structures and authorities

  1. An Independent Evaluation of the FMEA/CIL Hazard Analysis Alternative Study

    Science.gov (United States)

    Ray, Paul S.

    1996-01-01

    The present instruments of safety and reliability risk control for a majority of the National Aeronautics and Space Administration (NASA) programs/projects consist of Failure Mode and Effects Analysis (FMEA), Hazard Analysis (HA), Critical Items List (CIL), and Hazard Report (HR). This extensive analytical approach was introduced in the early 1970's and was implemented for the Space Shuttle Program by NHB 5300.4 (1D-2. Since the Challenger accident in 1986, the process has been expanded considerably and resulted in introduction of similar and/or duplicated activities in the safety/reliability risk analysis. A study initiated in 1995, to search for an alternative to the current FMEA/CIL Hazard Analysis methodology generated a proposed method on April 30, 1996. The objective of this Summer Faculty Study was to participate in and conduct an independent evaluation of the proposed alternative to simplify the present safety and reliability risk control procedure.

  2. Spatio-temporal patterns of hazards and their use in risk assessment and mitigation. Case study of road accidents in Romania

    Science.gov (United States)

    Catalin Stanga, Iulian

    2013-04-01

    the spatial or temporal clustering of crash accidents. Since the 1990's, Geographical Informational Systems (GIS) became a very important tool for traffic and road safety management, allowing not only the spatial and multifactorial analysis, but also graphical and non-graphical outputs. The current paper presents an accessible GIS methodology to study the spatio-temporal pattern of injury related road accidents, to identify the high density accidents zones, to make a cluster analysis, to create multicriterial typologies, to identify spatial and temporal similarities and to explain them. In this purpose, a Geographical Information System was created, allowing a complex analysis that involves not only the events, but also a large set of interrelated and spatially linked attributes. The GIS includes the accidents as georeferenced point elements with a spatially linked attribute database: identification information (date, location details); accident type; main, secondary and aggravating causes; data about driver; vehicle information; consequences (damages, injured peoples and fatalities). Each attribute has its own number code that allows both the statistical analysis and the spatial interrogation. The database includes those road accidents that led to physical injuries and loss of human lives between 2007 and 2012 and the spatial analysis was realized using TNTmips 7.3 software facilities. Data aggregation and processing allowed creating the spatial pattern of injury related road accidents through Kernel density estimation at three different levels (national - Romania; county level - Iasi County; local level - Iasi town). Spider graphs were used to create the temporal pattern or road accidents at three levels (daily, weekly and monthly) directly related to their causes. Moreover the spatial and temporal database relates the natural hazards (glazed frost, fog, and blizzard) with the human made ones, giving the opportunity to evaluate the nature of uncertainties in risk

  3. Drivers of accident preparedness and safety: evidence from the RMP Rule

    International Nuclear Information System (INIS)

    Kleindorfer, Paul R.; Elliott, Michael R.; Wang Yanlin; Lowe, Robert A.

    2004-01-01

    This paper provides an overview of recent results derived from the accident history data collected under 112(r) of the Clean Air Act Amendments (the Risk Management Program (RMP) Rule) covering the period 1994-2000, together with a preliminary assessment of the effectiveness of the RMP Rule as a form of Management System Regulation. These were undertaken at the University of Pennsylvania by a multi-disciplinary team of economists, statisticians and epidemiologists with the support of the US Environmental Protection Agency and its Office of Emergency Prevention, Preparedness and Response (OEPPR, formerly CEPPO). Section 112(r) of the Clean Air Act Amendments of 1990 requires that chemical facilities in the US that had on premises more than specified quantities of toxic or flammable chemicals file a 5-year history of accidents. The initial data reported under the RMP Rule covered roughly the period from mid-1994 through mid-2000, and provided details on economic, environmental and acute health affects resulting from accidents at some 15,000 US chemical facilities for this period. This paper reviews research based on this data. The research is in the form of a retrospective cohort study that considers the statistical associations between accident frequency and accident severity at covered facilities (the outcome variables of interest) and a number of facility characteristics (the available predictor variables provided by the RMP Rule), the latter including such facility characteristics as size, hazardousness, financial characteristics of parent company-owners of the facility, regulatory programs in force at the facility, and host community characteristics for the surrounding county in which the facility was located, as captured in the 1990 Census. Among the findings reviewed are: (1) positive associations with (a measure of) facility hazardousness and accident, injury and economic costs of accidents; (2) positive (resp., negative) associations between accident

  4. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

    1988-05-01

    The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

  5. Chernobyl and Fukushima nuclear accidents: what has changed in the use of atmospheric dispersion modeling?

    International Nuclear Information System (INIS)

    Benamrane, Y.; Wybo, J.-L.; Armand, P.

    2013-01-01

    The threat of a major accidental or deliberate event that would lead to hazardous materials emission in the atmosphere is a great cause of concern to societies. This is due to the potential large scale of casualties and damages that could result from the release of explosive, flammable or toxic gases from industrial plants or transport accidents, radioactive material from nuclear power plants (NPPs), and chemical, biological, radiological or nuclear (CBRN) terrorist attacks. In order to respond efficiently to such events, emergency services and authorities resort to appropriate planning and organizational patterns. This paper focuses on the use of atmospheric dispersion modeling (ADM) as a support tool for emergency planning and response, to assess the propagation of the hazardous cloud and thereby, take adequate counter measures. This paper intends to illustrate the noticeable evolution in the operational use of ADM tools over 25 y and especially in emergency situations. This study is based on data available in scientific publications and exemplified using the two most severe nuclear accidents: Chernobyl (1986) and Fukushima (2011). It appears that during the Chernobyl accident, ADM were used few days after the beginning of the accident mainly in a diagnosis approach trying to reconstruct what happened, whereas 25 y later, ADM was also used during the first days and weeks of the Fukushima accident to anticipate the potentially threatened areas. We argue that the recent developments in ADM tools play an increasing role in emergencies and crises management, by supporting stakeholders in anticipating, monitoring and assessing post-event damages. However, despite technological evolutions, its prognostic and diagnostic use in emergency situations still arise many issues. -- Highlights: • Study of atmospheric dispersion modeling use during nuclear accidents. • ADM tools were mainly used in a diagnosis approach during Chernobyl accident. • ADM tools were also used

  6. Assessment of emergency response planning and implementation in the aftermath of major natural disasters and technological accidents

    International Nuclear Information System (INIS)

    Milligan, Patricia A.; Jones, Joseph; Walton, F.; Smith, J.D.

    2008-01-01

    Emergency planning around nuclear power plants represents some of the most mature and well developed emergency planning in the United States. Since the implementation of NUREG-0654 / FEMA-REP-1, Rev. 1, A Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NRC, 1980a) the licensees, local, and State agencies have developed detailed Radiological Emergency Response Programs. An important component of these plans is the evacuation of the population in the event of a general emergency condition at the plant. In January 2005, the U.S. Nuclear Regulatory Commission (NRC) published the landmark report, 'Identification and Analysis of Factors Affecting Emergency Evacuations' (NUREG/CR 6864/), which represented the most comprehensive investigation of public evacuations in the United States in more than 15 years. Since the completion of this research, several high profile evacuations have occurred, including Hurricane Katrina in New Orleans, Hurricane Rita in Houston, as well as major wildfires across the western U.S. The NRC commissioned an update to its 2005 evacuation case study publication to evaluate the evacuation experience of the selected communities (e.g., timeliness, related injuries, hazard avoidance); the level of preplanning that was in place for the affected areas and extent that the pre planned requirements were implemented during the emergency response; the critical factors contributing to the efficiency of or impediments to the evacuations (e.g., training, drills, preparedness, experience, resources, facilities, and organizational structure); and additional factors that may have contributed to less than satisfactory public response (i.e., availability of personal transportation, use of public transportation, lack of availability of shelters, etc.). The comprehensive report will be published in fall of 2008 as NUREG/CR-6981, Assessment of Emergency Response Planning and

  7. Accidents with potentially hazardous biological material among workers in hospital supporting services.

    Science.gov (United States)

    Canini, Silvia Rita Marin da Silva; Gir, Elucir; Machado, Alcyone Artiolli

    2005-01-01

    Descriptive study was carried out to characterize the occupational accidents involving potentially contaminated material among workers of hospital supporting services. The study reviewed records of workers involved in these accidents and attended at a specialized outpatient clinic of a large tertiary care hospital between January 1997 and October 2001. A total of 2814 workers from different professional categories were attended during this period. Of these, 147 (5.2%) belonged to the hospital supporting services and were the victims of 156 accidents, auxiliary cleaning personnel (80.2%), and over a third of the workers had not received any dose of hepatitis B vaccine (35.4%). Most accidents were due to sharp injuries (96.8%) caused by inadequately discarded hollow needles. Chemoprophylaxis for HIV was not indicated in only 23.1% of cases. We conclude that these workers are also exposed to the possibility of acquiring blood-borne pathogens and that periodical education programs are needed.

  8. Work accidents during cable yarding operations in Central Europe 2006 – 2014

    International Nuclear Information System (INIS)

    Allman, M.; Jankovský, M.; Allmanová, Z.; Ferenčík, M.; Messingerová, V.; Vlčková, M.; Stanimir Stoilov

    2017-01-01

    Aim of study: This study is focused on detailed analysis of accidents in yarding during the years 2006–2014. There is still not enough information about such accidents in Central Europe in the literature available. Area of study: We collected the data on occupational accidents recorded in timber yarding from the databases of the Slovak state forest enterprise. Material and Methods: The data on occupational accidents were recorded according to actual European Regulation, the form of the record meets the requirements of the ESAW (European Statistics on Accidents at Work) methodology. To analyze the data, we used the multiple regression and correlation analysis, contingency tables, and a χ2 –test. Main results: Almost half of the accidents were the foot injuries and the most frequent type of injury was fracture of a bone. The most hazardous operation was yarding. Most of the accidents occurred between 1301-1400 h (22 %). The most frequent agent causing accidents were Particles, dust, splinters, fragments, etc. (14.05 by ESAW). Research highlights: This study informs about the most important risk factors in timber yarding, the most hazardous parts of shift, as well as the days when the most accidents occur during the week, and as such contributes to better understanding of how the accidents happen in timber yarding. The information can be subsequently used in knowledge-based improvement of safety trainings in forest enterprises.

  9. Work accidents during cable yarding operations in Central Europe 2006 – 2014

    Energy Technology Data Exchange (ETDEWEB)

    Allman, M.; Jankovský, M.; Allmanová, Z.; Ferenčík, M.; Messingerová, V.; Vlčková, M.; Stanimir Stoilov

    2017-11-01

    Aim of study: This study is focused on detailed analysis of accidents in yarding during the years 2006–2014. There is still not enough information about such accidents in Central Europe in the literature available. Area of study: We collected the data on occupational accidents recorded in timber yarding from the databases of the Slovak state forest enterprise. Material and Methods: The data on occupational accidents were recorded according to actual European Regulation, the form of the record meets the requirements of the ESAW (European Statistics on Accidents at Work) methodology. To analyze the data, we used the multiple regression and correlation analysis, contingency tables, and a χ2 –test. Main results: Almost half of the accidents were the foot injuries and the most frequent type of injury was fracture of a bone. The most hazardous operation was yarding. Most of the accidents occurred between 1301-1400 h (22 %). The most frequent agent causing accidents were Particles, dust, splinters, fragments, etc. (14.05 by ESAW). Research highlights: This study informs about the most important risk factors in timber yarding, the most hazardous parts of shift, as well as the days when the most accidents occur during the week, and as such contributes to better understanding of how the accidents happen in timber yarding. The information can be subsequently used in knowledge-based improvement of safety trainings in forest enterprises.

  10. Emergency planning lessons learned from a review of past major radiological accidents

    International Nuclear Information System (INIS)

    Stephan, J.G.; Selby, J.M.; Martin, J.B.; Moeller, D.W.; Vallario, E.J.

    1988-01-01

    In examining a range of nuclear accidents from the 1950s to the present that were reported in the literature, the authors have identified a number of contributing factors which affected human judgement during these events. One common thread found in a large number of accidents is the time of occurrence; a second is the adequacy of emergency training. The data show that events, whether severe accidents or operational incidents, appear to occur more frequently during off-normal hours such as the early morning shift, weekends, or holidays. Accidents seldom occur during the day shift when the full management team and senior operations personnel are present. As a result, those facility employees most expert in coping with the situation may not be available, and the normal chain of command may be disrupted. At several nuclear power plants, it was also observed that new or less experienced technicians are often assigned to night shifts. The lack of experienced human resources and the pressure of an accident situation can have an adverse impact on individuals who are faced with making important decisions

  11. Risk horoscopes: Predicting the number and type of serious occupational accidents in The Netherlands for sectors and jobs

    International Nuclear Information System (INIS)

    Bellamy, Linda J.; Damen, Martin; Jan Manuel, Henk; Aneziris, Olga N.; Papazoglou, Ioannis A.; Oh, Joy I.H.

    2015-01-01

    The risk of a serious occupational accident per hour exposure was calculated in a project to develop an occupational risk model in the Netherlands (WebORCA). To obtain risk rates, the numbers of victims of serious occupational accidents investigated by the Dutch Labour inspectorate 1998–Feb 2004 were divided by the number of hours exposure for each of 64 different types of hazards, such as contact with moving parts of machines and falls from various types of height. The exposures to the occupational accident hazards were calculated from a survey of a panel of 30,000 from the Dutch working population. Sixty risk rates were then used to predict serious accidents for activity sectors and jobs in the Netherlands where exposures to the hazards for sectors or jobs could be estimated from the survey. Such predictions have been called “horoscopes” because the idea is to provide a quick look-up of predicted accidents for a particular sector or job. Predictions compared favourably with actual data. It is concluded that predictive data can help provide information about accidents in cases where there is a lack of data, such as for smaller sub groups of the working population. - Highlights: • Dutch occupational accident risk rates and yearly exposures for 60 hazards are given. • Risks rates are based on the 1% most serious accidents 1998–Feb 2004. • Risk rates are used to predict serious accident risks in jobs and sectors. • Predictions (“risk horoscopes”) give a good match with actual accidents. • Risk horoscopes can help worker groups identify most important accident risks

  12. Two decades of radiological accidents direct causes, roots causes and consequences

    Directory of Open Access Journals (Sweden)

    Rozental Jose de Julio

    2002-01-01

    Full Text Available Practically all Countries utilize radioisotopes in medicine, industry, agriculture and research. The extent to which ionizing radiation practices are employed varies considerably, depending largely upon social and economic conditions and the level of technical skills available in the country. An overview of the majority of practices and the associated hazards will be found in the Table IV to VII of this document. The practices in normal and abnormal operating conditions should follow the basic principles of radiation protection and the Safety of Radiation Sources, considering the IAEA Radiation Protection and the Safety of Radiation Sources, Safety Series 120 and the IAEA Recommendation of the Basic Safety Standards for Radiation Protection, Safety Series Nº 115. The Standards themselves underline the necessity to be able to predict the radiological consequences of emergency conditions and the investigations that should need to be done. This paper describes the major accidents that had happened in the last two decades, provides a methodology for analyses and gives a collection of lessons learned. This will help the Regulatory Authority to review the reasons of vulnerabilities, and to start a Radiation safety and Security Programme to introduce measurescapable to avoid the recurrence of similar events. Although a number of accidents with fatalities have caught the attention of the public in recent year, a safety record has accompanied the widespread use of radiation sources. However, the fact that accidents are uncommon should not give grounds for complacency. No radiological accident is acceptable. From a radiation safety and security of the sources standpoint, accident investigation is necessary to determine what happened, why, when, where and how it occurred and who was (were involved and responsible. The investigation conclusion is an important process toward alertness and feedback to avoid careless attitudes by improving the comprehension

  13. Storage and transport of hazardous materials

    International Nuclear Information System (INIS)

    Jaeger, P.; Haferkamp, K.

    1986-01-01

    The attempt has been made to characterise the present risk scenario, and to set out approaches or methods for remedy and risk control. For this purpose, a retrospective analysis has been made of accidents, damage and consequential damage that occurred in the past either during storage of hazardous materials, or during road transport. A risk-benefit model facilitates assessment of accident frequency. The history of accidents during storage or transport allows assessment of the dangerousness of various materials. Another important aspect discussed is the property and behaviour of containers used for storage or transport. (DG) [de

  14. Severe accident tests and development of domestic severe accident system codes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)

  15. Severe accident tests and development of domestic severe accident system codes

    International Nuclear Information System (INIS)

    2013-01-01

    According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)

  16. 77 FR 45417 - Pipeline Safety: Inspection and Protection of Pipeline Facilities After Railway Accidents

    Science.gov (United States)

    2012-07-31

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Accidents AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. [[Page 45418

  17. Hemijski udesi i procena rizika / Chemical accidents and hazard assessment

    Directory of Open Access Journals (Sweden)

    Rade Biočanin

    2004-09-01

    Full Text Available Brojni su udesi vezani za transport i upotrebu hemijskih materija. Ova činjenica je važna i zbog toga što se naša zemlja nalazi na raskrsnici značajnih svetskih komunikacija kojima se ovakvi tereti prevoze. Veliki broj vrsta hemijskih materija može znatno da naruši životnu sredinu za duži period. Ovaj rad, kroz različite parametre, nastoji da prouči takvu mogućnost i ukaže na načine za prevenciju sličnih događaja i zaštitu stanovništva u miru i tokom ratnih dejstava. Ostvarenje projekta jedinstvenog sistema ABHO daje mogućnost da se, korišćenjem savremene opreme za komunikaciju i efikasnih jedinica za brzo reagovanje u realnom vremenu, uspešno obavi monitoring opasnosti, uzbunjivanje, zaštita i dekontaminacija. / There is a growing number of accidents involving hazardous chemical substances during transportation. Serbia and Montenegro are at the crossroads of numerous important European transport links where a lot of such transports pass through. A great number of such substances can considerably damage environment for a very long period of time. This paper studies such events applying different parameters; it tries to point at successful prevention and protection from this threat at peace, as well as during war operations. The realization of the universal and united system of the NBCD of the Army of Serbia and Montenegro, together with modern communication equipment and very effective mobile units, enables on - time reaction and successful monitoring, alarming, protection and decontamination.

  18. Transportation accidents/incidents involving radioactive materials (1971--1991)

    International Nuclear Information System (INIS)

    Cashwell, C.E.; McClure, J.D.

    1992-01-01

    The Radioactive Materials Incident Report (RMIR) database contains information on transportation-related accidents and incidents involving radioactive materials that have occurred in the United States. The RMIR was developed at Sandia National Laboratories (SNL) to support its research and development program efforts for the US Department of Energy (DOE). This paper will address the following topics: background information on the regulations and process for reporting a hazardous materials transportation incident, overview data of radioactive materials transportation accidents and incidents, and additional information and summary data on how packagings have performed in accident conditions

  19. Risk perceptions and technological hazards: a contextual view

    International Nuclear Information System (INIS)

    Walker, G.; Simmons, P.; Irwin, A.; Wynne, B.

    1998-01-01

    Full text of publication follows: the study of public perceptions of risk has given rise to a number of different (and sometimes conflicting) perspectives. Although the differences between these approaches are not trivial, recent reviews have suggested that there may be some points of convergence. In particular, recent work within the different traditions has emphasised the importance of factors such as trust and power for understanding public perceptions of risk. These factors take us beyond the characteristics of the risks themselves, which were the focus of influential work in the psychometric tradition and into a consideration of the social and cultural context within which potentially hazardous technologies are encountered and evaluated. In this paper we examine the way in which the lay public understand and respond to a particular class of technological risks - those associated with site-based major accident hazards. On the basis of empirical research, we argue that an appreciation of the different contexts within which citizens encounter such risks is crucial to understanding the dynamics of public concerns. We illustrate our argument by examining the different ways in which contextual factors influence perceptions. The discussion draws upon a recently completed study of public perceptions of the risks at seven major hazard sites in the UK, which was funded the by UK Health and Safety Executive. (authors)

  20. Incidents with hazardous radiation sources

    International Nuclear Information System (INIS)

    Schoenhacker, Stefan

    2016-01-01

    Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

  1. Chernobyl and Fukushima nuclear accidents: what has changed in the use of atmospheric dispersion modeling?

    Science.gov (United States)

    Benamrane, Y; Wybo, J-L; Armand, P

    2013-12-01

    The threat of a major accidental or deliberate event that would lead to hazardous materials emission in the atmosphere is a great cause of concern to societies. This is due to the potential large scale of casualties and damages that could result from the release of explosive, flammable or toxic gases from industrial plants or transport accidents, radioactive material from nuclear power plants (NPPs), and chemical, biological, radiological or nuclear (CBRN) terrorist attacks. In order to respond efficiently to such events, emergency services and authorities resort to appropriate planning and organizational patterns. This paper focuses on the use of atmospheric dispersion modeling (ADM) as a support tool for emergency planning and response, to assess the propagation of the hazardous cloud and thereby, take adequate counter measures. This paper intends to illustrate the noticeable evolution in the operational use of ADM tools over 25 y and especially in emergency situations. This study is based on data available in scientific publications and exemplified using the two most severe nuclear accidents: Chernobyl (1986) and Fukushima (2011). It appears that during the Chernobyl accident, ADM were used few days after the beginning of the accident mainly in a diagnosis approach trying to reconstruct what happened, whereas 25 y later, ADM was also used during the first days and weeks of the Fukushima accident to anticipate the potentially threatened areas. We argue that the recent developments in ADM tools play an increasing role in emergencies and crises management, by supporting stakeholders in anticipating, monitoring and assessing post-event damages. However, despite technological evolutions, its prognostic and diagnostic use in emergency situations still arise many issues. Copyright © 2013 Elsevier Ltd. All rights reserved.

  2. Utilisation of a Helicopter Emergency Medical Service (HEMS) for equestrian accidents in a regional major trauma network in the United Kingdom.

    Science.gov (United States)

    McQueen, Carl; Crombie, Nick; Cormack, Stef; George, Arun; Wheaton, Steve

    2015-05-01

    The utilisation of Helicopter Emergency Medical Services (HEMS) in response to equestrian accidents has been an integral part of operations for many years throughout the UK. The recent establishment of major trauma networks in the UK has placed great emphasis on the appropriate tasking of HEMS units to cases where added benefit can be provided and the incidence of time critical injury in cases of equestrian accidents has been shown to be low. This study assesses the impact made on the utilisation of the different HEMS resources for cases of equestrian accidents within the West Midlands following the launch of the regional trauma network. We present a retrospective analysis of all equestrian accidents attended by Midlands Air Ambulance (MAA) between 1 April 2012 and 1 April 2013. Data were abstracted from the MAA operational database relating to mission activations/scene attendances; team configuration (physician led and Critical Care Paramedic (CCP) led); on-scene interventions; mission timings and patient conveyance by helicopter. A total of 114 activations involved equestrian accidents (6% of overall workload). The contribution of equestrian accidents to overall workload was similar for physician led and CCP-led (69/1069) platforms (5% vs. 6%, p=0.50). Only three patients (3%) required pre-hospital RSI during the period analysed and there were no recorded cases of ketamine administration for analgesia/conscious sedation. In approximately half of all scene attendances patients did not require any medication to be administered by the HEMS team. The vast majority of incidents occurred in rural locations with over 80% of patients conveyed to hospital by helicopter. The average mission time for scene attendances resulting in conveyance by helicopter was in excess of 90 min on both types of platform. There is a clear requirement for the design and implementation of informed and intelligent tasking models to respond to the need for assistance in equestrian accidents

  3. Civil nuclear: which hazards?

    International Nuclear Information System (INIS)

    2011-01-01

    This document briefly indicates and describes the various hazards of exposure to radioactivity in relationship with the different stages of exploitation of nuclear energy: mining, exploitation, fuel reprocessing and waste management. It briefly presents and describes the scenarios associated with major risks in the exploitation phase: core fusion (description, possible origins, consequences in terms of possible releases), formation of hydrogen (chemical reaction, risk of explosion with releases, failure modes for the containment enclosure). It proposes a brief overview of consequences for mankind and for the environment due to irradiation and contamination. A brief assessment of major nuclear accidents is given, with an indication of their severity INES classification (Kyshtym, Three Mile Island, Chernobyl, Fukushima). It evokes incidents which occurred in France, and outlines the main challenges and stakes in terms of risk prevention, of plant control, of nuclear material and waste management, of public information, and of struggle against nuclear weapon proliferation. Actors and their roles are indicated: operator (EDF in France), control authority (ASN), actors in charge of waste management (ANDRA), research and information institutions (CEA, IRSN, CRIIRAD), international scientific bodies (UNSCEAR)

  4. Assessment of risk of accident at work as an indicator of safe behaviour of workers

    Energy Technology Data Exchange (ETDEWEB)

    Pisiewicz, K

    1978-10-01

    In 1977 the Psychology and Sociology Research Development Unit of the Central Mining Institute carried out research on the influence of assessment of the accident risk on the safe behaviour of workers. 450 workers employed at the longwall faces in 6 coal mines with various accident rates were questioned. It was found that a low assessment of risk favours hazardous operations, contrary to the principles of work safety, while a high assessment of the risk does not favour hazardous operations. Miners employed in coal mines with high accident rates tend to a low assessment of accident risk (arithmetic mean x 48.54) in comparison to miners from mines with low accident rates (arithmetic mean x 53.68). It was also found that the arithmetic mean of assessment of risks among workers who had had an accident at work is lower (x 50.3) than among workers who had not yet had an accident at work (x 55.32).

  5. Transportation of hazardous materials (hazmat) a literature survey

    OpenAIRE

    Zafer YILMAZ; Serpil EROL; Hakan Soner APLAK

    2016-01-01

    ransportation has a great role in logistics. Many researchers have studied on transportation and vehicle routing problems. Transportation of hazardous materials (hazmat) is a special subject for logistics. Causalities due to the accidents caused by trucks carrying hazardous materials will be intolerable. Many researchers have studied on risk assessment of hazmat transportation to find ways for reducing hazardous material transportation risks. Some researchers have studied routing of hazmat tr...

  6. Accident history, risk perception and traffic safe behaviour.

    Science.gov (United States)

    Ngueutsa, Robert; Kouabenan, Dongo Rémi

    2017-09-01

    This study clarifies the associations between accident history, perception of the riskiness of road travel and traffic safety behaviours by taking into account the number and severity of accidents experienced. A sample of 525 road users in Cameroon answered a questionnaire comprising items on perception of risk, safe behaviour and personal accident history. Participants who reported involvement in more than three accidents or involvement in a severe accident perceived road travel as less risky and also reported behaving less safely compared with those involved in fewer, or less severe accidents. The results have practical implications for the prevention of traffic accidents. Practitioner Summary: The associations between accident history, perceived risk of road travel and safe behaviour were investigated using self-report questionnaire data. Participants involved in more than three accidents, or in severe accidents, perceived road travel as less risky and also reported more unsafe behaviour compared with those involved in fewer, or less severe accidents. Campaigns targeting people with a less serious, less extensive accident history should aim to increase awareness of hazards and the potential severity of their consequences, as well as emphasising how easy it is to take the recommended preventive actions. Campaigns targeting those involved in more frequent accidents, and survivors of serious accidents, should address feelings of invulnerability and helplessness.

  7. Development of Database for Accident Analysis in Indian Mines

    Science.gov (United States)

    Tripathy, Debi Prasad; Guru Raghavendra Reddy, K.

    2016-10-01

    Mining is a hazardous industry and high accident rates associated with underground mining is a cause of deep concern. Technological developments notwithstanding, rate of fatal accidents and reportable incidents have not shown corresponding levels of decline. This paper argues that adoption of appropriate safety standards by both mine management and the government may result in appreciable reduction in accident frequency. This can be achieved by using the technology in improving the working conditions, sensitising workers and managers about causes and prevention of accidents. Inputs required for a detailed analysis of an accident include information on location, time, type, cost of accident, victim, nature of injury, personal and environmental factors etc. Such information can be generated from data available in the standard coded accident report form. This paper presents a web based application for accident analysis in Indian mines during 2001-2013. An accident database (SafeStat) prototype based on Intranet of the TCP/IP agreement, as developed by the authors, is also discussed.

  8. Hazard screening application guide

    International Nuclear Information System (INIS)

    1992-06-01

    The basic purpose of hazard screening is to group precesses, facilities, and proposed modifications according to the magnitude of their hazards so as to determine the need for and extent of follow on safety analysis. A hazard is defined as a material, energy source, or operation that has the potential to cause injury or illness in human beings. The purpose of this document is to give guidance and provide standard methods for performing hazard screening. Hazard screening is applied to new and existing facilities and processes as well as to proposed modifications to existing facilities and processes. The hazard screening process evaluates an identified hazards in terms of the effects on people, both on-site and off-site. The process uses bounding analyses with no credit given for mitigation of an accident with the exception of certain containers meeting DOT specifications. The process is restricted to human safety issues only. Environmental effects are addressed by the environmental program. Interfaces with environmental organizations will be established in order to share information

  9. LOFA [loss of flow accident] and LOCA [loss of coolant accident] in the TIBER-II engineering test reactor: Appendix A-4

    International Nuclear Information System (INIS)

    Sviatoslavsky, I.N.; Attaya, H.M.; Corradini, M.L.; Lomperski, S.

    1987-01-01

    This paper describes the preliminary analysis of LOFA (loss of flow accident) and LOCA (loss of coolant accident) in the TIBER-II engineering test reactor breeding shield. TIBER-II is a compact reactor with a major radius of 3 m and thus requires a thin, high efficiency shield on the inboard side. The use of tungsten in the inboard shield implies a rather high rate of afterheat upon plasma shutdown, which must be dissipated in a controlled manner to avoid the possibility of radioactivity release or threatening the investment. Because the shield is cooled with an aqueous solution, LOFA does not pose a problem as long as natural convection can be established. LOCA, however, has more serious consequences, particularly on the inboard side. Circulation of air by natural convection is proposed as a means for dissipating the inboard shield decay heat. The safety and environmental implications of such a scheme are evaluated. It is shown that the inboard shield temperature never exceeds 510 0 C following LOCA posing no hazard to reactor personnel and not threatening the investment. 7 refs., 6 figs

  10. A RULE-BASED SYSTEM APPROACH FOR SAFETY MANAGEMENT IN HAZARDOUS WORK SYSTEMS

    Directory of Open Access Journals (Sweden)

    Ercüment N. DİZDAR

    1998-03-01

    Full Text Available Developments in technology increased the importance of safety management in work life. These improvements also resulted in a requirement of more investment and assignment on human in work systems. Here we face this problem: Can we make it possible to forecast the possible accidents that workers can face, and prevent these accidents by taking necessary precautions? In this study made, we aimed at developing an rule-based system to forecast the occupational accidents in coming periods at the departments of the facilities in hazardous work systems. The validity of the developed system was proved by implementing it into practice in hazardous work systems in manufacturing industry.

  11. Barrow hazards survey

    International Nuclear Information System (INIS)

    1980-06-01

    Following a series of public meetings at which PERG presented the results of a literature review and site specific accident study of the hazards of the maritime transport of spent nuclear reactor fuel to Barrow (en route to the Windscale reprocessing works), PERG was requested by the Planning Committee of Barrow Town Council to prepare an assessment of the interaction of the hazards arising from the concentration of nuclear activities in the area with those of a proposed gas-terminal. This report presents a preliminary review of the Environmental Impact Assessments prepared by the Borough Surveyor and a critical appraisal of the hazard analyses undertaken by the Health and Safety Executive, and the consultants to Cumbria County Council on this matter, the Safety and Reliability Directorate of the United Kingdom Atomic Energy Authority. After a general and historical introduction, the document continues under the following headings: a description of the hazards (BNFL spent fuel shipments; the gas terminal; gas condensate storage; the Vickers shipyard (involving nuclear powered submarines)); the interaction of hazards; planning implications and democratic decisions; recommendations. (U.K.)

  12. Chemical and nuclear emergencies: Interchanging lessons learned from planning and accident experience

    International Nuclear Information System (INIS)

    Adler, V.; Sorensen, J.H.; Rogers, G.O.

    1989-01-01

    Because the goal of emergency preparedness for both chemical and nuclear hazards is to reduce human exposure to hazardous materials, this paper examines the interchange of lessons learned from emergency planning and accident experience in both industries. While the concerns are slightly different, sufficient similarity is found for each to draw implications from the others experience. Principally the chemical industry can learn from the dominant planning experience associated with nuclear power plants, while the nuclear industry can chiefly learn from the chemical industry's accident experience. 23 refs

  13. Hazards analysis of TNX Large Melter-Off-Gas System

    International Nuclear Information System (INIS)

    Randall, C.T.

    1982-03-01

    Analysis of the potential safety hazards and an evaluation of the engineered safety features and administrative controls indicate that the LMOG System can be operated without undue hazard to employees or the public, or damage to equipment. The safety features provided in the facility design coupled with the planned procedural and administrative controls make the occurrence of serious accidents very improbable. A set of recommendations evolved during this analysis that was judged potentially capable of further reducing the probability of personnel injury or further mitigating the consequences of potential accidents. These recommendations concerned areas such as formic acid vapor hazards, hazard of feeding water to the melter at an uncontrolled rate, prevention of uncontrolled glass pours due to melter pressure excursions and additional interlocks. These specific suggestions were reviewed with operational and technical personnel and are being incorporated into the process. The safeguards provided by these recommendations are discussed in this report

  14. Toward risk assessment 2.0: Safety supervisory control and model-based hazard monitoring for risk-informed safety interventions

    International Nuclear Information System (INIS)

    Favarò, Francesca M.; Saleh, Joseph H.

    2016-01-01

    Probabilistic Risk Assessment (PRA) is a staple in the engineering risk community, and it has become to some extent synonymous with the entire quantitative risk assessment undertaking. Limitations of PRA continue to occupy researchers, and workarounds are often proposed. After a brief review of this literature, we propose to address some of PRA's limitations by developing a novel framework and analytical tools for model-based system safety, or safety supervisory control, to guide safety interventions and support a dynamic approach to risk assessment and accident prevention. Our work shifts the emphasis from the pervading probabilistic mindset in risk assessment toward the notions of danger indices and hazard temporal contingency. The framework and tools here developed are grounded in Control Theory and make use of the state-space formalism in modeling dynamical systems. We show that the use of state variables enables the definition of metrics for accident escalation, termed hazard levels or danger indices, which measure the “proximity” of the system state to adverse events, and we illustrate the development of such indices. Monitoring of the hazard levels provides diagnostic information to support both on-line and off-line safety interventions. For example, we show how the application of the proposed tools to a rejected takeoff scenario provides new insight to support pilots’ go/no-go decisions. Furthermore, we augment the traditional state-space equations with a hazard equation and use the latter to estimate the times at which critical thresholds for the hazard level are (b)reached. This estimation process provides important prognostic information and produces a proxy for a time-to-accident metric or advance notice for an impending adverse event. The ability to estimate these two hazard coordinates, danger index and time-to-accident, offers many possibilities for informing system control strategies and improving accident prevention and risk mitigation

  15. Risks to offshore installations in Europe due to natural hazards

    Science.gov (United States)

    Necci, Amos; Krausmann, Elisabeth

    2017-04-01

    Natural hazards, such as storms, earthquakes, or lightning are a major threat to industry. In particular, chemical plants, storage facilities, pipelines, and offshore oil and gas facilities are vulnerable to natural events which can cause hazardous materials releases and thereby endanger workers, the population and the environment. These technological accidents are commonly referred to as Natech accidents. Recent events have increased concerns about safety in the offshore oil and gas sector, and the need for improving knowledge on the matter has become evident. With those premises, we analyzed accidents, near misses and accident precursors at offshore facilities in Europe caused by natural events using both a statistical and a qualitative approach. For this purpose, we screened the World Offshore Accident Database (WOAD) to identify all incidents that featured natural events as causes or aggravating factors. A dataset of 1,085 global Natech events was built for the statistical analysis. Among those, a subset composed of 303 European records was selected. The results of the analysis showed that offshore Natech events in Europe are frequent; they resulted, however, in low consequences. The main threat to offshore facilities resulted from bad weather, such as strong winds and heavy seas. Storms can put intense loads on the structural parts of offshore installations, eventually exceeding design resistance specifications. Several incidents triggered by lightning strikes and earthquakes were also recorded. Substantial differences in terms of vulnerability, damage modality and consequences emerged between fixed and floating offshore structures. The main damage mode for floating structures was the failure of station keeping systems due to the rupture of mooring or anchors, mainly caused by adverse meteorological conditions. Most of the incidents at fixed offshore structures in Europe involved falling loads for both metal jacket and concrete base platforms due to storms. In

  16. A hazard and probabilistic safety analysis of a high-level waste transfer process

    International Nuclear Information System (INIS)

    Bott, T.F.; Sasser, M.K.

    1996-01-01

    This paper describes a safety analysis of a transfer process for high-level radioactive and toxic waste. The analysis began with a hazard assessment that used elements of What If, Checklist, Failure Modes and Effects Analysis, and Hazards and Operability Study (HAZOP) techniques to identify and rough-in accident sequences. Based on this preliminary analysis, the most significant accident sequences were developed further using event trees. Quantitative frequency estimates for the accident sequences were based on operational data taken from the historical record of the site where the process is performed. Several modeling challenges were encountered in the course of the study. These included linked initiating and accident progression events, fire propagation modeling, accounting for administrative control violations, and handling mission-phase effects

  17. Major accident prevention through applying safety knowledge management approach.

    Science.gov (United States)

    Kalatpour, Omid

    2016-01-01

    Many scattered resources of knowledge are available to use for chemical accident prevention purposes. The common approach to management process safety, including using databases and referring to the available knowledge has some drawbacks. The main goal of this article was to devise a new emerged knowledge base (KB) for the chemical accident prevention domain. The scattered sources of safety knowledge were identified and scanned. Then, the collected knowledge was formalized through a computerized program. The Protégé software was used to formalize and represent the stored safety knowledge. The domain knowledge retrieved as well as data and information. This optimized approach improved safety and health knowledge management (KM) process and resolved some typical problems in the KM process. Upgrading the traditional resources of safety databases into the KBs can improve the interaction between the users and knowledge repository.

  18. Analysis on Dangerous Source of Large Safety Accident in Storage Tank Area

    Science.gov (United States)

    Wang, Tong; Li, Ying; Xie, Tiansheng; Liu, Yu; Zhu, Xueyuan

    2018-01-01

    The difference between a large safety accident and a general accident is that the consequences of a large safety accident are particularly serious. To study the tank area which factors directly or indirectly lead to the occurrence of large-sized safety accidents. According to the three kinds of hazard source theory and the consequence cause analysis of the super safety accident, this paper analyzes the dangerous source of the super safety accident in the tank area from four aspects, such as energy source, large-sized safety accident reason, management missing, environmental impact Based on the analysis of three kinds of hazard sources and environmental analysis to derive the main risk factors and the AHP evaluation model is established, and after rigorous and scientific calculation, the weights of the related factors in four kinds of risk factors and each type of risk factors are obtained. The result of analytic hierarchy process shows that management reasons is the most important one, and then the environmental factors and the direct cause and Energy source. It should be noted that although the direct cause is relatively low overall importance, the direct cause of Failure of emergency measures and Failure of prevention and control facilities in greater weight.

  19. An Examination of Aviation Accidents Associated with Turbulence, Wind Shear and Thunderstorm

    Science.gov (United States)

    Evans, Joni K.

    2013-01-01

    The focal point of the study reported here was the definition and examination of turbulence, wind shear and thunderstorm in relation to aviation accidents. NASA project management desired this information regarding distinct subgroups of atmospheric hazards, in order to better focus their research portfolio. A seven category expansion of Kaplan's turbulence categories was developed, which included wake turbulence, mountain wave turbulence, clear air turbulence, cloud turbulence, convective turbulence, thunderstorm without mention of turbulence, and low altitude wind shear, microburst or turbulence (with no mention of thunderstorms).More than 800 accidents from flights based in the United States during 1987-2008 were selected from a National Transportation Safety Board (NTSB) database. Accidents were selected for inclusion in this study if turbulence, thunderstorm, wind shear or microburst was considered either a cause or a factor in the accident report, and each accident was assigned to only one hazard category. This report summarizes the differences between the categories in terms of factors such as flight operations category, aircraft engine type, the accident's geographic location and time of year, degree of injury to aircraft occupants, aircraft damage, age and certification of the pilot and the phase of flight at the time of the accident.

  20. To revisit economics of nuclear technology. Lessons from the learning of a complex technology by major accidents

    International Nuclear Information System (INIS)

    Finon, Dominique

    2012-05-01

    The Fukushima accident raises again the issue of the social and economic viability of nuclear technology. To re-evaluate this viability, we analyse the past process of internalisation of external costs of nuclear energy, which present the specificities to be chanted by accidents and has had a constant effect of complexification. This process has provoked a de-organisation of the classical learning process reflected in constant cost increases and the change of social preferences, to end up by the lack of competitiveness before climate policies. Independent institutions of safety regulation have become essential elements of the social embeddedness of nuclear technology at the expense of technology stability and standardization, condition of its competitiveness. In this perspective, the paper argues that the new sequence of social costs' internalization opened by Fukushima will have limited effects on costs, because of anterior steps of safety improvements. Nuclear technology complexification reaches its asymptote: it is being to overcome the challenge of 'learning by major accidents'. On the other hand nuclear institutions must be re-designed in such a way that it could guarantee maximum safety records and minimum residual risks by going to the other root of the safety issue, the degree of independence and capabilities of the safety authorities in every country, what cannot be decreed. It is nevertheless at this price that could be preserved the global public good of the social acceptance of nuclear technology by limiting drastically chance of new accidents. (author)

  1. Medical aid in the initial period of radiation accident

    International Nuclear Information System (INIS)

    Selidovkin, G.D.

    1995-01-01

    The main tasks of medical arrangements on the initial stage of rendering aid after radiation accident are the prime medical classification of the injured persons among the personnel of the plant and population, and realization of measures to avoid the increase of doses. The volume of medical aid depends on the type of accident, on the after-accident radiation situation, on the influence of hazardous factors, on the number of people involved in accident situation and the spectrum of sanitary losses, etc., which is to be predicted in advance and to be taken into consideration when rendering aid. The proper and sufficient aid on the initial stage will build the foundation of the ultimate efficiency of medical aid after radiation accident. 14 refs

  2. Hazardous materials incidents on major highways -- A case study

    International Nuclear Information System (INIS)

    McElhaney, M.S.

    1995-01-01

    Personnel from both the public and private sectors have been involved for many years in pre-planning for hazardous materials releases at fixed installations all over the world. As a result of several major petroleum releases during marine transportation, oil companies, private contractors and government agencies have been preparing contingency plans for oil spills and other petroleum product releases in marine settings. Various industry groups have also developed plans for railway and pipeline disasters. These response plans are of varying quality, complexity and usefulness. Organizations such as plant emergency response teams, government agencies, contract response and clean-up crews and fire departments use these plans as a basis for training and resource allocation, hopefully becoming familiar enough with them that the plans are truly useful when product releases occur. Planners and emergency responders to hazardous materials releases must overcome some of the deficiencies which have long stood in the way of efficient and effective response and mitigation efforts. Specifically they must recognize and involve all resources with which they may respond or interact during an incident. This involvement should begin with the planning stages and carry through to training and emergency response and recovery efforts. They must ensure that they adopt and utilize a common command and control system and that all potential resources know this system thoroughly and train together before the incident occurs. It is only through incorporating these two factors that may successfully combat the ever growing number of unwanted product releases occurring in the more difficult realm of transportation

  3. Effective tree hazard control on forested recreation sites...losses and protection costs evaluated

    Science.gov (United States)

    Lee A. Paine

    1967-01-01

    Effectiveness of hazard control was evaluated by analyzing data on tree failures, accidents, and control costs on California recreation sites. Results indicate that reduction of limb hazard in oaks and bole hazard in conifers is the most effective form of control. Least effective is limb hazard reduction in conifers. After hazard control goals or control budgets have...

  4. Screening for hazardous drinking using the Michigan Alcohol Screening Test-Geriatric Version (MAST-G) in elderly persons with acute cerebrovascular accidents.

    Science.gov (United States)

    Johnson-Greene, Doug; McCaul, Mary E; Roger, Patricia

    2009-09-01

    Effective and valid screening methods are needed to identify hazardous drinking in elderly persons with new onset acute medical illness. The goal of the current study was to examine the effectiveness of the Michigan Alcohol Screening Test-Geriatric Version (MAST-G) in identifying hazardous drinking among elderly patients with acute cerebrovascular accidents (CVA) and to compare the effectiveness of 2 shorter versions of the MAST-G with the full instrument. The study sample included 100 men and women who averaged 12 days posthemorrhagic or ischemic CVA admitted to a rehabilitation unit and who were at least 50 years of age and free of substance use other than alcohol. This cross-sectional validation study compared the 24-item full MAST-G, the 10-item Short MAST-G (SMAST-G), and a 2-item regression analysis derived Mini MAST-G (MMAST-G) to the reference standard of hazardous drinking during the past 3 months. Alcohol use was collected using the Timeline Followback (TLFB). Recent and lifetime alcohol-related consequences were collected using the Short Inventory of Problems (SIP). Nearly one-third (28%) of the study sample met the World Health Organization (WHO) criteria for hazardous drinking. Moderately strong associations were found for the MAST-G, SMAST-G, and MMAST-G with alcohol quantity and frequency and recent and lifetime alcohol consequences. All 3 MAST-G versions could differentiate hazardous from nonhazardous drinkers and had nearly identical area under the curve characteristics. Comparable sensitivity was found across the 3 MAST-G measures. The optimal screening threshold for hazardous drinking was 5 for the MAST-G, 2 for the SMAST-G, and 1 for the MMAST-G. The 10-item SMAST-G and 2-item MMAST-G are brief screening tests that show comparable effectiveness in detecting hazardous drinking in elderly patients with acute CVA compared with the full 24-item MAST-G. Implications for research and clinical practice are discussed.

  5. Strategies for the protection of the environment from other hazards

    International Nuclear Information System (INIS)

    Ruffing, K.

    2002-01-01

    Strategies for the protection of the environment from radiological hazards may benefit from a consideration of risk management strategies applied in other areas. This paper attempts to do that with respect to the way the OECD has addressed these issues. The paper briefly describes the approach developed within the OECD on harmonization and common approaches to chemicals risk management, related work by the Organisation on major industrial accidents and natural disasters, and places the relationship of chemical and radiological risk management in the context of the OECD Environmental Strategy for the First Decade of the Twenty-first Century. (author)

  6. Hazard and consequence analysis for waste emplacement at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Gerstner, D.M.; Clayton, S.G.; Farrell, R.F.; McCormick, J.A.; Ortiz, C.; Standiford, D.L.

    1996-01-01

    The Carlsbad Area Office established and analyzed the safety bases for the design and operations as documented in the WIPP Safety Analysis Report (SAR). Additional independent efforts are currently underway to assess the hazards associated with the long-term (10,000 year) isolation period as required by 40 CFR 191. The structure of the WIPP SAR is unique due to the hazards involved, and the agreement between the State of New Mexico and the DOE regarding SAR content and format. However, the hazards and accident analysis philosophy as contained in DOE-STD-3009-94 was followed as closely as possible, while adhering to state agreements. Hazards associated with WIPP waste receipt, emplacement, and disposal operations were systematically identified using a modified Hazard and Operability Study (HAZOP) technique. The WIPP HAZOP assessed the potential internal, external, and natural phenomena events that can cause the identified hazards to develop into accidents. The hazard assessment identified deviations from the intended design and operation of the waste handling system, analyzed potential accident consequences to the public and workers, estimated likelihood of occurrence, and evaluated associated preventative and mitigative features. It was concluded from the assessment that the proposed WIPP waste emplacement operations and design are sufficient to ensure safety of the public, workers, and environment, over the 35 year disposal phase

  7. The perception of hazards

    International Nuclear Information System (INIS)

    Fritzsche, A.F.

    1986-01-01

    The fourth chapter deals with the profusion of factors determining the differing assessment of hazards by our society. Subjective factors influencing risk perception comprise, among others, general knowledge and recognition of a hazard; the degree of voluntariness when taking the risk and its influencibility; the problem of large scale accidents; immediate and delayed results. Next to the objective and the subjective risks, the individual and the social or collective risks are assessed differently. The author dicusses in detail recent investigations into and study methods for the determination of risk perception, while eliminating systematic trends from subjective perception since common assessments are shared by whole groups of individuals time and again which allow a better understanding of today's handling of hazards. (HSCH) [de

  8. A study on hazard types occurring in hydrogen facilities

    International Nuclear Information System (INIS)

    Cho, Nam Chul; Jae, Moo Sung; Eon, Yang Joon

    2004-01-01

    Hydrogen has ideal characteristics as an energy carrier. Hydrogen can be used as a clean fuel in a variety of energy end-use sectors including the conversion to electricity. After combustion, it produces only water. Therefore, the concept of hydrogen energy system has attracted much interest worldwide. But hydrogen has a defect that the explosion risk is high to an inflammable gas of a colorless, tasteless and odorless. Therefore, to use the hydrogen to the source of energy, hydrogen accident sequences and causes analysis must be needed. For this, hazard types occurring in hydrogen facilities have been considered through the case of domestic and foreign hydrogen accident in this study and hazard types to be considered are ignition, leaks, hydrogen dispersion, fire an explosion, storage vessel failure, vent and exhaust system, purging, condensation of air, hydrogen embrittlement, physiological hazard, and collisions during transportation

  9. 78 FR 60755 - Hazardous Materials: Enhanced Enforcement Procedures-Resumption of Transportation

    Science.gov (United States)

    2013-10-02

    ... material,'' we envisioned etiological agents, such as biological products, infectious substances, medical... accidents or incidents involving the transportation of hazardous material. In order to achieve a uniform... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part...

  10. The hazards of coal (other than the greenhouse effect)

    International Nuclear Information System (INIS)

    Durand, Bernard

    2012-01-01

    After an introduction in which he outlines the major role of coal in CO 2 emissions and the health effects associated with coal and, more precisely, with the various hazardous elements it contains, and also evokes the different types of coals and their difference with hydrocarbons, the author proposes an overview of coal production, uses, resources and reserves. He addresses the different environmental and health risks associated with coal: those related to exploitation and transport (direct mortality due to accidents, delayed mortality due to occupational diseases), those related to the use of coal (related to combustion products, to domestic use, to electricity production by coal-fired plants)

  11. Hazard analysis in uranium hexafluoride production facility

    International Nuclear Information System (INIS)

    Marin, Maristhela Passoni de Araujo

    1999-01-01

    The present work provides a method for preliminary hazard analysis of nuclear fuel cycle facilities. The proposed method identify both chemical and radiological hazards, as well as the consequences associated with accident scenarios. To illustrate the application of the method, a uranium hexafluoride production facility was selected. The main hazards are identified and the potential consequences are quantified. It was found that, although the facility handles radioactive material, the main hazards as associated with releases of toxic chemical substances such as hydrogen fluoride, anhydrous ammonia and nitric acid. It was shown that a contention bung can effectively reduce the consequences of atmospheric release of toxic materials. (author)

  12. THE ATMOSPHERE PROTECTION FROM AN ACCIDENT WITH HAZARDOUS CHEMICAL CARGO

    Directory of Open Access Journals (Sweden)

    V. M. Lysniak

    2009-09-01

    Full Text Available The 3D CFD model to simulate the pollutant transfer and the process of neutralization of toxic gas after accidents was developed. The model is based on the transport gradient model. The results of numerical experiments are presented.

  13. Managing severe reactor accidents. A review and evaluation of our knowledge on reactor accidents and accident management

    International Nuclear Information System (INIS)

    Gustavsson, Veine

    2002-11-01

    The report gives a review of the results from the last years research on severe reactor accidents, and an opinion on the possibilities to refine the present strategies for accident management in Swedish and Finnish BWRs. The following aspect of reactor accidents are the major themes of the study: 1. Early pressure relief from hydrogen production; 2. Recriticality in re-flooded, degraded core; 3. Melt-through; 4. Steam explosion after melt-through; 5. Coolability of the melt after after melt-through; 6. Hydrogen fire in the reactor containment; 7. Leaking containment; 8. Hydrogen fire in the reactor building; 9. Long-time developments after a severe accident; 10. Accidents during shutdown for overhaul; 11. Information need for remedial actions. Possibilities for improving the strategies in each of these areas are discussed. The review shows that our knowledge is sufficient in the areas 1, 2, 4, 6, 8. For the other areas, more research is needed

  14. Identification of Hazardous Road Locations on the basis of Floating Car Data

    DEFF Research Database (Denmark)

    Agerholm, Niels; Lahrmann, Harry

    2012-01-01

    A central aspect of road safety work relies on identification of hazardous road locations (HRL). However, the said identification is based on police-reported accidents, which show massive underreporting. Thus, in Denmark, only 14% of the serious injury accidents were reported in 2007...

  15. Chernobyl - an evaluation of health hazards. 3. Enl. and Rev. Ed. Tschernobyl - eine Einschaetzung der gesundheitlichen Schaeden

    Energy Technology Data Exchange (ETDEWEB)

    Huber, E E; Dersee, T; Iwert, B

    1986-01-01

    The pamphlet abstracted contains some general information about the radiation hazards and health risks of nuclear power plants. The consequences of the Chernobyl reactor accident are dealt with by way of summarizing the events and by evaluating the health risks and damage the public should be prepared for. This topical report is completed by a popular presentation of the risks of nuclear power and by definitions of the major terms and measuring units.

  16. Accidents in perspective

    International Nuclear Information System (INIS)

    Gittus, J.H.

    1989-01-01

    The nuclear industry perspective and the public perspective on big nuclear accidents and leukaemia near nuclear sites are discussed. The industry perspective is that big accidents are so unlikely as to be virtually impossible and that leukaemia is not specifically associated with nuclear installations. Clusters of cancer with statistical significance occur in major cities. The public perspective is coloured by a prejudice and myth: the fear of radiation. The big nuclear accident is seen therefore as much more unacceptable than any other big accident. Risks associated with Sizewell-B nuclear station and the liquid gas depot at Canvey Island are discussed. The facts and figures are presented as tables and graphs. Given conflicting interpretations of the leukaemia problem the public inclines towards the more pessimistic view. (author)

  17. Control room habitability during severe accidents

    International Nuclear Information System (INIS)

    Siu, R.P.

    1989-01-01

    The requirements for protection of control room personnel against radiation hazards are specified in 10CFR50, Appendix A, GDC 19. The conventional approach involves a mechanistic evaluation of the radiation doses to control room personnel during design-basis accidents. In this study, an assessment of control room habitability during severe accidents is conducted. The potential levels of radiation hazards to control room personnel are evaluated in terms of both magnitude and probability of occurrence. The expected values for the probabilities of exceeding GDC-19 limits and the cumulative probability distributions of control room doses are determined. In this study, a pressurized water reactor with a large dry containment has been selected for analysis. The types of control rooms evaluated in this study include designs with: (a) filtered local intakes only, (b) filtered recirculation only, (c) filtered local intakes and recirculation, and (d) filtered dual remote intakes and recirculation. From the observations, it is concluded that, except for control room D, all other control room designs may require improvements in order to provide adequate radiation protection during severe accidents, particularly in terms of reducing whole-body gamma doses and skin doses. Potential design improvements include reduction of intake flows for concepts relying on pressurization, reduction in overall leakages, and control room pressurization through the use of bottled air supply

  18. Hazardous materials transportation and emergency response programs

    International Nuclear Information System (INIS)

    Joy, D.S.; Fore, C.S.

    1983-01-01

    This presentation consists of the following visual aids; (1) detailed routing capabilities of truck, rail, barge; (2) legislative data base for hazardous materials; and (3) emergency response of accident site Eddyville, Kentucky (airports in vicinity of Eddyville, KY)

  19. Development of supporting system for emergency response to maritime transport accidents involving radioactive material

    International Nuclear Information System (INIS)

    Odano, N.; Matsuoka, T.; Suzuki, H.

    2004-01-01

    National Maritime Research Institute has developed a supporting system for emergency response of competent authority to maritime transport accidents involving radioactive material. The supporting system for emergency response has functions of radiation shielding calculation, marine diffusion simulation, air diffusion simulation and radiological impact evaluation to grasp potential hazard of radiation. Loss of shielding performance accident and loss of sealing ability accident were postulated and impact of the accidents was evaluated based on the postulated accident scenario. Procedures for responding to emergency were examined by the present simulation results

  20. Lessons from the Fukushima nuclear power accident

    International Nuclear Information System (INIS)

    Hatamura, Yotaro

    2013-01-01

    Through the investigation of the Fukushima Nuclear Power Accident as the chairman of the related Government's Committee, many things had been considered. Essence of the accident could be not only what occurred in the Fukushima nuclear power station, but also dispersed radioactive materials forced many residents to move and not to be returned. Such events as indication errors of water level meter occurring in severe accident could no be thought and remote mechanical operation of valves under high radiation environment were not prepared. Contamination by radioactive clouds caused the evacuation of residents for a long period. Lessons learned from the accident were described such as; (1) the verification of the road to failure connecting selected accident sequence and road to success with another supposed choice, (2) considering what might occur and then what should be needed on the contrary, (3) nuclear power, if should be continued, should be used with the premise of its hazards, and (4) advise to nuclear engineer for adequate information dissemination and technical explanation to the public and keeping nuclear technologies alive. (T. Tanaka)

  1. Improvement of severe accident analysis method for KSNP

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Hong [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Cho, Song Won; Cho, Youn Soo [Korea Radiation Technology Institute Co., Taejon (Korea, Republic of)

    2002-03-15

    The objective of this study is preparation of MELCOR 1.8.5 input deck for KSNP and simulation of some major severe accidents. The contents of this project are preparation of MELCOR 1.8.5 base input deck for KSNP to understand severe accident phenomena and to assess severe accident strategy, preparation of 20 cell containment input deck to simulate the distribution of hydrogen and fission products in containment, simulation of some major severe accident scenarios such as TLOFW, SBO, SBLOCA, MBLOCA, and LBLOCA. The method for MELCOR 1.8.5 input deck preparation can be used to prepare the input deck for domestic PWRs and to simulate severe accident experiments such as ISP-46. Information gained from analyses of severe accidents may be helpful to set up the severe accident management strategy and to develop regulatory guidance.

  2. Security and health protection during the transport of hazardous substances

    International Nuclear Information System (INIS)

    Benkovic, Z.; Bobic, V.

    2009-01-01

    The introduction of this work describes the legal regulations which regulate the conditions and method of the transport of hazardous substances, necessary documentation for storage, forwarding and transport. Hazardous substances are defined and classified according to the ADR. The necessary security measures which are taken for the transport of particular types of hazardous substances are mentioned. Marking and labeling of vehicles for the transport of hazardous substances (plates and lists of hazards), packing and marking of packaging is important. The safety measures which are taken at the filling stations of combustible liquids as well as places specially organized for filling, prohibitions and limitations and necessary transport documentation are mentioned. It is visible from the above mentioned that the activity of the whole security chain is necessary and depends on the good knowledge of basic characteristics and features of substances. All the participants in the security chain have to be familiar with and consistently obey the legal regulations. The manufacturer must know the features of the hazardous substance, supervisory services must be acquainted with the threat and potential danger. The hauler and intervention forces must, in case of accidents and damage, be familiar with the emergency procedures in case of accidents and act properly regarding the threatening dangerous substance.(author)

  3. Risk methodologies for offsite hazardous materials

    International Nuclear Information System (INIS)

    Kot, C.A.; Eichler, T.V.; Wiedermann, A.H.

    1983-01-01

    A number of suggestions have been advanced in recent years concerning the risks posed to nuclear power plants by offsite hazardous materials relative to (1) the regulatory approach including considerations of minimum and safe standoff distances, exclusion distances, site acceptance ceilings and floors, screening distances and screening probabilities, plant design, etc., and (2) the analysis and evaluation procedures such as material screening criteria, plant vulnerability, standarized physical models, etc. An evaluation of current analyses and approaches indicates that this complex problem, variety of approaches, and safety concerns may be better accommodated by developing criteria and treatments along the lines of a so-called conditional risk approach. Specifically, the probability (P) of some ultimate consequence (C) occurring from an accident (A) involving hazardous materials is given as P(C) = P(C/A) x P(A). Assuming that the plant to accident site standoff distance is the fundamental independent variable of the risk methodology, certain conditional risk designations and conditions can be made and are presented

  4. 10-year evaluation of train accidents.

    Science.gov (United States)

    Akkaş, Meltem; Ay, Didem; Metin Aksu, Nalan; Günalp, Müge

    2011-09-01

    Although less frequent than automobile accidents, train accidents have a major impact on victims' lives. Records of patients older than 16 years of age admitted to the Adult Emergency Department of Hacettepe University Medical Center due to train accidents were retrospectively evaluated. 44 patients (30 males, 14 females) with a mean age of 31.8±11.4 years were included in the study. The majority of the accidents occurred during commuting hours. 37 patients were discharged, 22 of them from the emergency department. The mortality rate was 7/44 (16%). Overall mean Revised Trauma Score (RTS) was 10.5 (3 in deaths and 11.9 in survivors). In 5 patients, the cause of death was pelvic trauma leading to major vascular injury and lower limb amputation. In 1 patient, thorax and abdomen trauma and in 1 patient head injury were the causes of mortality. Primary risk factors for mortality were alcohol intoxication (100%), cardiopulmonary resuscitation on admittance (100%), recurrent suicide attempt (75%), presence of psychiatric illness (60%), and low RTS. In this study, most train accidents causing minor injuries were due to falling from the train prior to acceleration. Nevertheless, train accidents led to a mortality rate of 16% and morbidity rate of 37%. These findings draw attention to the importance of developing preventive strategies.

  5. Hazard identification: A proposal for a new development

    International Nuclear Information System (INIS)

    Contini, S.; Labath, N.

    1989-01-01

    Risk assessment is a complex task performed to quantify and minimise the hazards associated with potentially dangerous installations. The hazards identification represents the first step and can be performed by means of different methodologies. Some of these methodologies allow the collection of information on the possible plant behaviours in a structured way. However, this information cannot be easily used for further investigations (i.e. accident quantification). The paper suggests the application of a simple technique for hazard identification and fault tree construction, that can easily be implemented in a computer program. (orig.)

  6. Empirical Risk Analysis of Severe Reactor Accidents in Nuclear Power Plants after Fukushima

    OpenAIRE

    Kaiser, Jan Christian

    2012-01-01

    Many countries are reexamining the risks connected with nuclear power generation after the Fukushima accidents. To provide updated information for the corresponding discussion a simple empirical approach is applied for risk quantification of severe reactor accidents with International Nuclear and Radiological Event Scale (INES) level ≥5. The analysis is based on worldwide data of commercial nuclear facilities. An empirical hazard of 21 (95% confidence intervals (CI) 4; 62) severe accidents am...

  7. Assessment of Mobile Accident Response Capability

    International Nuclear Information System (INIS)

    1983-03-01

    This report presents the results of a DOE-sponsored assessment of nuclear accident response resources. It identifies the mobile resources that could be required to respond to different types of nuclear accidents including major ones like TMI-2, identifies the resources currently available and makes recommendations for the design and construction of additional mobile accident response resources to supplement those already in existence. This project is referred to as the Mobile Accident Response Capability (MARC) program

  8. Ten years after the Chernobyl accident: reporting on nuclear and other hazards in six Swedish newspapers

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Aasa; Sjoeberg, L.; Waahlberg, A. af

    1997-07-01

    A European Commission sponsored study (RISKPERCOM) involving France, Norway, Spain, Sweden, and the UK, is concerned with surveying public perceptions of radiation related and other risks. This was partly done by distributing a questionnaire in each country at three different times in 1996: before, during and after the expected media attention given to the tenth anniversary of the Chernobyl accident. A selection of print media were analyzed, during a period of eight weeks - four weeks before the anniversary, and four weeks after - making it possible to contrast any changes between the three waves of the questionnaire with the results of the media study. The present report aims at providing a picture of the Swedish media coverage of different kinds of risks during the period referred to above. The purpose of the analysis is thus primarily of a descriptive nature; explanatory factors are only considered in an ad hoc manner while discussing the results and their possible implications. Naturally, the findings arising from this study cannot alone serve as a basis for making statements about the effects of risk related content on the Swedish newspaper readers. The risk stories included in the analysis were those dealing with one or more of the twenty different hazard items referred to in several of the questions in the RISKPERCOM questionnaire. Radiation and nuclear power energy were not the only issues of concern. The selection covered a wide range of other hazards as well, in order to provide for a wide risk panorama, thus making it possible to compare specific risk qualities etc., as these were presented in the media 70 refs, 40 refs

  9. Ten years after the Chernobyl accident: reporting on nuclear and other hazards in six Swedish newspapers

    International Nuclear Information System (INIS)

    Nilsson, Aasa; Sjoeberg, L.; Waahlberg, A. af

    1997-07-01

    A European Commission sponsored study (RISKPERCOM) involving France, Norway, Spain, Sweden, and the UK, is concerned with surveying public perceptions of radiation related and other risks. This was partly done by distributing a questionnaire in each country at three different times in 1996: before, during and after the expected media attention given to the tenth anniversary of the Chernobyl accident. A selection of print media were analyzed, during a period of eight weeks - four weeks before the anniversary, and four weeks after - making it possible to contrast any changes between the three waves of the questionnaire with the results of the media study. The present report aims at providing a picture of the Swedish media coverage of different kinds of risks during the period referred to above. The purpose of the analysis is thus primarily of a descriptive nature; explanatory factors are only considered in an ad hoc manner while discussing the results and their possible implications. Naturally, the findings arising from this study cannot alone serve as a basis for making statements about the effects of risk related content on the Swedish newspaper readers. The risk stories included in the analysis were those dealing with one or more of the twenty different hazard items referred to in several of the questions in the RISKPERCOM questionnaire. Radiation and nuclear power energy were not the only issues of concern. The selection covered a wide range of other hazards as well, in order to provide for a wide risk panorama, thus making it possible to compare specific risk qualities etc., as these were presented in the media

  10. Aviation safety and maintenance under major organizational changes, investigating non-existing accidents.

    Science.gov (United States)

    Herrera, Ivonne A; Nordskag, Arve O; Myhre, Grete; Halvorsen, Kåre

    2009-11-01

    The objective of this paper is to discuss the following questions: Do concurrent organizational changes have a direct impact on aviation maintenance and safety, if so, how can this be measured? These questions were part of the investigation carried out by the Accident Investigation Board, Norway (AIBN). The AIBN investigated whether Norwegian aviation safety had been affected due to major organizational changes between 2000 and 2004. The main concern was the reduction in safety margins and its consequences. This paper presents a summary of the techniques used and explains how they were applied in three airlines and by two offshore helicopter operators. The paper also discusses the development of safety related indicators in the aviation industry. In addition, there is a summary of the lessons learned and safety recommendations. The Norwegian Ministry of Transport has required all players in the aviation industry to follow up the findings and recommendations of the AIBN study.

  11. Risk evaluation for protection of the public in radiation accidents

    International Nuclear Information System (INIS)

    1967-01-01

    Evaluation of the risk that would be involved in the exposure of the public in the event of a radiation accident requires information on the biological consequences expected of such an exposure. This report defines a range of reference doses of radiation and their corresponding risks to the public in the event of a radiation accident. The reference doses and the considerations on which they were based will be used for assessing the hazards of nuclear installations and for policy decisions by the authorities responsible for measures taken to safeguards the public in the case of a nuclear accident.

  12. Accident scenarios triggered by lightning strike on atmospheric storage tanks

    International Nuclear Information System (INIS)

    Necci, Amos; Argenti, Francesca; Landucci, Gabriele; Cozzani, Valerio

    2014-01-01

    Severe Natech accidents may be triggered by lightning strike affecting storage tanks containing relevant inventories of hazardous materials. The present study focused on the identification of event sequences and accident scenarios following lightning impact on atmospheric tanks. Reference event trees, validated using past accident analysis, are provided to describe the specific accident chains identified, accounting for reference protection and mitigation safety barriers usually adopted in current industrial practice. An overall methodology was outlined to allow the calculation of the expected frequencies of final scenarios following lightning impact on atmospheric storage tanks, taking into account the expected performance of available safety barriers. The methodology was applied to a case study in order to better understand the data that may be obtained and their importance in the framework of quantitative risk assessment (QRA) and of the risk management of industrial facilities with respect to external hazards due to natural events. - Highlights: • Event sequences following lightning impact on atmospheric tanks were identified. • Reference event trees including standard safety barriers were obtained. • Safety barriers applied in industrial practice were assessed to quantify event trees. • Frequencies of final scenarios following lightning impact on tanks were calculated. • Natech scenarios caused by lightning have an important influence on risk profiles

  13. Some Lessons Learnt From the Fukushima Daiichi Accident, as Regards Defence in Depth and its Implementation in New or Existing Designs – An Industry Example

    Energy Technology Data Exchange (ETDEWEB)

    De L’Epinois, B.; Bouteille, F.; Nicaise, N., E-mail: bertrand.delepinois@areva.com [AREVA, Paris (France)

    2014-10-15

    Defence-in-Depth (DiD) concept has been the overarching principle of the nuclear safety since the design of the first power reactors and it remains so more than ever. The Fukushima accident, characterised by a massive common mode failure induced by the flooding due to the tsunami, reminds the need for a very careful implementation, in the engineering, construction and operation of nuclear facilities, of the principles and rules concerning DiD. In particular, this accident highlights the need for appropriate consideration of DiD in two domains: protection against external hazards and severe accident management. In terms of external hazards, Fukushima reminds that the site design basis hazards must be as complete as possible and incorporate all relevant, including new, knowledge. In addition, in case nature would reveal to be more imaginative than us, or in case some hazards would have been under-evaluated despite all precautions, adequate extra margins should be ensured beyond the design basis hazards, as a defence in depth provision to avoid cliff edge effects. In other words, a minimal set of essential safety functions needed to prevent a severe accident or to mitigate its consequences should show sufficient robustness and safety margins to cope with external hazards exceeding the design basis hazards. Concerning severe accident, comprehensive R&D has been performed for several decades, the occurrence of such situations has been included in the DiD principles (level 4 as defined by INSAG 10) and has led to substantial safety improvements at many plants. Fukushima reminds the importance of a thorough implementation of these mitigation provisions. These two DiD provisions can be expressed as the need to show that the nuclear facilities and the crisis organizations can cope with extreme, beyond design hazards or accidents, precluding unacceptable offsite radiological impact and contamination. The development of Gen 3+ reactors targeted a significant safety step, by

  14. Accident knowledge and emergency management

    Energy Technology Data Exchange (ETDEWEB)

    Rasmussen, B; Groenberg, C D

    1997-03-01

    The report contains an overall frame for transformation of knowledge and experience from risk analysis to emergency education. An accident model has been developed to describe the emergency situation. A key concept of this model is uncontrolled flow of energy (UFOE), essential elements are the state, location and movement of the energy (and mass). A UFOE can be considered as the driving force of an accident, e.g., an explosion, a fire, a release of heavy gases. As long as the energy is confined, i.e. the location and movement of the energy are under control, the situation is safe, but loss of confinement will create a hazardous situation that may develop into an accident. A domain model has been developed for representing accident and emergency scenarios occurring in society. The domain model uses three main categories: status, context and objectives. A domain is a group of activities with allied goals and elements and ten specific domains have been investigated: process plant, storage, nuclear power plant, energy distribution, marine transport of goods, marine transport of people, aviation, transport by road, transport by rail and natural disasters. Totally 25 accident cases were consulted and information was extracted for filling into the schematic representations with two to four cases pr. specific domain. (au) 41 tabs., 8 ills.; 79 refs.

  15. Accident knowledge and emergency management

    International Nuclear Information System (INIS)

    Rasmussen, B.; Groenberg, C.D.

    1997-03-01

    The report contains an overall frame for transformation of knowledge and experience from risk analysis to emergency education. An accident model has been developed to describe the emergency situation. A key concept of this model is uncontrolled flow of energy (UFOE), essential elements are the state, location and movement of the energy (and mass). A UFOE can be considered as the driving force of an accident, e.g., an explosion, a fire, a release of heavy gases. As long as the energy is confined, i.e. the location and movement of the energy are under control, the situation is safe, but loss of confinement will create a hazardous situation that may develop into an accident. A domain model has been developed for representing accident and emergency scenarios occurring in society. The domain model uses three main categories: status, context and objectives. A domain is a group of activities with allied goals and elements and ten specific domains have been investigated: process plant, storage, nuclear power plant, energy distribution, marine transport of goods, marine transport of people, aviation, transport by road, transport by rail and natural disasters. Totally 25 accident cases were consulted and information was extracted for filling into the schematic representations with two to four cases pr. specific domain. (au) 41 tabs., 8 ills.; 79 refs

  16. Accident risks in nuclear facilities (a bibliography with abstracts). Report for 1964-Sep 77

    International Nuclear Information System (INIS)

    Grooms, D.W.

    1977-10-01

    The bibliography presents risk analysis and hazards evaluation of the design, construction and operation of nuclear facilities, including the risk and hazards of transporting radioactive materials to and from these facilities. Radiological calculations for environmental effects of nuclear accidents are also included

  17. Transportation of hazardous materials (hazmat a literature survey

    Directory of Open Access Journals (Sweden)

    Zafer YILMAZ

    2016-02-01

    Full Text Available ransportation has a great role in logistics. Many researchers have studied on transportation and vehicle routing problems. Transportation of hazardous materials (hazmat is a special subject for logistics. Causalities due to the accidents caused by trucks carrying hazardous materials will be intolerable. Many researchers have studied on risk assessment of hazmat transportation to find ways for reducing hazardous material transportation risks. Some researchers have studied routing of hazmat trucks. The emergency response models and network design problems for hazmat transportation were also studied by some researchers. The transportation of hazmats can also be classified according to the mode of transport. Mainly roads are used for hazmat transportation but some shipments are intermodal. There has been a great amount of effort spent to find convenient ways for hazmat transportation. In this study, a literature survey for the articles about hazmat transportation is prepared. After pointing out the importance of hazmat transportation by the example of US hazmat transportation data, the studies on hazmat transportation since 2005 have been examined. Totally 88 articles are classified as risk, routing, routing and scheduling, emergency response, network design and accident analysis. What can be studied in future researches is pointed out.Keywords: Hazardous materials, Network design, Transportation, Routing, Risk assessment

  18. MELCOR assessment of sequential severe accident mitigation actions under SGTR accident

    International Nuclear Information System (INIS)

    Choi, Wonjun; Jeon, Joongoo; Kim, Nam Kyung; Kim, Sung Joong

    2017-01-01

    The representative example of the severe accident studies using the severe accident code is investigation of effectiveness of developed severe accident management (SAM) strategy considering the positive and adverse effects. In Korea, some numerical studies were performed to investigate the SAM strategy using various severe accident codes. Seo et.al performed validation of RCS depressurization strategy and investigated the effect of severe accident management guidance (SAMG) entry condition under small break loss of coolant accident (SBLOCA) without safety injection (SI), station blackout (SBO), and total loss of feed water (TLOFW) scenarios. The SGTR accident with the sequential mitigation actions according to the flow chart of SAMG was simulated by the MELCOR 1.8.6 code. Three scenariospreventing the RPV failure were investigated in terms of fission product release, hydrogen risk, and the containment pressure. Major conclusions can be summarized as follows: (1) According to the flow chart of SAMG, RPV failure can be prevented depending on the method of RCS depressurization. (2) To reduce the release of fission product during the injecting into SGs, a temporary opening of SDS before the injecting into SGs was suggested. These modified sequences of mitigation actions can reduce the release of fission product and the adverse effect of SDS.

  19. Economic burden of motorcycle accidents in Northern Ghana.

    Science.gov (United States)

    Kudebong, M; Wurapa, F; Nonvignon, J; Norman, I; Awoonor-Williams, J K; Aikins, M

    2011-12-01

    Motorcycles are the most popular means of transportation in northern Ghana, and their accidents are major causes of out-patient attendance and admissions in the Bolgatanga Municipality. This paper estimates the economic burden of motorcycle accidents in the Bolgatanga Municipality in Northern Ghana. Retrospective cross-sectional cost study. Data were collected from Drivers and Vehicle Licensing Authority, the Police, health facilities and motorcycle accident victims. Both quantitative and qualitative approaches were used for data collection. Cost analysis was based on the standard road accident cost conceptual framework. Ninety-eight percent of vehicles registered in the municipality in 2004 - 2008 were motorcycles. The motorcycles were significantly more than the cars registered. The economic burden of motorcycle accidents was estimated to be about US$1.2 million, of which, 52% were accident-related costs (i.e. property damage and administration) and 48% casualty-related costs (i.e. medical costs, out-of-pocket expenses, lost labour outputs, intangible costs and funeral expenses). Most motorcycle accident victims were in their productive ages and were males. Only a third of the motorcycles were insured. Majority of the riders (71%) did not possess valid driving license and would want to avoid the police. Main motorcycle injuries were head injuries, fractures, lacerations and contusions. Majority of the accidents were caused by lack of formal motorcycle riding training, abuse of alcohol, unrestrained animals and donkey carts. Motorcycle accidents could be reduced through law enforcement, continuous mass education and helmet use.

  20. Severe Accident Research Program plan update

    International Nuclear Information System (INIS)

    1992-12-01

    In August 1989, the staff published NUREG-1365, ''Revised Severe Accident Research Program Plan.'' Since 1989, significant progress has been made in severe accident research to warrant an update to NUREG-1365. The staff has prepared this SARP Plan Update to: (1) Identify those issues that have been closed or are near completion, (2) Describe the progress in our understanding of important severe accident phenomena, (3) Define the long-term research that is directed at improving our understanding of severe accident phenomena and developing improved methods for assessing core melt progression, direct containment heating, and fuel-coolant interactions, and (4) Reflect the growing emphasis in two additional areas--advanced light water reactors, and support for the assessment of criteria for containment performance during severe accidents. The report describes recent major accomplishments in understanding the underlying phenomena that can occur during a severe accident. These include Mark I liner failure, severe accident scaling methodology, source term issues, core-concrete interactions, hydrogen transport and combustion, TMI-2 Vessel Investigation Project, and direct containment heating. The report also describes the major planned activities under the SARP over the next several years. These activities will focus on two phenomenological issues (core melt progression, and fuel-coolant interactions and debris coolability) that have significant uncertainties that impact our understanding and ability to predict severe accident phenomena and their effect on containment performance SARP will also focus on severe accident code development, assessment and validation. As the staff completes the research on severe accident issues that relate to current generation reactors, continued research will focus on efforts to independently evaluate the capability of new advanced light water reactor designs to withstand severe accidents

  1. Nuclear accidents and safety measures of domestic nuclear power plants

    International Nuclear Information System (INIS)

    Song Zurong; Che Shuwei; Pan Xiang

    2012-01-01

    Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

  2. Energy. Health, environment, and safety hazards. Final report from the Energy Commission. Energi. Haelso- miljoe- och saekerhetsrisker. Slutbetaenkande av energikommissionen

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The Swedish Energy Commission in its main report (''Energy'', SOU 1978:17) presented its considerations and put forward its proposals for a Swedish Energy policy for the next decade. This report contains complementary information on health hazards, risks of major accidents and sabotage, and problems of waste management. The presentation takes the form of a comparison of such risks in relation to different sources of energy. The Commission is not unanimous in its estimates of the relative hazards of different energysystems. The Commission recommends the initiation of a large number of studies concerning the possible ways the increase the safety and reduce the adverse effects of energy production.

  3. Supplemental Hazard Analysis and Risk Assessment - Hydrotreater

    Energy Technology Data Exchange (ETDEWEB)

    Lowry, Peter P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wagner, Katie A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-04-01

    A supplemental hazard analysis was conducted and quantitative risk assessment performed in response to an independent review comment received by the Pacific Northwest National Laboratory (PNNL) from the U.S. Department of Energy Pacific Northwest Field Office (PNSO) against the Hydrotreater/Distillation Column Hazard Analysis Report issued in April 2013. The supplemental analysis used the hazardous conditions documented by the previous April 2013 report as a basis. The conditions were screened and grouped for the purpose of identifying whether additional prudent, practical hazard controls could be identified, using a quantitative risk evaluation to assess the adequacy of the controls and establish a lower level of concern for the likelihood of potential serious accidents. Calculations were performed to support conclusions where necessary.

  4. Statistical treatment of hazards result from radioactive material in metal scrap

    International Nuclear Information System (INIS)

    Salem, E.F.; Rashad, S.M.

    2013-01-01

    Radioactive sources have a wide range of uses in medicine and industry. Radioactive materials entering the public domain in an uncontrolled manner may creating a serious risk of radiation exposure for workers and the public as well as excessive costs for plant decontamination and waste of product to be borne by the metal industry. This paper describes the major accidents that had happened in the last decades due to radioactive material in metal scrap, provides assessment of associated hazards and lessons learned. This will help Regulatory Authority to introduce measures capable to avoid the recurrence of similar events. The study highlights the situation for metal scrap incidents in Egypt.

  5. Applicability of simplified human reliability analysis methods for severe accidents

    Energy Technology Data Exchange (ETDEWEB)

    Boring, R.; St Germain, S. [Idaho National Lab., Idaho Falls, Idaho (United States); Banaseanu, G.; Chatri, H.; Akl, Y. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

    2016-03-15

    Most contemporary human reliability analysis (HRA) methods were created to analyse design-basis accidents at nuclear power plants. As part of a comprehensive expansion of risk assessments at many plants internationally, HRAs will begin considering severe accident scenarios. Severe accidents, while extremely rare, constitute high consequence events that significantly challenge successful operations and recovery. Challenges during severe accidents include degraded and hazardous operating conditions at the plant, the shift in control from the main control room to the technical support center, the unavailability of plant instrumentation, and the need to use different types of operating procedures. Such shifts in operations may also test key assumptions in existing HRA methods. This paper discusses key differences between design basis and severe accidents, reviews efforts to date to create customized HRA methods suitable for severe accidents, and recommends practices for adapting existing HRA methods that are already being used for HRAs at the plants. (author)

  6. Point Source contamination approach for hydrological risk assessment of a major hypothetical accident from second research reactor at Inshas site

    International Nuclear Information System (INIS)

    Sadek, M.A.; Tawfik, F.S.

    2002-01-01

    The point source contamination mechanism and the deterministic conservative approach have been implemented to demonstrate the hazards of hydrological pollution due to a major hypothetical accident in the second research reactor at Inshas. The radioactive inventory is assumed to be dissolved in 75% of the cooling water (25% are lost) and comes directly into contact with ground water and moved down gradient. Five radioisotopes(I-129, Sr-90, Ru-106, Cs-134 and Cs-137) of the entire inventory are found to be highly durable and represent vulnerability in the environment. Their downstream spread indices; C max : maximum concentration at the focus of the moving ellipse, delta: pollution duration at different distances, A:polluted area at different distances and X min : safety distance from the reactor, were calculated based on analytical solutions of the convection-dispersion partial differential equation for absorbable and decaying species. The largest downstream contamination range was found for Sr-90 and Ru-106 but still no potential. The geochemical and hydrological parameters of the water bearing formations play a great role in buffering and limiting the radiation effects. These reduce the retention time of the radioisotopes several order of magnitudes in the polluted distances. Sensitivity analysis of the computed pollution ranges shows low sensitivity to possible potential for variations activity of nuclide inventory, dispersivity and saturated thickness and high sensitivity for possible variations in groundwater velocity and retention factors

  7. Chemical Hazards and Safety Issues in Fusion Safety Design

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    2003-01-01

    Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

  8. Radiological consequences of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.

    2002-01-01

    Fifty years of peaceful utilization of nuclear power were interrupted by the reactor accident in unit 4 of the Chernobyl nuclear power station in Ukraine in 1986, a disruptive event whose consequences profoundly affected the way of life of millions of people, and which has moved the public to this day. Releases of radioactive materials contaminated large areas of Belarus, the Russian Federation, and Ukraine. Early damage in the form of radiation syndrome was suffered by a group of rescue workers and members of the reactor operating crew, in some cases with fatal consequences, while the population does not, until now, show a statistically significant increase in the rate of late damage due to ionizing radiation expect for thyroid diseases in children. In particular, no increases in the rates of solid tumors, leukaemia, genetic defects, and congenital defects were detected. For some risk groups exposed to high radiation doses (such as liquidators) the hazard may still be greater, but the large majority of the population need not live in fear of serious impacts on health. Nevertheless, the accident shows major negative social and psychological consequences reinforced by the breakdown of the Soviet Union. This may be one reason for the observed higher incidence of other diseases whose association with the effects of radiation as a cause has not so far been proven. The measurement campaign conducted by the federal government in 1991-1993 addressed these very concerns of the public in an effort to provide unbiased information about exposures detected, on the one hand, in order to alleviate the fears of the public and reduce stress and, on the other hand, to contribute to the scientific evaluation of the radiological situation in the regions most highly exposed. The groups of the population requiring special attention in the future include especially children growing up in highly contaminated regions, and the liquidators of 1986 and 1987 employed in the period immediately

  9. The impact of major transformations of a production process on age-related accident risks

    DEFF Research Database (Denmark)

    Blank, V L; Laflamme, L; Diderichsen, Finn

    1996-01-01

    This paper describes a study of whether accident risks were equally distributed across age categories among a population of mining workers whose work activities were suspected to be age-impaired. The impairment factors in focus are the transformation of production technology during the 80s...... and consequent changes in job content. It was hypothesized that the combined effect of these factors might lead accident risks, both non-specific (aggregated) and specific (by kind), to increase with age. Accident risk ratios (ARRs), however, proved to be higher for younger workers than older ones, in both...... the non-specific and the specific cases. However, two accident patterns (specific risks) also show relatively high ARRs among workers in their 40s (and even 30s), results that might be explained by particular exposures and/or age-related performance problems. The findings suggest that technological...

  10. Dust: A major environmental hazard on the earth's moon

    Energy Technology Data Exchange (ETDEWEB)

    Heiken, G.; Vaniman, D.; Lehnert, B.

    1990-01-01

    On the Earth's Moon, obvious hazards to humans and machines are created by extreme temperature fluctuations, low gravity, and the virtual absence of any atmosphere. The most important other environmental factor is ionizing radiation. Less obvious environmental hazards that must be considered before establishing a manned presence on the lunar surface are the hazards from micrometeoroid bombardment, the nuisance of electro-statically-charged lunar dust, and an alien visual environment without familiar clues. Before man can establish lunar bases and lunar mining operations, and continue the exploration of that planet, we must develop a means of mitigating these hazards. 4 refs.

  11. A study on industrial accident rate forecasting and program development of estimated zero accident time in Korea.

    Science.gov (United States)

    Kim, Tae-gu; Kang, Young-sig; Lee, Hyung-won

    2011-01-01

    To begin a zero accident campaign for industry, the first thing is to estimate the industrial accident rate and the zero accident time systematically. This paper considers the social and technical change of the business environment after beginning the zero accident campaign through quantitative time series analysis methods. These methods include sum of squared errors (SSE), regression analysis method (RAM), exponential smoothing method (ESM), double exponential smoothing method (DESM), auto-regressive integrated moving average (ARIMA) model, and the proposed analytic function method (AFM). The program is developed to estimate the accident rate, zero accident time and achievement probability of an efficient industrial environment. In this paper, MFC (Microsoft Foundation Class) software of Visual Studio 2008 was used to develop a zero accident program. The results of this paper will provide major information for industrial accident prevention and be an important part of stimulating the zero accident campaign within all industrial environments.

  12. The radiological hazard of plutonium isotopes and specific plutonium mixtures

    International Nuclear Information System (INIS)

    Heindel, G.; Clow, J.; Inkret, W.; Miller, G.

    1995-11-01

    The US Department of Energy defines the hazard categories of its nuclear facilities based upon the potential for accidents to have significant effects on specific populations and the environment. In this report, the authors consider the time dependence of hazard category 2 (significant on-site effects) for facilities with inventories of plutonium isotopes and specific weapons-grade and heat-source mixtures of plutonium isotopes. The authors also define relative hazard as the reciprocal of the hazard category 2 threshold value and determine its time dependence. The time dependence of both hazard category 2 thresholds and relative hazards are determined and plotted for 10,000 years to provide useful information for planning long-term storage or disposal facilities

  13. Emergency preparedness and response in case of a fire accident with (UF6) packages tracking Suez Canal

    International Nuclear Information System (INIS)

    Salama, M.

    2004-01-01

    Egypt has a unique problem - the Suez Canal. Radioactive cargo passing regularly through the canal carrying new and spent reactor fuel. Moreover there are also about 1000 metric tons of uranium hexaflouride (UF6) passing through the canal every year. In spite of all precautions taken in the transportation, accidents with packages containing (UF 6 ) and shipped through the Suez Canal, accidents may arise even though the probability is minimal. These accidents, may be accompanied by injuries or death of persons and damage to property. Due to the radiation and criticality hazards of (UF 6 ) and its high risk of chemical toxicity. The probability of a fire accident with a cargo carrying (UF 6 ) during its crossing the Suez Canal can cause serious chemical toxic and radiological hazards, particularly if the accident occurred close or near to one of the three densely populated cities (Port-Said, Ismailia, and Suez), which are located along the Suez Canal, west bank. The government of Egypt has elaborated a national radiological emergency plan inorder to face probable radiological accidents, which may be arised inside the country. Arrangements have been also elaborated for the medical care of any persons who, might be injured or contaminated, or who, have been exposed to severe radiation doses. The motivation of the present paper was undertaken to visualize a fire accident scenario occurring in industrial packages containing UF6 on board of a Cargo crossing the Suez Canal near Port-Said City. The accident scenario and emergency response actions taken during the different phases of the accident are going to be presented and discussed. The proposed emergency response actions taken to face the accident are going to be also presented. The work presented had revealed the importance of public awareness will be needed for populations located in densely populated areas along Suez Canal bank inorder to react timely and effectively to avoid the toxic and radiological hazards

  14. Probability analysis of multiple-tank-car release incidents in railway hazardous materials transportation

    International Nuclear Information System (INIS)

    Liu, Xiang; Saat, Mohd Rapik; Barkan, Christopher P.L.

    2014-01-01

    Railroads play a key role in the transportation of hazardous materials in North America. Rail transport differs from highway transport in several aspects, an important one being that rail transport involves trains in which many railcars carrying hazardous materials travel together. By contrast to truck accidents, it is possible that a train accident may involve multiple hazardous materials cars derailing and releasing contents with consequently greater potential impact on human health, property and the environment. In this paper, a probabilistic model is developed to estimate the probability distribution of the number of tank cars releasing contents in a train derailment. Principal operational characteristics considered include train length, derailment speed, accident cause, position of the first car derailed, number and placement of tank cars in a train and tank car safety design. The effect of train speed, tank car safety design and tank car positions in a train were evaluated regarding the number of cars that release their contents in a derailment. This research provides insights regarding the circumstances affecting multiple-tank-car release incidents and potential strategies to reduce their occurrences. The model can be incorporated into a larger risk management framework to enable better local, regional and national safety management of hazardous materials transportation by rail

  15. Probability analysis of multiple-tank-car release incidents in railway hazardous materials transportation

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Xiang, E-mail: liu94@illinois.edu; Saat, Mohd Rapik, E-mail: mohdsaat@illinois.edu; Barkan, Christopher P.L., E-mail: cbarkan@illinois.edu

    2014-07-15

    Railroads play a key role in the transportation of hazardous materials in North America. Rail transport differs from highway transport in several aspects, an important one being that rail transport involves trains in which many railcars carrying hazardous materials travel together. By contrast to truck accidents, it is possible that a train accident may involve multiple hazardous materials cars derailing and releasing contents with consequently greater potential impact on human health, property and the environment. In this paper, a probabilistic model is developed to estimate the probability distribution of the number of tank cars releasing contents in a train derailment. Principal operational characteristics considered include train length, derailment speed, accident cause, position of the first car derailed, number and placement of tank cars in a train and tank car safety design. The effect of train speed, tank car safety design and tank car positions in a train were evaluated regarding the number of cars that release their contents in a derailment. This research provides insights regarding the circumstances affecting multiple-tank-car release incidents and potential strategies to reduce their occurrences. The model can be incorporated into a larger risk management framework to enable better local, regional and national safety management of hazardous materials transportation by rail.

  16. Severity of electrical accidents in the construction industry in Spain.

    Science.gov (United States)

    Suárez-Cebador, Manuel; Rubio-Romero, Juan Carlos; López-Arquillos, Antonio

    2014-02-01

    This paper analyzes the severity of workplace accidents involving electricity in the Spanish construction sector comprising 2,776 accidents from 2003 to 2008. The investigation considered the impact of 13 variables, classified into 5 categories: Personal, Business, Temporal, Material, and Spatial. The findings showed that electrical accidents are almost five times more likely to have serious consequences than the average accident in the sector and it also showed how the variables of age, occupation, company size, length of service, preventive measures, time of day, days of absence, physical activity, material agent, type of injury, body part injured, accident location, and type of location are related to the severity of the electrical accidents under consideration. The present situation makes it clear that greater effort needs to be made in training, monitoring, and signage to guarantee a safe working environment in relation to electrical hazards. This research enables safety technicians, companies, and government officials to identify priorities and to design training strategies to minimize the serious consequences of electrical accidents for construction workers. Copyright © 2013 Elsevier Ltd and National Safety Council. All rights reserved.

  17. Lessons Learned for Space Safety from the Fukushima Nuclear Power Plant Accident

    Science.gov (United States)

    Nogami, Manami; Miki, Masami; Mitsui, Masami; Kawada, Ysuhiro; Takeuchi, Nobuo

    2013-09-01

    On March 11 2011, Tohoku Region Pacific Coast Earthquake hit Japan and caused the devastating damage. The Fukushima Nuclear Power Station (NPS) was also severely damaged.The Japanese NPSs are designed based on the detailed safety requirements and have multiple-folds of hazard controls to the catastrophic hazards as in space system. However, according to the initial information from the Tokyo Electric Power Company (TEPCO) and the Japanese government, the larger-than-expected tsunami and subsequent events lost the all hazard controls to the release of radioactive materials.At the 5th IAASS, Lessons Learned from this disaster was reported [1] mainly based on the "Report of the Japanese Government to the IAEA Ministerial Conference on Nuclear Safety" [2] published by Nuclear Emergency Response Headquarters in June 2011, three months after the earthquake.Up to 2012 summer, the major investigation boards, including the Japanese Diet, the Japanese Cabinet and TEPCO, published their final reports, in which detailed causes of this accident and several recommendations are assessed from each perspective.In this paper, the authors examine to introduce the lessons learned to be applied to the space safety as findings from these reports.

  18. Accidents - Chernobyl accident; Accidents - accident de Tchernobyl

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)

  19. Aircraft accident analysis for emergency planning and safety analysis

    International Nuclear Information System (INIS)

    Nicolosi, S.L.; Jordan, H.; Foti, D.; Mancuso, J.

    1996-01-01

    Potential aircraft accidents involving facilities at the Rocky Flats Environmental Technology Site (Site) are evaluated to assess their safety significance. This study addresses the probability and facility penetrability of aircraft accidents at the Site. The types of aircraft (large, small, etc.) that may credibly impact the Site determine the types of facilities that may be breached. The methodology used in this analysis follows elements of the draft Department of Energy Standard ''Accident Analysis for Aircraft Crash into Hazardous Facilities'' (July 1995). Key elements used are: the four-factor frequency equation for aircraft accidents; the distance criteria for consideration of airports, airways, and jet routes; the consideration of different types of aircraft; and the Modified National Defense Research Committee (NDRC) formula for projectile penetration, perforation, and minimum resistant thickness. The potential aircraft accident frequency for each type of aircraft applicable to the Site is estimated using a four-factor formula described in the draft Standard. The accident frequency is the product of the annual number of operations, probability of an accident, probability density function, and area. The annual number of operations is developed from site-specific and state-wide data

  20. Loss experience from natural phenomena hazards in the Department of Energy (50 years of natural phenomena hazard losses)

    International Nuclear Information System (INIS)

    Hill, J.R.

    1993-01-01

    This paper presents a historical prespective on losses due to natural hazard incidents (1943-1993) at Department of Energy (DOE) and predecessor agencies including the Atomic Energy Commission (AEC) and the Energy Research and Development Agency (ERDA). This paper also demonstrates how an existing DOE resource can be used to gain valuable insight into injury or property damage incidents. That resource is the Computerized Accident/Incident Reporting System (CAIRS) module of DOE's Safety Performance Measurement System. CAIRS data selected the 1981-1991 DOE injury/illness reports, from all the accident reports of the AEC that cited a natural phenomena hazard as either the direct or indirect cause of the injury/property damage. Specifically, injury or property damage reports were selected for analysis if they had a causal factor link to severe weather or natural phenomena hazard categories. Natural phenomena hazard categories are injury/property damage caused by hurricane/tornado, earthquake, lightning, or flood. Severe weather categories are injury/property damage associated with other than normal weather conditions. The lessons learned, as a result of reviewing case histories, are presented, as are suggestions on how to reduce the likelihood of future injuries/property damage as a result of similar events. A significant finding, is that most injuries and property damage were the result of an indirect causal link to a natural phenomena hazard and thus, may be more preventable than previously thought possible. The primary message, however, is that CAIRS and other incident data bases are valuable resources and should be considered for use by those interested in identifying new ways of protecting the health and safety of the worker and for reducing building losses due to the effects of natural phenomena hazards

  1. Risk assessment of major hazards: Hazardous materials transportation in urban areas

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, Ph; Pages, P

    1988-02-01

    There is no doubt that, thanks to the pioneering studies of the late seventies and the early eighties, a methodology has been made available that allows risk management of hazardous transportation in urban areas. This approach can easily be extended to the management of other similar risks (storages and to some extent natural hazards). The methodology is both technically available and affordable. The insertion within the decision making processes deserves still some efforts. It has be seen that the applications are broad and numerous. They range from route selection to emergency preparedness, with some insights into acceptability considerations. One limit to the use of such studies, aiming to an objective assessment of the risk, is the complexity of the decision problems, where many factors are to be considered, the most subtle being the one linked to acceptability. However, as such studies develop, those factors start to be clarified, and decision makers learn how to use risk indices in this context. So at the present time it can be said that risk analyses are a valuable input into the decision making process in most cases. And, as more experience is acquired the uses are broader. As any technical innovation risk assessment modifies the approaches to the questions it is dealing with. It seems impossible now to treat those kinds of risks as was done ten years ago.

  2. Risk assessment of major hazards: Hazardous materials transportation in urban areas

    International Nuclear Information System (INIS)

    Hubert, Ph.; Pages, P.

    1988-02-01

    There is no doubt that, thanks to the pioneering studies of the late seventies and the early eighties, a methodology has been made available that allows risk management of hazardous transportation in urban areas. This approach can easily be extended to the management of other similar risks (storages and to some extent natural hazards). The methodology is both technically available and affordable. The insertion within the decision making processes deserves still some efforts. It has be seen that the applications are broad and numerous. They range from route selection to emergency preparedness, with some insights into acceptability considerations. One limit to the use of such studies, aiming to an objective assessment of the risk, is the complexity of the decision problems, where many factors are to be considered, the most subtle being the one linked to acceptability. However, as such studies develop, those factors start to be clarified, and decision makers learn how to use risk indices in this context. So at the present time it can be said that risk analyses are a valuable input into the decision making process in most cases. And, as more experience is acquired the uses are broader. As any technical innovation risk assessment modifies the approaches to the questions it is dealing with. It seems impossible now to treat those kinds of risks as was done ten years ago

  3. WE-G-BRA-06: Application of Systems and Control Theory-Based Hazard Analysis to Radiotherapy

    Energy Technology Data Exchange (ETDEWEB)

    Pawlicki, T [UC San Diego, La Jolla, CA (United States); Samost, A; Leveson, N [Massachusetts Institute of Technology, Cambridge, MA (United States)

    2015-06-15

    Purpose: The process of delivering radiation occurs in a complex socio-technical system heavily reliant on human operators. Furthermore, both humans and software are notoriously challenging to account for in traditional hazard analysis models. High reliability industries such as aviation have approached this problem through using hazard analysis techniques grounded in systems and control theory. The purpose of this work is to apply the Systems Theoretic Accident Model Processes (STAMP) hazard model to radiotherapy. In particular, the System-Theoretic Process Analysis (STPA) approach is used to perform a hazard analysis of a proposed on-line adaptive cranial radiosurgery procedure that omits the CT Simulation step and uses only CBCT for planning, localization, and treatment. Methods: The STPA procedure first requires the definition of high-level accidents and hazards leading to those accidents. From there, hierarchical control structures were created followed by the identification and description of control actions for each control structure. Utilizing these control structures, unsafe states of each control action were created. Scenarios contributing to unsafe control action states were then identified and translated into system requirements to constrain process behavior within safe boundaries. Results: Ten control structures were created for this new CBCT-only process which covered the areas of hospital and department management, treatment design and delivery, and vendor service. Twenty three control actions were identified that contributed to over 80 unsafe states of those control actions resulting in over 220 failure scenarios. Conclusion: The interaction of people, hardware, and software are highlighted through the STPA approach. STPA provides a hierarchical model for understanding the role of management decisions in impacting system safety so that a process design requirement can be traced back to the hazard and accident that it is intended to mitigate. Varian

  4. High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

    International Nuclear Information System (INIS)

    Kloepfer, Michael

    2012-01-01

    The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

  5. Preliminary Analysis of Aircraft Loss of Control Accidents: Worst Case Precursor Combinations and Temporal Sequencing

    Science.gov (United States)

    Belcastro, Christine M.; Groff, Loren; Newman, Richard L.; Foster, John V.; Crider, Dennis H.; Klyde, David H.; Huston, A. McCall

    2014-01-01

    Aircraft loss of control (LOC) is a leading cause of fatal accidents across all transport airplane and operational classes, and can result from a wide spectrum of hazards, often occurring in combination. Technologies developed for LOC prevention and recovery must therefore be effective under a wide variety of conditions and uncertainties, including multiple hazards, and their validation must provide a means of assessing system effectiveness and coverage of these hazards. This requires the definition of a comprehensive set of LOC test scenarios based on accident and incident data as well as future risks. This paper defines a comprehensive set of accidents and incidents over a recent 15 year period, and presents preliminary analysis results to identify worst-case combinations of causal and contributing factors (i.e., accident precursors) and how they sequence in time. Such analyses can provide insight in developing effective solutions for LOC, and form the basis for developing test scenarios that can be used in evaluating them. Preliminary findings based on the results of this paper indicate that system failures or malfunctions, crew actions or inactions, vehicle impairment conditions, and vehicle upsets contributed the most to accidents and fatalities, followed by inclement weather or atmospheric disturbances and poor visibility. Follow-on research will include finalizing the analysis through a team consensus process, defining future risks, and developing a comprehensive set of test scenarios with correlation to the accidents, incidents, and future risks. Since enhanced engineering simulations are required for batch and piloted evaluations under realistic LOC precursor conditions, these test scenarios can also serve as a high-level requirement for defining the engineering simulation enhancements needed for generating them.

  6. The possibility of GIS application for the needs of planning transport of hazardous waste

    Directory of Open Access Journals (Sweden)

    Panić Milena

    2010-01-01

    Full Text Available Hazardous waste management system as a separate segment includes the transportation of hazardous waste, which specifically includes transportation from the place of its origin to the place of storage, treatment or final disposal. This function includes all forms of transport, but experience has shown that the most used one is a road traffic, which also carries an extremely high risk of possible occurrence of accident and endangering the local community, material resources and environment. Therefore, it is necessary to establish control over transport option, and the risk too, which is achieved by conducting risk assessments and then selecting the optimal transport routes. In each of these phases GIS has found its major application, enabling operation with different types of data, a simplified procedure of multi-criteria analysis and a clear visual representation of the received results. .

  7. Consequences of potential accidents in heavy water plants

    International Nuclear Information System (INIS)

    Croitoru, C.; Lazar, R.E.; Preda, I.A.; Dumitrescu, M.

    2002-01-01

    Heavy water plants achieve the primary isotopic concentration by H 2 O-H 2 S chemical exchange. In these plants are stored large quantities of hydrogen sulphide (high toxic, corrosive, flammable and explosive) maintained in process at relative high temperatures and pressures. It is required an assessment of risks associated with the potential accidents. The paper presents adopted model for quantitative consequences assessment in heavy water plants. Following five basic steps are used to identify the risks involved in plants operation: hazard identification, accident sequences development, H 2 S emissions calculus, dispersion analyses and consequences determination. A brief description of each step and some information from risk assessment for our heavy water pilot plant are provided. Accident magnitude, atmospheric conditions and population density in studied area were accounted for consequences calculus. (author)

  8. Accident analysis of railway transportation of low-level radioactive and hazardous chemical wastes: Application of the /open quotes/Maximum Credible Accident/close quotes/ concept

    Energy Technology Data Exchange (ETDEWEB)

    Ricci, E.; McLean, R.B.

    1988-09-01

    The maximum credible accident (MCA) approach to accident analysis places an upper bound on the potential adverse effects of a proposed action by using conservative but simplifying assumptions. It is often used when data are lacking to support a more realistic scenario or when MCA calculations result in acceptable consequences. The MCA approach can also be combined with realistic scenarios to assess potential adverse effects. This report presents a guide for the preparation of transportation accident analyses based on the use of the MCA concept. Rail transportation of contaminated wastes is used as an example. The example is the analysis of the environmental impact of the potential derailment of a train transporting a large shipment of wastes. The shipment is assumed to be contaminated with polychlorinated biphenyls and low-level radioactivities of uranium and technetium. The train is assumed to plunge into a river used as a source of drinking water. The conclusions from the example accident analysis are based on the calculation of the number of foreseeable premature cancer deaths the might result as a consequence of this accident. These calculations are presented, and the reference material forming the basis for all assumptions and calculations is also provided.

  9. Accident analysis of railway transportation of low-level radioactive and hazardous chemical wastes: Application of the /open quotes/Maximum Credible Accident/close quotes/ concept

    International Nuclear Information System (INIS)

    Ricci, E.; McLean, R.B.

    1988-09-01

    The maximum credible accident (MCA) approach to accident analysis places an upper bound on the potential adverse effects of a proposed action by using conservative but simplifying assumptions. It is often used when data are lacking to support a more realistic scenario or when MCA calculations result in acceptable consequences. The MCA approach can also be combined with realistic scenarios to assess potential adverse effects. This report presents a guide for the preparation of transportation accident analyses based on the use of the MCA concept. Rail transportation of contaminated wastes is used as an example. The example is the analysis of the environmental impact of the potential derailment of a train transporting a large shipment of wastes. The shipment is assumed to be contaminated with polychlorinated biphenyls and low-level radioactivities of uranium and technetium. The train is assumed to plunge into a river used as a source of drinking water. The conclusions from the example accident analysis are based on the calculation of the number of foreseeable premature cancer deaths the might result as a consequence of this accident. These calculations are presented, and the reference material forming the basis for all assumptions and calculations is also provided

  10. Analysis of factors related to man-induced hazard for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young

    2003-03-01

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out

  11. Analysis of factors related to man-induced hazard for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young [Seoul National Univ. of Technology, Seoul (Korea, Republic of)

    2003-03-15

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out.

  12. Evaluation of severe accident environmental conditions taking accident management strategy into account for equipment survivability assessments

    International Nuclear Information System (INIS)

    Lee, Byung Chul; Jeong, Ji Hwan; Na, Man Gyun; Kim, Soong Pyung

    2003-01-01

    This paper presents a methodology utilizing accident management strategy in order to determine accident environmental conditions in equipment survivability assessments. In case that there is well-established accident management strategy for specific nuclear power plant, an application of this tool can provide a technical rationale on equipment survivability assessment so that plant-specific and time-dependent accident environmental conditions could be practically and realistically defined in accordance with the equipment and instrumentation required for accident management strategy or action appropriately taken. For this work, three different tools are introduced; Probabilistic Safety Assessment (PSA) outcomes, major accident management strategy actions, and Accident Environmental Stages (AESs). In order to quantitatively investigate an applicability of accident management strategy to equipment survivability, the accident simulation for a most likely scenario in Korean Standard Nuclear Power Plants (KSNPs) is performed with MAAP4 code. The Accident Management Guidance (AMG) actions such as the Reactor Control System (RCS) depressurization, water injection into the RCS, the containment pressure and temperature control, and hydrogen concentration control in containment are applied. The effects of these AMG actions on the accident environmental conditions are investigated by comparing with those from previous normal accident simulation, especially focused on equipment survivability assessment. As a result, the AMG-involved case shows the higher accident consequences along the accident environmental stages

  13. A five-year history of hazardous materials incidents in Chester County, PA

    International Nuclear Information System (INIS)

    Shorten, C.V.; McNamara, J.

    1993-01-01

    The Emergency Planning and Community Right-to-Know Act (EPCRA) of 1986 established Local Emergency Planning Committees (LEPCs) to oversee emergency response planning at the community level. In Pennsylvania, each county was assigned its own LEPC, and Chester County held its first LEPC meeting on October 15, 1987. From the data of that meeting through September 1992, 300 hazardous materials incidents have been reported. The majority of these incidents were met with fire department response, but several warranted response by hazardous materials teams. This report presents an analysis of the database of reported hazardous materials incidents in Chester County, including chemical identification, amount released, type of response, location, and trends. Over 235 of the reported spills were either gasoline, diesel fuel, home heating oil, or kerosene, often in five to 50 gallon amounts from transportation accidents. A number of extremely hazardous substance (EHS) incidents were reported, however, including sulfuric acid, chlorine, ammonia, phosphorus, formaldehyde, bromine, methyl mercaptan, and hydrofluoric acid. The most commonly released EHS's were ammonia and chlorine. The number of hazardous materials incidents reported in Chester County increased from only 14 in 1988 to 95 in 1991, with 67 in 1992 through September. This dramatic increase is attributable to both increased reporting and an increased number of incidents. This database clearly indicates both the success of EPCRA reporting system and the magnitude of hazardous materials incidents in this part of Pennsylvania

  14. Description of the information and calculation system for combatment of accidents with hazardous materials

    International Nuclear Information System (INIS)

    Scheur, M.J. van de; Stolk, D.J.

    1987-04-01

    On request of the Netherlands government by TNO a decision support system is developed for the assessment of the off-site consequences of an accident with toxic or radioactive materials. The interactive system supports the emergency planning in two ways. First, the risk to the residents in the surroundings of the accident is quantified in terms of severity and magnitude. Second, a set of countermeasures is evaluated by which an optimum strategy to reduce the impact of the accident can be determined. At this moment the system is in a development stage. It turned out that even the preliminary system provides information to the decision process that is urgently needed. This specifically refers to the introduction of the time aspects and the quantification of the damage. 7 refs.; 8 figs.; 3 tabs

  15. Emergency preparedness and response in case of a fire accident with (UF{sub 6}) packages tracking Suez Canal

    Energy Technology Data Exchange (ETDEWEB)

    Salama, M. [National Center for Nuclear Safety and Radiation Control (NCNSRC), Nasr City, Cairo (Egypt)

    2004-07-01

    Egypt has a unique problem - the Suez Canal. Radioactive cargo passing regularly through the canal carrying new and spent reactor fuel. Moreover there are also about 1000 metric tons of uranium hexaflouride (UF6) passing through the canal every year. In spite of all precautions taken in the transportation, accidents with packages containing (UF{sub 6}) and shipped through the Suez Canal, accidents may arise even though the probability is minimal. These accidents, may be accompanied by injuries or death of persons and damage to property. Due to the radiation and criticality hazards of (UF{sub 6}) and its high risk of chemical toxicity. The probability of a fire accident with a cargo carrying (UF{sub 6}) during its crossing the Suez Canal can cause serious chemical toxic and radiological hazards, particularly if the accident occurred close or near to one of the three densely populated cities (Port-Said, Ismailia, and Suez), which are located along the Suez Canal, west bank. The government of Egypt has elaborated a national radiological emergency plan inorder to face probable radiological accidents, which may be arised inside the country. Arrangements have been also elaborated for the medical care of any persons who, might be injured or contaminated, or who, have been exposed to severe radiation doses. The motivation of the present paper was undertaken to visualize a fire accident scenario occurring in industrial packages containing UF6 on board of a Cargo crossing the Suez Canal near Port-Said City. The accident scenario and emergency response actions taken during the different phases of the accident are going to be presented and discussed. The proposed emergency response actions taken to face the accident are going to be also presented. The work presented had revealed the importance of public awareness will be needed for populations located in densely populated areas along Suez Canal bank inorder to react timely and effectively to avoid the toxic and radiological

  16. Fukushima, an accident which will leave a deep mark in the nuclear industry; Fukushima, un accident qui laissera une marque profonde sur le nucleaire civil

    Energy Technology Data Exchange (ETDEWEB)

    Vallee, Alain [International Nuclear Academy, 1, avenue de Verdun, BP 60190, 71105 Chalon-sur-Saone Cedex (France)

    2011-07-01

    Fukushima is the third major accident in the short history of civilian nuclear reactors. As the two previous ones, Three Mile Island and Chernobyl, it has delivered lessons which have to be learnt by governments, nuclear organizations and industry. Among them, the most important ones are the followings: - The past upgrades of the operating reactors against severe accidents has to be reassessed; - The requirements on the plant to sustain external hazards (earthquakes, flooding,...) has to be reviewed and improved in some cases; - Plants have to be tested against unrealistic situations to verify that no cliff edge effect can be expected; - The competence and the independence of the Safety Bodies have to be verified. The situation in the Fukushima reactors is not yet completely stabilized and it will take years before a return to normal life in the vicinity can take place; nevertheless, considering the size of the disaster, due to the exceptional magnitude of the earthquake and the height of the tsunami, the consequences of the nuclear part of the event are rather low: no casualty and limited risks of cancer for people in the future. (author)

  17. Evaluating a multi-criteria model for hazard assessment in urban design. The Porto Marghera case study

    International Nuclear Information System (INIS)

    Luria, Paolo; Aspinall, Peter A.

    2003-01-01

    The aim of this paper is to describe a new approach to major industrial hazard assessment, which has been recently studied by the authors in conjunction with the Italian Environmental Protection Agency ('ARPAV'). The real opportunity for developing a different approach arose from the need of the Italian EPA to provide the Venice Port Authority with an appropriate estimation of major industrial hazards in Porto Marghera, an industrial estate near Venice (Italy). However, the standard model, the quantitative risk analysis (QRA), only provided a list of individual quantitative risk values, related to single locations. The experimental model is based on a multi-criteria approach--the Analytic Hierarchy Process--which introduces the use of expert opinions, complementary skills and expertise from different disciplines in conjunction with quantitative traditional analysis. This permitted the generation of quantitative data on risk assessment from a series of qualitative assessments, on the present situation and on three other future scenarios, and use of this information as indirect quantitative measures, which could be aggregated for obtaining the global risk rate. This approach is in line with the main concepts proposed by the last European directive on Major Hazard Accidents, which recommends increasing the participation of operators, taking the other players into account and, moreover, paying more attention to the concepts of 'urban control', 'subjective risk' (risk perception) and intangible factors (factors not directly quantifiable)

  18. Tsunami hazard

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Tohoku Earthquake Tsunami on 11 March, 2011 has led the Fukushima Daiichi nuclear power plant to a serious accident, which highlighted a variety of technical issues such as a very low design tsunami height and insufficient preparations in case a tsunami exceeding the design tsunami height. Lessons such as to take measures to be able to maintain the important safety features of the facility for tsunamis exceeding design height and to implement risk management utilizing Probabilistic Safety Assessment are shown. In order to implement the safety assessment on nuclear power plants across Japan accordingly to the back-fit rule, Nuclear Regulatory Commission will promulgate/execute the New Safety Design Criteria in July 2013. JNES has positioned the 'enhancement of probabilistic tsunami hazard assessment' as highest priority issue and implemented in order to support technically the Nuclear Regulatory Authority in formulating the new Safety Design Criteria. Findings of the research had reflected in the 'Technical Review Guidelines for Assessing Design Tsunami Height based on tsunami hazards'. (author)

  19. Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Hoover, M.D.; Newton, G.J.; Farrell, R.F.

    1996-01-01

    This qualitative hazard evaluation systematically assessed potential doses to workers during postulated accident conditions at the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP). Postulated accidents included the spontaneous ignition of a waste drum, puncture of a waste drum by a forklift, dropping of a waste drum from a forklift, and simultaneous dropping of seven drums during a crane failure. The descriptions and estimated frequencies of occurrence for these accidents were developed by the Hazard and Operability Study for CH TRU Waste Handling System (WCAP 14312). The estimated materials at risk, damage ratios, airborne release fractions and respirable fractions for these accidents were taken from the 1995 Safety Analysis Report (SAR) update and from the DOE handbook Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities (DOE-HDBK-3010-94). A Monte Carlo simulation was used to estimate the range of worker exposures that could result from each accident. Guidelines for evaluating the adequacy of defense-in-depth for worker protection at WIPP were adopted from a scheme presented by the International Commission on Radiological Protection in its publication on Protection from Potential Exposure: A Conceptual Framework (ICRP Publication 64). Probabilities of exposures greater than 5, 50, and 300 rem were less than 10 -2 , 10 -4 , and 10 -6 per year, respectively. In conformance with the guidance of DOE standard 3009-94, Appendix A (draft), we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposure under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, as well as members of the public and the environment

  20. Simulation of severe accidents in COTELS experiments

    International Nuclear Information System (INIS)

    Vasilev, Yu.S.; Zhdanov, V.S.; Kolodeshnikov, A.A.; Kadyrov, Kh. G.; Turkebaev, T.E.; Tsaj, K.V.; Suslov, E.E.

    1999-01-01

    At present, the issue of atomic reactor operation safety is of a great attention. It is evident that the accident accompanied with a core materials melting is an improbable event. To fully assess a hazard of a reactor use and enhance its safety, it is necessary to predict a possible accident progress and specify possible consequences of severe accidents and eliminating measures. In COTELS experiments, aimed at investigation of interaction of corium with concrete and water, the corium s imulator m elt is discharged on the concrete. The concrete erosion parameters, composition and rate of aerosol and gas escaping are recorded. The solidified melt and concrete fragments structure is studied after the testing, using the X-ray diffractometer DRON-3. This paper gives consideration to possible mechanisms of formation of uranium-containing and other phases of products of interaction of the corium melt with concrete and water

  1. Health hazards from radiocaesium following the Chernobyl nuclear accident

    International Nuclear Information System (INIS)

    1987-01-01

    The WHO Regional Office for Europe has organized a series of meetings to assess the health impact of the Chernobyl nuclear accident. Considering the long-term importance of radiocaesium a decision was made to examine carefully the following aspects of this radionuclide in Europe: rate of deposition; environmental pathways through soil, flora and fauna to humans; absorption, distribution, metabolism, and excretion in humans; estimated doses resulting from these exposures; and some consideration of the possible adverse health effects. This is a report from a working group studying the health implications of radiocaesium. Refs, figs and tabs

  2. Monitoring and surveillance in accident situations

    International Nuclear Information System (INIS)

    Chadwick, K.; Menzel, H.

    1993-01-01

    The Chernobyl accident, which occurred on 26 April 1986, presented major challenges to the European Community with respect to the practical and regulatory aspects of radiation protection, public information, trade -particularly in food - and international politics. The Chernobyl accident was also a major challenge to the international scientific community which had to evaluate rapidly the radiological consequences of the accident and advise on the introduction at Chernobyl, countermeasures to reduce the consequences of radioactive contamination had been conceived largely in the context of relatively small accidental releases and for application over relatively small areas. Less consideration had been given to the practical implications of applying such measures in the case of a large source and a spread over a very large area

  3. A decision support system for emergency response to major nuclear accidents

    International Nuclear Information System (INIS)

    Papazoglou, I.A.; Christou, M.D.

    1997-01-01

    A methodology for the optimization of the short-term emergency response in the event of a nuclear accident is presented. The method seeks an optimum combination of protective actions in the presence of a multitude of conflicting objectives and under uncertainty. Conflicting objectives arise in the attempt to minimize simultaneously the potential adverse effects of an accident and the associated socioeconomic impacts. Additional conflicting objectives arise whenever an emergency plan tends to decrease a particular health effect, such as acute deaths, while it increases another, such as latent deaths. The uncertainty is due to the multitude of possible accident scenarios and their respective probability of occurrence, the stochastic variability in the weather conditions, and the variability and/or lack of knowledge of the parameters of the risk assessment models. A multiobjective optimization approach is adopted. An emergency protection plan consists of defining a protective action at each spatial cell around the plant. Three criteria are used as the objective functions of the problem, namely, acute fatalities, latent effects, and socioeconomic cost. The optimization procedure defines the efficient frontier, i.e., all emergency plans that are not dominated by another in all three criteria. No value trade-offs are necessary up to this point. The most preferred emergency plan is then chosen among the set of efficient plans. Finally, the methodology is integrated into a computerized decision support system, and its use is demonstrated in a realistic application

  4. STUDY OF ROAD TRAFFIC ACCIDENTS WITH SPECIAL REFERENCE TO THE ACCIDENT VICTIMS ADMITTED IN GAUHATI MEDICAL COLLEGE AND HOSPITAL, ASSAM

    Directory of Open Access Journals (Sweden)

    Rocket Chandra

    2016-05-01

    Full Text Available BACKGROUND In the present scenario, road traffic accidents have become a major cause of human mortality and morbidity. Accidents are increasing at alarming rates in India. The objective of our study was to assess the socio-demographic profile of road traffic accident victims admitted in a tertiary care setting, and to assess the pattern of injuries. METHODOLOGY The present study is prospective and analytical hospital based study. RESULTS The present studies show that more than 70% of the victims are in the age group of below 45 years (n=3196 and with male preponderance. Out of 14364 accident patients visiting the emergency department of Gauhati Medical College and Hospital, 4953 patients were admitted. The majorities of the patients (n=2995 were admitted in surgery department and 1586 in orthopaedic department. CONCLUSIONS Several factors are responsible for causing road accidents such as drunk driving, lack of awareness of traffic rules, nonadherence to safety measures. To reduce morbidity and mortality following road accidents, comprehensive policy has to be adopted by the government

  5. Implementing DOE guidance for hazards assessments at Rocky Flats Plant

    International Nuclear Information System (INIS)

    Zimmerman, G.A.

    1993-01-01

    Hazards Assessments are performed for a variety of activities and facilities at Rocky Flats Plant. Prior to 1991, there was no guidance for performing Hazards Assessments. Each organization that performed Hazards Assessments used its own methodology with no attempt at standardization. In 1991, DOE published guidelines for the performance of Hazards Assessments for Emergency Planning (DOE-EPG-5500.1, ''Guidance for a Hazards Assessment Methodology''). Subsequently, in 1992, DOE published a standard for the performance of Hazards Assessments (DOE-STD-1027-92, ''Hazard Categorization and Accident Analysis, Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports''). Although these documents are a step in the direction of standardization, there remains a great deal of interpretation and subjective implementation in the performance of Hazards Assessments. Rocky Flats Plant has initiated efforts to develop a uniform and standard process to be used for Hazards Assessments

  6. Analysis of Construction Accidents in Turkey and Responsible Parties

    Science.gov (United States)

    GÜRCANLI, G. Emre; MÜNGEN, Uğur

    2013-01-01

    Construction is one of the world’s biggest industry that includes jobs as diverse as building, civil engineering, demolition, renovation, repair and maintenance. Construction workers are exposed to a wide variety of hazards. This study analyzes 1,117 expert witness reports which were submitted to criminal and labour courts. These reports are from all regions of the country and cover the period 1972–2008. Accidents were classified by the consequence of the incident, time and main causes of the accident, construction type, occupation of the victim, activity at time of the accident and party responsible for the accident. Falls (54.1%), struck by thrown/falling object (12.9%), structural collapses (9.9%) and electrocutions (7.5%) rank first four places. The accidents were most likely between the hours 15:00 and 17:00 (22.6%), 10:00–12:00 (18.7%) and just after the lunchtime (9.9%). Additionally, the most common accidents were further divided into sub-types. Expert-witness assessments were used to identify the parties at fault and what acts of negligence typically lead to accidents. Nearly two thirds of the faulty and negligent acts are carried out by the employers and employees are responsible for almost one third of all cases. PMID:24077446

  7. Analysis of construction accidents in Turkey and responsible parties.

    Science.gov (United States)

    Gürcanli, G Emre; Müngen, Uğur

    2013-01-01

    Construction is one of the world's biggest industry that includes jobs as diverse as building, civil engineering, demolition, renovation, repair and maintenance. Construction workers are exposed to a wide variety of hazards. This study analyzes 1,117 expert witness reports which were submitted to criminal and labour courts. These reports are from all regions of the country and cover the period 1972-2008. Accidents were classified by the consequence of the incident, time and main causes of the accident, construction type, occupation of the victim, activity at time of the accident and party responsible for the accident. Falls (54.1%), struck by thrown/falling object (12.9%), structural collapses (9.9%) and electrocutions (7.5%) rank first four places. The accidents were most likely between the hours 15:00 and 17:00 (22.6%), 10:00-12:00 (18.7%) and just after the lunchtime (9.9%). Additionally, the most common accidents were further divided into sub-types. Expert-witness assessments were used to identify the parties at fault and what acts of negligence typically lead to accidents. Nearly two thirds of the faulty and negligent acts are carried out by the employers and employees are responsible for almost one third of all cases.

  8. Incidents with hazardous radiation sources; Zwischenfaelle mit gefaehrlichen Strahlenquellen

    Energy Technology Data Exchange (ETDEWEB)

    Schoenhacker, Stefan [Bundesministerium fuer Inneres, Traiskirchen (Austria). Abt. 1/9 - Zivilschutzschule

    2016-07-01

    Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

  9. Severe accidents in nuclear reactors

    International Nuclear Information System (INIS)

    Ohai, Dumitru; Dumitrescu, Iulia; Tunaru, Mariana

    2004-01-01

    The likelihood of accidents leading to core meltdown in nuclear reactors is low. The consequences of such an event are but so severe that developing and implementing of adequate measures for preventing or diminishing the consequences of such events are of paramount importance. The analysis of major accidents requires sophisticated computation codes but necessary are also relevant experiments for checking the accuracy of the predictions and capability of these codes. In this paper an overview of the severe accidents worldwide with definitions, computation codes and relating experiments is presented. The experimental research activity of severe accidents was conducted in INR Pitesti since 2003, when the Institute jointed the SARNET Excellence Network. The INR activity within SARNET consists in studying scenarios of severe accidents by means of ASTEC and RELAP/SCDAP codes and conducting bench-scale experiments

  10. [Traffic accidents associated with emotional stress after divorce].

    Science.gov (United States)

    Cui, Li-Juan; Yi, Xu-Fu; Chen, Xiao-Gang

    2009-04-01

    In recent years, the traffic accidents increased gradually, especially those caused by the drivers daily emotional abnormality and in which the drivers were liable. This article reviewed the traffic accidents caused by divorced driver's emotional abnormality, illustrated the features of those accidents from the gender, age, occupation and mileage of drivers. It was considered that the major cause of those accidents was excessive drinking due to drivers' emotional stress. Suggestions about preventing the traffic accidents caused by emotional abnormality were put forward so as to make the corresponding rules and finally decrease the emotional abnormality traffic accidents.

  11. Accident statistics for fixed offshore units on the UK Continental Shelf 1980-2001

    International Nuclear Information System (INIS)

    Funnemark, E.; Young, E.

    2003-01-01

    Comprehensive statistics for the accidents and incidents on fixed units engaged in oil and gas exploration/exploitation on the UK continental shelf between 1980 and 2001 have been assembled from other databases. The data includes nature of the incident, type of unit involved, geographical area and time period. The results cover a total of 5,563 events which are described as accidents, hazardous situations or near misses

  12. Consequences of major nuclear accidents on wild fauna and flora: dosimetric assessments remain a weakness to establish robust conclusions

    International Nuclear Information System (INIS)

    2014-01-01

    As about hundred of studies have been undertaken after the major nuclear accidents (Chernobyl and Fukushima) to study the consequences of these accidents on wild flora and fauna, notably on the effects of low doses of ionizing radiations, it appears that some of them reported noticeable effects due to extremely low doses. Such findings put knowledge in radiobiology into question again. This note aims at discussing the importance of the quality of dosimetric assessments for any study performed 'in natura'. It seems that the ambient external dose rate is not systematically a good indicator of the dose or dose rate absorbed by a living organism in radio-contaminated environment. This note outlines the problem related to the spatial heterogeneity of the radioactive contamination, that some statistic methods are not always adapted to data set quality. It briefly indicates other factors which may affect the quality of data set obtained during in situ studies

  13. The Fukushima major accident. Seismic, nuclear and medical considerations

    International Nuclear Information System (INIS)

    Carpentier, Alain; Friedel, Jacques; Brezin, Edouard; Baulieu, Etienne-Emile; Courtillot, Vincent; Dercourt, Jean; Jaupart, Claude; Le Pichon, Xavier; Poirier, Jean-Paul; Salencon, Jean; Tapponnier, Paul; Dautray, Robert; Taquet, Philippe; Blanchet, Rene; Le Mouel, Jean-Louis; Chapron, Jean-Yves; Fanon, Joelle; BARD, Pierre-Yves; Bernard, Pascal; Montagner, Jean-Paul; Armijo, Rolando; Shapiro, Nikolai; Tait, Steve; Cara, Michel; Madariaga, Raul; Pecker, Alain; Schindele, Francois; Douglas, John

    2011-01-01

    The first part of this voluminous report addresses mega-earthquakes and mega-tsunamis: scientific data, case of France (West Indies and metropolitan France), and socioeconomic aspects (governance, regulation, para-seismic protection). The second part deals with the nuclear accident at Fukushima: event sequence, situation of the nuclear industry in France after Fukushima, fuel cycle and future opportunities. The third part addresses health and environmental consequences. Each part is completed by a large number of documents in which some specific aspects are more precisely reported, commented and discussed

  14. The investigation of the impacts of major disasters, on the basis of the Van earthquake (October 23, 2011, Turkey), on the profile of the injuries due to occupational accidents.

    Science.gov (United States)

    Hekimoglu, Yavuz; Dursun, Recep; Karadas, Sevdegul; Asirdizer, Mahmut

    2015-10-01

    The purpose of this study is to identify the impacts of major disasters, on the basis of the Van earthquake (October 23, 2011, Turkey), on the profile of the injuries due to occupational accidents. In this study, we evaluated 245 patients of occupational accidents who were admitted to emergency services of Van city hospitals in the 1-year periods including pre-earthquake and post-earthquake. We determined that there was a 63.4% (P accidents in the post-earthquake period compared to the pre-earthquake period. Also, injuries due to occupational accidents increased 211% (P accidents. In this study, the impact of disasters such as earthquakes on the accidents at work was evaluated as we have not seen in literature. This study emphasizes that governments should make regulations and process relating to the post-disaster business before the emergence of disaster by taking into account factors that may increase their work-related accidents. Copyright © 2015 Elsevier Ltd and Faculty of Forensic and Legal Medicine. All rights reserved.

  15. Intranet-based safety documentation in management of major hazards and occupational health and safety.

    Science.gov (United States)

    Leino, Antti

    2002-01-01

    In the European Union, Council Directive 96/82/EC requires operators producing, using, or handling significant amounts of dangerous substances to improve their safety management systems in order to better manage the major accident potentials deriving from human error. A new safety management system for the Viikinmäki wastewater treatment plant in Helsinki, Finland, was implemented in this study. The system was designed to comply with both the new safety liabilities and the requirements of OHSAS 18001 (British Standards Institute, 1999). During the implementation phase experiences were gathered from the development processes in this small organisation. The complete documentation was placed in the intranet of the plant. Hyperlinks between documents were created to ensure convenience of use. Documentation was made accessible for all workers from every workstation.

  16. An Approach to Human Error Hazard Detection of Unexpected Situations in NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sangjun; Oh, Yeonju; Shin, Youmin; Lee, Yong-Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Fukushima accident is a typical complex event including the extreme situations induced by the succeeding earthquake, tsunami, explosion, and human errors. And it is judged with incomplete cause of system build-up same manner, procedure as a deficiency of response manual, education and training, team capability and the discharge of operator from human engineering point of view. Especially, the guidelines of current operating NPPs are not enough including countermeasures to the human errors at the extreme situations. Therefore, this paper describes a trial to detect the hazards of human errors at extreme situation, and to define the countermeasures that can properly response to the human error hazards when an individual, team, organization, and working entities that encounter the extreme situation in NPPs. In this paper we try to propose an approach to analyzing and extracting human error hazards for suggesting additional countermeasures to the human errors in unexpected situations. They might be utilized to develop contingency guidelines, especially for reducing the human error accident in NPPs. But the trial application in this study is currently limited since it is not easy to find accidents cases in detail enough to enumerate the proposed steps. Therefore, we will try to analyze as more cases as possible, and consider other environmental factors and human error conditions.

  17. An Approach to Human Error Hazard Detection of Unexpected Situations in NPPs

    International Nuclear Information System (INIS)

    Park, Sangjun; Oh, Yeonju; Shin, Youmin; Lee, Yong-Hee

    2015-01-01

    Fukushima accident is a typical complex event including the extreme situations induced by the succeeding earthquake, tsunami, explosion, and human errors. And it is judged with incomplete cause of system build-up same manner, procedure as a deficiency of response manual, education and training, team capability and the discharge of operator from human engineering point of view. Especially, the guidelines of current operating NPPs are not enough including countermeasures to the human errors at the extreme situations. Therefore, this paper describes a trial to detect the hazards of human errors at extreme situation, and to define the countermeasures that can properly response to the human error hazards when an individual, team, organization, and working entities that encounter the extreme situation in NPPs. In this paper we try to propose an approach to analyzing and extracting human error hazards for suggesting additional countermeasures to the human errors in unexpected situations. They might be utilized to develop contingency guidelines, especially for reducing the human error accident in NPPs. But the trial application in this study is currently limited since it is not easy to find accidents cases in detail enough to enumerate the proposed steps. Therefore, we will try to analyze as more cases as possible, and consider other environmental factors and human error conditions

  18. Safety in Academic Chemistry Laboratories: Volume 1. Accident Prevention for College and University Students, 7th Edition.

    Science.gov (United States)

    American Chemical Society, Washington, DC.

    This book contains volume 1 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Your Responsibility for Accident Prevention"; (2) "Guide to Chemical Hazards"; (3) "Recommended Laboratory Techniques"; and (4) "Safety Equipment and Emergency…

  19. Study of evacuation times based on recent accident history

    International Nuclear Information System (INIS)

    Mills, G.S.; Neuhauser, K.S.

    1995-01-01

    A key parameter in the calculation of accident dose-risks by the RADTRAN 4 code is the time assigned for evacuation of the affected area surrounding the accident. Currently, in the interest of assured conservatism, this time is set at 24 hrs. Casual anecdotal evidence has indicated that this value is overly conservative and results in assignment of overly conservative estimates of accident dose-risk. Therefore, a survey of recent truck accidents involving various hazardous materials which required evacuation of surrounding populations reported in various news media was undertaken. Accounts of pertinent scenarios were gleaned from databases citing newspapers and other periodicals, and the local authorities involved in each were contacted to get details of the evacuation including time required. This paper presents the data obtained in the study and the resultant mean evacuation time plus limits and factors influencing specific results together with conclusions regarding the appropriate value to be used in the RADTRAN 4 code

  20. Issues and challenges for pedestrian active safety systems based on real world accidents.

    Science.gov (United States)

    Hamdane, Hédi; Serre, Thierry; Masson, Catherine; Anderson, Robert

    2015-09-01

    The purpose of this study was to analyze real crashes involving pedestrians in order to evaluate the potential effectiveness of autonomous emergency braking systems (AEB) in pedestrian protection. A sample of 100 real accident cases were reconstructed providing a comprehensive set of data describing the interaction between the vehicle, the environment and the pedestrian all along the scenario of the accident. A generic AEB system based on a camera sensor for pedestrian detection was modeled in order to identify the functionality of its different attributes in the timeline of each crash scenario. These attributes were assessed to determine their impact on pedestrian safety. The influence of the detection and the activation of the AEB system were explored by varying the field of view (FOV) of the sensor and the level of deceleration. A FOV of 35° was estimated to be required to detect and react to the majority of crash scenarios. For the reaction of a system (from hazard detection to triggering the brakes), between 0.5 and 1s appears necessary. Copyright © 2015 Elsevier Ltd. All rights reserved.

  1. Hazardous alcohol consumption is a major factor in male premature mortality in a typical Russian city: prospective cohort study 2003-2009.

    Directory of Open Access Journals (Sweden)

    Susannah Tomkins

    Full Text Available Russia has experienced massive fluctuations in mortality at working ages over the past three decades. Routine data analyses suggest that these are largely driven by fluctuations in heavy alcohol drinking. However, individual-level evidence supporting alcohol having a major role in Russian mortality comes from only two case-control studies, which could be subject to serious biases due to their design.A prospective study of mortality (2003-9 of 2000 men aged 25-54 years at recruitment was conducted in the city of Izhevsk, Russia. This cohort was free from key limitations inherent in the design of the two earlier case-control studies. Cox proportional hazards regression was used to estimate hazard ratios of all-cause mortality by alcohol drinking type as reported by a proxy informant. Hazardous drinkers were defined as those who either drank non-beverage alcohols or were reported to regularly have hangovers or other behaviours related to heavy drinking episodes. Over the follow-up period 113 men died. Compared to non-hazardous drinkers and abstainers, men who drank hazardously had appreciably higher mortality (HR = 3.4, 95% CI 2.2, 5.1 adjusted for age, smoking and education. The population attributable risk percent (PAR% for hazardous drinking was 26% (95% CI 14,37. However, larger effects were seen in the first two years of follow-up, with a HR of 4.6 (2.5, 8.2 and a corresponding PAR% of 37% (17, 51.This prospective cohort study strengthens the evidence that hazardous alcohol consumption has been a major determinant of mortality among working age men in a typical Russian city. As such the similar findings of the previous case-control studies cannot be explained as artefacts of limitations of their design. As Russia struggles to raise life expectancy, which even in 2009 was only 62 years among men, control of hazardous drinking must remain a top public health priority.

  2. A review of criticality accidents

    International Nuclear Information System (INIS)

    Stratton, W.R.; Smith, D.R.

    1989-03-01

    Criticality accidents and the characteristics of prompt power excursions are discussed. Forty-one accidental power transients are reviewed. In each case where available, enough detail is given to help visualize the physical situation, the cause or causes of the accident, the history and characteristics of the transient, the energy release, and the consequences, if any, to personnel and property. Excursions associated with large power reactors are not included in this study, except that some information on the major accident at the Chernobyl reactor in April 1986 is provided in the Appendix. 67 refs., 21 figs., 2 tabs

  3. Accident frequency and unrealistic optimism: Children's assessment of risk.

    Science.gov (United States)

    Joshi, Mary Sissons; Maclean, Morag; Stevens, Claire

    2018-02-01

    Accidental injury is a major cause of mortality and morbidity among children, warranting research on their risk perceptions. Three hundred and seven children aged 10-11 years assessed the frequency, danger and personal risk likelihood of 8 accidents. Two social-cognitive biases were manifested. The frequency of rare accidents (e.g. drowning) was overestimated, and the frequency of common accidents (e.g. bike accidents) underestimated; and the majority of children showed unrealistic optimism tending to see themselves as less likely to suffer these accidents in comparison to their peers, offering superior skills or parental control of the environment as an explanation. In the case of pedestrian accidents, children recognised their seriousness, underestimated the frequency of this risk and regarded their own road crossing skill as protection. These findings highlight the challenging task facing safety educators who, when teaching conventional safety knowledge and routines, also need to alert children to the danger of over-confidence without disabling them though fear. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. A statistical description of the types and severities of accidents involving tractor semi-trailers

    International Nuclear Information System (INIS)

    Clauss, D.B.; Wilson, R.K.; Blower, D.F.; Campbell, K.L.

    1994-06-01

    This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. Several accident databases were reviewed to determine their suitability to the task. The TIFA (Trucks Involved in Fatal Accidents) database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports for selected TIFA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, fire temperature, fire size, fire separation, and fire duration

  5. Accident risks in nuclear facilities (a bibliography with abstracts). Report for 1964-Sep 76

    International Nuclear Information System (INIS)

    Grooms, D.W.

    1976-10-01

    The bibliography presents risk analysis and hazards evaluation of the design, construction and operation of nuclear facilities including the risk and hazards of transporting radioactive materials to and from these facilities. Radiological calculations for environmental effects of nuclear accidents are included. (This updated bibliography contains 195 abstracts, 64 of which are new entries to the previous edition.)

  6. Seismic design criteria and their application to major hazard plant within the United Kingdom

    International Nuclear Information System (INIS)

    Alderson, M.A.H.G.

    1982-12-01

    The nature of seismic motions and the implications are briefly described and the development of seismic design criteria for nuclear power plants in various countries is described including possible future developments. The seismicity of the United Kingdom is briefly reviewed leading to the present position on seismic design criteria for nuclear power plants within the United Kingdom. Damage from past destructive earthquakes is reviewed and the existing codes of practice and standards are described. Finally the effect of earthquakes on major hazard plant is discussed in general terms including the seismic analysis of a typical plant item. (author)

  7. Helicopter emergency medical services response to equestrian accidents.

    Science.gov (United States)

    Lyon, Richard M; Macauley, Ben; Richardson, Sarah; de Coverly, Richard; Russell, Malcolm

    2015-04-01

    Horse riding is a common leisure activity associated with a significant rate of injury. Helicopter emergency medical services (HEMS) may be called to equestrian accidents. Accurate HEMS tasking is important to ensure appropriate use of this valuable medical resource. We sought to review HEMS response to equestrian accidents and identify factors associated with the need for HEMS intervention or transport of the patient to a major trauma centre. Retrospective case review of all missions flown by Kent, Surrey & Sussex Air Ambulance Trust over a 1-year period (1 July 2011 to 1 July 2012). All missions were screened for accidents involving a horse. Call details, patient demographics, suspected injuries, clinical interventions and patient disposition were all analysed. In the 12-month data collection period there were 47 equestrian accidents, representing ∼3% of the total annual missions. Of the 42 cases HEMS attended, one patient was pronounced life extinct at the scene. In 15 (36%) cases the patient was airlifted to hospital. In four (10%) cases, the patient underwent prehospital anaesthesia. There were no specific predictors of HEMS intervention. Admission to a major trauma centre was associated with the rider not wearing a helmet, a fall onto their head or the horse falling onto the rider. Equestrian accidents represent a significant proportion of HEMS missions. The majority of patients injured in equestrian accidents do not require HEMS intervention, however, a small proportion have life-threatening injuries, requiring immediate critical intervention. Further research is warranted, particularly regarding HEMS dispatch, to further improve accuracy of tasking to equestrian accidents.

  8. Environmental measurements during the TMI-2 accident

    International Nuclear Information System (INIS)

    Hull, A.P.

    1988-01-01

    Although the environmental consequences of the TMI accident were relatively insignificant, it was a major test of the ability of the involved state and federal radiological agencies to make a coordinated environmental monitoring response. This was accomplished largely on an ad hoc basis under the leadership of DOE. With some fine tuning, it is the basis for today's integrated FRMAP monitoring plan, which would be put into operation should another major accident occur at a US nuclear facility

  9. [Preparation of the database and the homepage on chemical accidents relating to health hazard].

    Science.gov (United States)

    Yamamoto, M; Morita, M; Kaminuma, T

    1998-01-01

    We collected the data on accidents due to chemicals occurred in Japan, and prepared the database. We also set up the World Wide Web homepage containing the explanation on accidents due to chemicals and the retrieval page for the database. We designed the retrieval page so that users can search the data from keywords such as chemicals (e.g. chlorine gas, hydrogen sulfide, pesticides), places (e.g. home, factory, vehicles, tank), causes (e.g. reaction, leakage, exhaust gas) and others (e.g. cleaning, painting, transportation).

  10. Occurrence and countermeasures of urban power grid accident

    Science.gov (United States)

    Wei, Wang; Tao, Zhang

    2018-03-01

    With the advance of technology, the development of network communication and the extensive use of power grids, people can get to know power grid accidents around the world through the network timely. Power grid accidents occur frequently. Large-scale power system blackout and casualty accidents caused by electric shock are also fairly commonplace. All of those accidents have seriously endangered the property and personal safety of the country and people, and the development of society and economy is severely affected by power grid accidents. Through the researches on several typical cases of power grid accidents at home and abroad in recent years and taking these accident cases as the research object, this paper will analyze the three major factors that cause power grid accidents at present. At the same time, combining with various factors and impacts caused by power grid accidents, the paper will put forward corresponding solutions and suggestions to prevent the occurrence of the accident and lower the impact of the accident.

  11. Fatal accidents analysis in Peruvian mining industry

    International Nuclear Information System (INIS)

    Candia, R. C.; Hennies, W. T.; Azevedo, R. c.; Almeida, I.G.; Soto, J. F.

    2010-01-01

    Although reductions in the tax of injuries and accidents have been observed in recent years, Mining is still one of the highest risks industries. The basic causes for occurrence of fatalities can be attributed to unsafe conditions and unsafe acts. In this scene is necessary to identify safety problems and to aim the effective solutions. On the other hand, the developing countries dependence on primary industries as mining is evident. In the Peruvian economy, approximately 16% of the GNP and more than 50% of the exportations are due to the mining sector, detaching its competitive position in the worldwide mining. This paper presents fatal accidents analysis in the Peruvian mining industry, having as basis the register of occurred fatal accidents since year 2000 until 2007, identifying the main types of accidents occurred. The source of primary information is the General Mining Direction (DGM) of the Peruvian Mining and Energy Ministry (MEM). The majority of victims belongs to tertiary contractor companies that render services for mine companies. The results of the analysis show also that the majority of accidents happened in the underground mines, and that it is necessary to propose effective solutions to manage risks, aiming at reducing the fatal accidents taxes. (Author)

  12. Example process hazard analysis of a Department of Energy water chlorination process

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    On February 24, 1992, the Occupational Safety and Health Administration (OSHA) released a revised version of Section 29 Code of Federal Regulations CFR Part 1910 that added Section 1910.119, entitled ``Process Safety Management of Highly Hazardous Chemicals`` (the PSM Rule). Because US Department of Energy (DOE) Orders 5480.4 and 5483.1A prescribe OSHA 29 CFR 1910 as a standard in DOE, the PSM Rule is mandatory in the DOE complex. A major element in the PSM Rule is the process hazard analysis (PrHA), which is required for all chemical processes covered by the PSM Rule. The PrHA element of the PSM Rule requires the selection and application of appropriate hazard analysis methods to systematically identify hazards and potential accident scenarios associated with processes involving highly hazardous chemicals (HHCs). The analysis in this report is an example PrHA performed to meet the requirements of the PSM Rule. The PrHA method used in this example is the hazard and operability (HAZOP) study, and the process studied is the new Hanford 300-Area Water Treatment Facility chlorination process, which is currently in the design stage. The HAZOP study was conducted on May 18--21, 1993, by a team from the Westinghouse Hanford Company (WHC), Battelle-Columbus, the DOE, and Pacific Northwest Laboratory (PNL). The chlorination process was chosen as the example process because it is common to many DOE sites, and because quantities of chlorine at those sites generally exceed the OSHA threshold quantities (TQs).

  13. Research on the management of the wastes from plant accidents

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The accident in Fukushima Daiichi Nuclear Power Plant released large amount of radio-nuclides and contaminated wide areas within and out of the site. The decontamination, storage, treatment and disposal of generated wastes are now under planning. Though the regulations for radioactive wastes discharged from normal operation and decommissioning of nuclear facilities have been prepared, it is necessary to make amendments of those regulations to deal with wastes from the severe accidents which may have much different features on nuclides contents, or possibility to accompany hazardous chemical materials. Characteristics, treatment and disposal of wastes from accidents were surveyed by literature and the radionuclide migration from the assumed temporally storage yards of the disaster debris was analyzed for consideration of future regulation. (author)

  14. Bibliography for nuclear criticality accident experience, alarm systems, and emergency management

    International Nuclear Information System (INIS)

    Putman, V.L.

    1995-09-01

    The characteristics, detection, and emergency management of nuclear criticality accidents outside reactors has been an important component of criticality safety for as long as the need for this specialized safety discipline has been recognized. The general interest and importance of such topics receives special emphasis because of the potentially lethal, albeit highly localized, effects of criticality accidents and because of heightened public and regulatory concerns for any undesirable event in nuclear and radiological fields. This bibliography lists references which are potentially applicable to or interesting for criticality alarm, detection, and warning systems; criticality accident emergency management; and their associated programs. The lists are annotated to assist bibliography users in identifying applicable: industry and regulatory guidance and requirements, with historical development information and comments; criticality accident characteristics, consequences, experiences, and responses; hazard-, risk-, or safety-analysis criteria; CAS design and qualification criteria; CAS calibration, maintenance, repair, and testing criteria; experiences of CAS designers and maintainers; criticality accident emergency management (planning, preparedness, response, and recovery) requirements and guidance; criticality accident emergency management experience, plans, and techniques; methods and tools for analysis; and additional bibliographies

  15. Accident investigation practices in Europe--main responses from a recent study of accidents in industry and transport.

    Science.gov (United States)

    Roed-Larsen, Sverre; Valvisto, T; Harms-Ringdahl, L; Kirchsteiger, C

    2004-07-26

    Europe has during recent years been shocked by disasters from natural events and technical breakdowns. The consequences have been comprehensive, measured by lost lives, injuries, and material and environmental damage. ESReDA wanted in 2000--by setting up a special expert group on accident investigation--to clarify the state of art of accident investigation practices and to map the use of thoroughly accident investigation in order to learn lessons from past disasters and prevent new ones. The scope was to cover three sectors in the society: transport, production processes and storage of hazardous materials, and energy production. The main method used was a questionnaire, which was sent in 2001 to about 150 organisations. About 50 replies were analysed. The replies showed great variations but also similarities, among others in definition of accident and incident, the objectives of the investigation team, criteria used to start an investigation, the status of the investigation organisation, the flow of information, the composition of the investigation team, and the use of internal or international procedures or rules. Several methods (in total 14 different methods were mentioned) were used for carrying out accident /incident investigations. Most of the respondents were willing to co-operate in one or another way with ESReDA. Although there are important biases in the material, the results from questionnaire are important inputs to the future work of ESReDA Expert group in this field. 3 safety approaches have been identified.

  16. HANARO thermal hydraulic accident analysis

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chul; Kim, Heon Il; Lee, Bo Yook; Lee, Sang Yong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    For the safety assessment of HANARO, accident analyses for the anticipated operational transients, accident scenarios and limiting accident scenarios were conducted. To do this, the commercial nuclear reactor system code. RELAP5/MOD2 was modified to RELAP5/KMRR; the thermal hydraulic correlations and the heat exchanger model was changed to incorporate HANARO characteristics. This report summarizes the RELAP/KMRR calculation results and the subchannel analyses results based on the RELAP/KMRR results. During the calculation, major concern was placed on the integrity of the fuel. For all the scenarios, the important accident analysis parameters, i.e., fuel centerline temperatures and the minimum critical heat flux ratio(MCHFR), satisfied safe design limits. It was verified, therefore, that the HANARO was safely designed. 21 tabs., 89 figs., 39 refs. (Author) .new.

  17. Comparative analysis of the countermeasures taken to mitigate exposure of the public to radioiodine following the Chernobyl and Fukushima accidents: lessons from both accidents.

    Science.gov (United States)

    Uyba, Vladimir; Samoylov, Alexander; Shinkarev, Sergey

    2018-04-01

    In the case of a severe radiation accident at a nuclear power station, the most important radiation hazard for the public is internal exposure of the thyroid to radioiodine. The purposes of this paper were (i) to compare countermeasures conducted (following the Chernobyl and Fukushima accidents) aimed at mitigation of exposure to the thyroid for the public, (ii) to present comparative estimates of doses to the thyroid and (iii) to derive lessons from the two accidents. The scale and time of countermeasures applied in the early phase of the accidents (sheltering, evacuation, and intake of stable iodine to block the thyroid) and at a later time (control of 131I concentration in foodstuffs) have been described. After the Chernobyl accident, the estimation of the thyroid doses for the public was mainly based on direct thyroid measurements of ~400 000 residents carried out within the first 2 months. The highest estimates of thyroid doses to children reached 50 Gy. After the Fukushima accident, the estimation of thyroid doses was based on radioecological models due to a lack of direct thyroid measurements (only slightly more than 1000 residents were measured). The highest estimates of thyroid doses to children were a few hundred mGy. Following the Chernobyl accident, ingestion of 131I through cows' milk was the dominant pathway. Following the Fukushima accident, it appears that inhalation of contaminated air was the dominant pathway. Some lessons learned following the Chernobyl and Fukushima accidents have been presented in this paper.

  18. Facial trauma among victims of terrestrial transport accidents.

    Science.gov (United States)

    d'Avila, Sérgio; Barbosa, Kevan Guilherme Nóbrega; Bernardino, Ítalo de Macedo; da Nóbrega, Lorena Marques; Bento, Patrícia Meira; E Ferreira, Efigênia Ferreira

    2016-01-01

    In developing countries, terrestrial transport accidents - TTA, especially those involving automobiles and motorcycles - are a major cause of facial trauma, surpassing urban violence. This cross-sectional census study attempted to determine facial trauma occurrence with terrestrial transport accidents etiology, involving cars, motorcycles, or accidents with pedestrians in the northeastern region of Brazil, and examine victims' socio-demographic characteristics. Morbidity data from forensic service reports of victims who sought care from January to December 2012 were analyzed. Altogether, 2379 reports were evaluated, of which 673 were related to terrestrial transport accidents and 103 involved facial trauma. Three previously trained and calibrated researchers collected data using a specific form. Facial trauma occurrence rate was 15.3% (n=103). The most affected age group was 20-29 years (48.3%), and more men than women were affected (2.81:1). Motorcycles were involved in the majority of accidents resulting in facial trauma (66.3%). The occurrence of facial trauma in terrestrial transport accident victims tends to affect a greater proportion of young and male subjects, and the most prevalent accidents involve motorcycles. Copyright © 2015 Associação Brasileira de Otorrinolaringologia e Cirurgia Cérvico-Facial. Published by Elsevier Editora Ltda. All rights reserved.

  19. Criticality analysis for hazardous materials transportation; Classificacao da criticidade das rotas do transporte rodoviario de produtos perigosos da BRASKEM

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Katia; Brady, Mariana [Det Norske Veritas (DNV), Rio de Janeiro, RJ (Brazil); Diniz, Americo [BRASKEM S.A., Sao Paulo, SP (Brazil)

    2008-07-01

    The bad conditions of Brazilians roads drive the companies to be more exigent with the transportation of hazardous materials to avoid accidents or materials releases with actions to contain the releases to community and water sources. To minimize this situation, DNV and BRASKEM developed a methodology for risk analysis called Criticality Analysis for Hazardous Materials Transportation. The objective of this methodology is identifying the most critical points of routes to make actions to avoid accidents. (author)

  20. EPRI nuclear fuel-cycle accident risk assessment

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    The present results of the nuclear fuel-cycle accident risk assessment conducted by the Electric Power Research Institute show that the total risk contribution of the nuclear fuel cycle is only approx. 1% of the accident risk of the power plant; hence, with little error, the accident risk of nuclear electric power is essentially that of the power plant itself. The power-plant risk, assuming a very large usage of nuclear power by the year 2005 is only approx. 0.5% of the radiological risk of natural background. The smallness of the fuel-cycle risk relative to the power-plant risk may be attributed to the lack of internal energy to drive an accident and the small amount of dispersible material. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihood of errors and the estimated size of errors. The primary probabilistic estimation tool is fault-tree analysis, with the release source terms calculated using physicochemical processes. Doses and health effects are calculated with CRAC (Consequences of Reactor Accident Code). No evacuation or mitigation is considered; source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/t) and short cooling period (90 to 150 d); high-efficiency particulate air filter efficiencies are derived from experiments

  1. Final hazard classification and auditable safety analysis for the N basin segment

    International Nuclear Information System (INIS)

    Kloster, G.; Smith, R.I.; Larson, A.R.; Duncan, G.M.

    1996-12-01

    The purpose of this report is to provide the following: To serve as the auditable safety analysis (ASA) for the N Basin Segment, including both the quiescent state and planned intrusive activities. The ASA is developed through the realistic evaluation of potential hazards that envelope the threat to personnel. The ASA also includes the specification of the programmatic, baseline, and activity- specific controls that are necessary for the protection of workers. To determine and document the final hazard classification (FHC) for the N Basin Segment. The FHC is developed through the use of bounding accident analyses that envelope the potential exposures to personnel. The FHC also includes the specification of the special controls that are necessary to remain within the envelope of those accident analyses

  2. Storage of hazardous substances in bonded warehouses

    International Nuclear Information System (INIS)

    Villalobos Artavia, Beatriz

    2008-01-01

    A variety of special regulations exist in Costa Rica for registration and transport of hazardous substances; these set the requirements for entry into the country and the security of transport units. However, the regulations mentioned no specific rules for storing hazardous substances. Tax deposits have been the initial place where are stored the substances that enter the country.The creation of basic rules that would be regulating the storage of hazardous substances has taken place through the analysis of regulations and national and international laws governing hazardous substances. The regulatory domain that currently exists will be established with a field research in fiscal deposits in the metropolitan area. The storage and security measures that have been used by the personnel handling the substances will be identified to be putting the reality with that the hazardous substances have been handled in tax deposits. A rule base for the storage of hazardous substances in tax deposits can be made, protecting the safety of the environment in which are manipulated and avoiding a possible accident causing a mess around. The rule will have the characteristics of the storage warehouses hazardous substances, such as safety standards, labeling standards, infrastructure features, common storage and transitional measures that must possess and meet all bonded warehouses to store hazardous substances. (author) [es

  3. Language issues, an underestimated danger in major hazard control?

    Science.gov (United States)

    Lindhout, Paul; Ale, Ben J M

    2009-12-15

    Language issues are problems with communication via speech, signs, gestures or their written equivalents. They may result from poor reading and writing skills, a mix of foreign languages and other circumstances. Language issues are not picked up as a safety risk on the shop floor by current safety management systems. These safety risks need to be identified, acknowledged, quantified and prioritized in order to allow risk reducing measures to be taken. This study investigates the nature of language issues related danger in literature, by experiment and by a survey among the Seveso II companies in the Netherlands. Based on human error frequencies, and on the contents of accident investigation reports, the risks associated with language issues were ranked. Accident investigation method causal factor categories were found not to be sufficiently representative for the type and magnitude of these risks. Readability of safety related documents used by the companies was investigated and found to be poor in many cases. Interviews among regulators and a survey among Seveso II companies were used to identify the gap between the language issue related dangers found in literature and current best practices. This study demonstrates by means of triangulation with different investigative methods that language issue related risks are indeed underestimated. A recommended coarse of action in order to arrive at appropriate measures is presented.

  4. Language issues, an underestimated danger in major hazard control?

    Energy Technology Data Exchange (ETDEWEB)

    Lindhout, Paul, E-mail: plindhout@minszw.nl [Ministry of Social Affairs and Employment, AI-MHC, Anna van Hannoverstraat 4, P.O. Box 90801, 2509 LV The Hague (Netherlands); Ale, Ben J.M. [Delft University of Technology, TBM-Safety Science Group, Jaffalaan 5, 2628 BX Delft (Netherlands)

    2009-12-15

    Language issues are problems with communication via speech, signs, gestures or their written equivalents. They may result from poor reading and writing skills, a mix of foreign languages and other circumstances. Language issues are not picked up as a safety risk on the shop floor by current safety management systems. These safety risks need to be identified, acknowledged, quantified and prioritised in order to allow risk reducing measures to be taken. This study investigates the nature of language issues related danger in literature, by experiment and by a survey among the Seveso II companies in the Netherlands. Based on human error frequencies, and on the contents of accident investigation reports, the risks associated with language issues were ranked. Accident investigation method causal factor categories were found not to be sufficiently representative for the type and magnitude of these risks. Readability of safety related documents used by the companies was investigated and found to be poor in many cases. Interviews among regulators and a survey among Seveso II companies were used to identify the gap between the language issue related dangers found in literature and current best practices. This study demonstrates by means of triangulation with different investigative methods that language issue related risks are indeed underestimated. A recommended coarse of action in order to arrive at appropriate measures is presented.

  5. Language issues, an underestimated danger in major hazard control?

    International Nuclear Information System (INIS)

    Lindhout, Paul; Ale, Ben J.M.

    2009-01-01

    Language issues are problems with communication via speech, signs, gestures or their written equivalents. They may result from poor reading and writing skills, a mix of foreign languages and other circumstances. Language issues are not picked up as a safety risk on the shop floor by current safety management systems. These safety risks need to be identified, acknowledged, quantified and prioritised in order to allow risk reducing measures to be taken. This study investigates the nature of language issues related danger in literature, by experiment and by a survey among the Seveso II companies in the Netherlands. Based on human error frequencies, and on the contents of accident investigation reports, the risks associated with language issues were ranked. Accident investigation method causal factor categories were found not to be sufficiently representative for the type and magnitude of these risks. Readability of safety related documents used by the companies was investigated and found to be poor in many cases. Interviews among regulators and a survey among Seveso II companies were used to identify the gap between the language issue related dangers found in literature and current best practices. This study demonstrates by means of triangulation with different investigative methods that language issue related risks are indeed underestimated. A recommended coarse of action in order to arrive at appropriate measures is presented.

  6. MDEP Common Position CP-STC-02. Common Position Addressing Fukushima Daiichi Nuclear Power Accident

    International Nuclear Information System (INIS)

    2016-09-01

    Following the nuclear accident in Japan as a consequence of the earthquake and tsunami, the MDEP Members provide the following information, based on initial information available, to ensure adequate safety of new reactor design activities being undertaken pursuant to the MDEP program of work. Due to the extensive nature of the magnitude and duration of the Fukushima Daiichi NPP accident, it is important to consider lessons learnt at an early stage of the design. In this context, the extensive work done by the IAEA, the International Atomic Energy Agency, is also acknowledged. Vendors, licensees and applicants involved in New Design activities should examine the implications of the Fukushima Daiichi NPP accident and identify relevant issues to be taken into account to strengthen defense in depth. Those lessons learnt should include, but not be limited to, plans to assess the following: - Provisions taken in the design basis concerning flooding, earthquake, other extreme natural phenomena and combinations of external event hazards appropriate to each country, - The robustness of the plant to maintain its safety functions beyond the design basis hazards, - The capability of the plant to withstand extended loss of all electrical power supplies as well as prolonged loss of ultimate heat sink and other essential supplies, and - The capability of the plant to cope with such extreme situations, including provisions to manage severe accidents (such as combustible gas management). In assessing these areas, the effect of multiple units and nuclear fuel storages should be considered. The MDEP regulators will strive to harmonize approaches to incorporate lessons learnt in their ongoing national safety reviews of new reactors. Based on the design-specific common positions, this paper identifies the approaches to address potential safety improvements for several designs as related to lessons learned from the Fukushima Daiichi NPP accident or related issues. Designs being

  7. Analysis of the radiation accident in El Salvador

    International Nuclear Information System (INIS)

    Melara, N.E.

    1998-01-01

    On 5 February 1989 at 2 a.m. local time in a cobalt-60 industrial irradiation facility, a series of events started leading to one of the most serious radiation accidents in this type of installation. It took place in Soyapango, a city situated 5 km from San Salvador, the capital of the Republic of El Salvador. In this accident, three workers were involved in the first event and a further four in the second. When the accident took place, the activity level was approximately 0.66 PBq (18,000 Ci). The source became blocked when being lowered to its safe position, where upon the technician responsible for the irradiator entered the chamber in breach of the few inadequate safety procedures, accompanied by two colleagues from an adjacent department; the three workers suffered acute radiation exposure, with the result that one of them died six-and-a-half months later, the second had both his legs amputated at mid-thigh, while the third recovered completely. This article describes the irradiator, outlines the causes of the accident and analyses the economic and social repercussions, with the aim of helping teams responsible for radiation protection and safety in industrial irradiation facilities to identify potentially hazardous circumstances and avoid accidents. (author)

  8. [Occupational accidents in an oil refinery in Brazil].

    Science.gov (United States)

    Souza, Carlos Augusto Vaz de; Freitas, Carlos Machado de

    2002-10-01

    Work in oil refineries involves the risk of minor to major accidents. National data show the impact of accidents on this industry. A study was carried out to describe accident profile and evaluate the adequacy of accident reporting system. Data on all accidents reported in an oil refinery in the state of Rio de Janeiro for the year 1997 were organized and analyzed. The study population consisted of 153 injury cases, 83 hired and 69 contracted workers. The variables were: type of accident, operation mode and position of the worker injured. Among hired workers, minor accidents predominated (54.2%) and they occurred during regular operation activities (62.9%). Among contracted workers, there also predominated minor accidents (75.5%) in a higher percentage, but they occurred mainly during maintenance activities (96.8%). The study results showed that there is a predominance of accidents in lower hierarchy workers, and these accidents occur mainly during maintenance activities. There is a need to improve the company's accident reporting system and accident investigation procedures.

  9. Including uncertainty in hazard analysis through fuzzy measures

    International Nuclear Information System (INIS)

    Bott, T.F.; Eisenhawer, S.W.

    1997-12-01

    This paper presents a method for capturing the uncertainty expressed by an Hazard Analysis (HA) expert team when estimating the frequencies and consequences of accident sequences and provides a sound mathematical framework for propagating this uncertainty to the risk estimates for these accident sequences. The uncertainty is readily expressed as distributions that can visually aid the analyst in determining the extent and source of risk uncertainty in HA accident sequences. The results also can be expressed as single statistics of the distribution in a manner analogous to expressing a probabilistic distribution as a point-value statistic such as a mean or median. The study discussed here used data collected during the elicitation portion of an HA on a high-level waste transfer process to demonstrate the techniques for capturing uncertainty. These data came from observations of the uncertainty that HA team members expressed in assigning frequencies and consequences to accident sequences during an actual HA. This uncertainty was captured and manipulated using ideas from possibility theory. The result of this study is a practical method for displaying and assessing the uncertainty in the HA team estimates of the frequency and consequences for accident sequences. This uncertainty provides potentially valuable information about accident sequences that typically is lost in the HA process

  10. President's Commission and the normal accident

    International Nuclear Information System (INIS)

    Perrow, C.

    1982-01-01

    This chapter incorporates the major points of an analysis of the accident at Three Mile Island that I prepared in September 1979. In contrast to the findings of the President's Commission (1979), I did not view the accident as the result of operator error, an inept utility, or a negligent Nuclear Regulatory Commission but as a consequence of the complexity and interdependence that characterize the system itself. I argued that the accident was inevitable-that is, that it could not have been prevented, foreseen, or quickly terminated, because it was incomprehensible. It resembled other accidents in nuclear plants and in other high risk, complex and highly interdependent operator-machine systems; none of the accidents were caused by management or operator ineptness or by poor government regulation, though these characteristics existed and should have been expected. I maintained that the accident was normal, because in complex systems there are bound to be multiple faults that cannot be avoided by planning and that operators cannot immediately comprehend

  11. K Basins floor sludge retrieval system knockout pot basket fuel burn accident

    International Nuclear Information System (INIS)

    HUNT, J.W.

    1998-01-01

    The K Basins Sludge Retrieval System Preliminary Hazard Analysis Report (HNF-2676) identified and categorized a series of potential accidents associated with K Basins Sludge Retrieval System design and operation. The fuel burn accident was of concern with respect to the potential release of contamination resulting from a runaway chemical reaction of the uranium fuel in a knockout pot basket suspended in the air. The unmitigated radiological dose to an offsite receptor from this fuel burn accident is calculated to be much less than the offsite risk evaluation guidelines for anticipated events. However, because of potential radiation exposure to the facility worker, this accident is precluded with a safety significant lifting device that will prevent the monorail hoist from lifting the knockout pot basket out of the K Basin water pool

  12. Tsunami hazard

    International Nuclear Information System (INIS)

    2013-01-01

    Tohoku Earthquake Tsunami on 11 March, 2011 has led the Fukushima Daiichi nuclear power plant to a serious accident, which highlighted a variety of technical issues such as a very low design tsunami height and insufficient preparations in case a tsunami exceeding the design tsunami height. Lessons such as to take measures to be able to maintain the important safety features of the facility for tsunamis exceeding design height and to implement risk management utilizing Probabilistic Safety Assessment are shown. In order to implement the safety assessment on nuclear power plants across Japan accordingly to the back-fit rule, Nuclear Regulatory Commission will promulgate/execute the New Safety Design Criteria in July 2013. JNES has positioned the 'enhancement of probabilistic tsunami hazard assessment' as highest priority issue and implemented in order to support technically the Nuclear Regulatory Authority in formulating the new Safety Design Criteria. Findings of the research had reflected in the 'Technical Review Guidelines for Assessing Design Tsunami Height based on tsunami hazards'. (author)

  13. Accidents - Chernobyl accident

    International Nuclear Information System (INIS)

    2004-01-01

    This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)

  14. Three Mile Island accident

    International Nuclear Information System (INIS)

    Barre, B.; Olivier, E.; Roux, J.P.; Pelle, P.

    2010-01-01

    Deluded by equivocal instrumentation signals, operators at TMI-2 (Three Mile Island - unit 2) misunderstood what was going on in the reactor and for 2 hours were taking inadequate decisions that turned a reactor incident into a major nuclear event that led to the melting of about one third of the core. The TMI accident had worldwide impacts in the domain of nuclear safety. The main consequences in France were: 1) the introduction of the major accident approach and the reinforcement of crisis management; 2) the improvement of the reactor design, particularly that of the pressurizer valves; 3) the implementation of safety probabilistic studies; 4) a better taking into account of the feedback experience in reactor operations; and 5) a better taking into account of the humane factor in reactor safety. (A.C.)

  15. Chemical phenomena under severe accident conditions

    International Nuclear Information System (INIS)

    Powers, D.A.

    1988-01-01

    A severe nuclear reactor accident is expected to involve a vast number of chemical processes. The chemical processes of major safety significance begin with the production of hydrogen during steam oxidation of fuel cladding. Physico-chemical changes in the fuel and the vaporization of radionuclides during reactor accidents have captured much of the attention of the safety community in recent years. Protracted chemical interactions of core debris with structural concrete mark the conclusion of dynamic events in a severe accident. An overview of the current understanding of chemical processes in severe reactor accident is provided in this paper. It is shown that most of this understanding has come from application of findings from other fields though a few areas have in the past been subject to in-depth study of a fundamental nature. Challenges in the study of severe accident chemistry are delineated

  16. Pattern of injuries from motorcycle accidents in Abia State, Nigeria ...

    African Journals Online (AJOL)

    Background: Motorcycle accidents are very common and cause major injuries. The Abia State government banned commercial motorcyclists from operating in the major cities of the state in July, 2009. Objectives: To determine the influence of this ban on the cause and pattern of injuries due to road traffic accidents. Design: ...

  17. THE METHOD OF ASSESSING ROCK BURSTING HAZARD IN MINING

    Directory of Open Access Journals (Sweden)

    Anna MANOWSKA

    2015-04-01

    Full Text Available The article discusses a concept of forecasting accident risk during longwall extraction in crump-risk conditions. In Polish mines rock burst hazard can be described as high compared to other mines around the world. It's related to increase of depth of longwall field operation, preparation works, including drilling of mine face pavements which leads to systematic deterioration of geological and mining conditions. Depletion of coal is also the reason why mines operate in high mining tremor risk conditions. Mines more and more often operate in decks, where there is large number of edges and remains of older decks. Rocks bursts still remain one of the most dangerous natural hazards and therefore are fundamental prob-lem and have the greatest impact on safety in mining industry. The proposed method for forecasting accidents and loss-es in people and goods can contribute to improvement of work organization methods and mine safety management system.

  18. The role of quantitative uncertainty in the safety analysis of flammable gas accidents in Hanford waste tanks

    International Nuclear Information System (INIS)

    Bratzel, D.R.

    1998-01-01

    Following a 1990 investigation into flammable gas generation, retention, and release mechanisms within the Hanford Site high-level waste tanks, personnel concluded that the existing Authorization Basis documentation did not adequately evaluate flammable gas hazards. The US Department of Energy Headquarters subsequently declared the flammable gas hazard as an unresolved safety issue. Although work scope has been focused on resolution of the issue, it has yet to be resolved due to considerable uncertainty regarding essential technical parameters and associated risk. Resolution of the Flammable Gas Safety Issue will include the identification of a set of controls for the Authorization Basis for the tanks which will require a safety analysis of flammable gas accidents. A traditional nuclear facility safety analysis is based primarily on the analysis of a set of bounding accidents to represent the risks of the possible accidents and hazardous conditions at a facility. While this approach may provide some indication of the bounding consequences of accidents for facilities, it does not provide a satisfactory basis for identification of facility risk or safety controls when there is considerable uncertainty associated with accident phenomena and/or data as is the case with potential flammable gas accidents at the Hanford Site. This is due to the difficulties in identifying the bounding case and reaching consensus among safety analysts, facility operations and engineering, and the regulator on the implications of the safety analysis results. In addition, the bounding cases are frequently based on simplifying assumptions that make the analysis results insensitive to variations among facilities or the impact of alternative safety control strategies. The existing safety analysis of flammable gas accidents for the Tank Waste Remediation system (TWRS) at the Hanford Site has these difficulties. However, Hanford Site personnel are developing a refined safety analysis approach

  19. A route-specific system for risk assessment of radioactive materials transportation accidents

    International Nuclear Information System (INIS)

    Moore, J.E.; Sandquist, G.M.; Slaughter, D.M.

    1995-01-01

    A low-cost, powerful geographic information system (GIS) that operates on a personal computer was integrated into a software system to provide route specific assessment of the risks associated with the atmospheric release of radioactive and hazardous materials in transportation accidents. The highway transportation risk assessment (HITRA) software system described here combines a commercially available GIS (TransCAD) with appropriate models and data files for route- and accident-specific factors, such as meteorology, dispersion, demography, and health effects to permit detailed analysis of transportation risk assessment. The HITRA system allows a user to interactively select a highway or railroad route from a GIS database of major US transportation routes. A route-specific risk assessment is then performed to estimate downwind release concentrations and the resulting potential health effects imposed on the exposed population under local environmental and temporal conditions. The integration of GIS technology with current risk assessment methodology permits detailed analysis coupled with enhanced user interaction. Furthermore, HITRA provides flexibility and documentation for route planning, updating and improving the databases required for evaluating specific transportation routes, changing meteorological and environmental conditions, and local demographics

  20. MDEP Common Position CP-EPRWG-04. Common position on EPR containment heat removal system in accident conditions

    International Nuclear Information System (INIS)

    2015-01-01

    The importance of the integrity of the containment as a fundamental barrier to protect the people and environment against the effects of a nuclear accident is well established. In this regard, an essential objective is that the necessity for off-site counter-measures to reduce radiological consequences be limited or even eliminated. The design should provide engineering means to address those sequences which would otherwise lead to large or early releases, even in case of severe external hazards. The plant shall be designed so that it can be brought into a controlled and stable state and the containment function can be maintained, under accident conditions in which there is a significant amount of radioactive material in the containment, i.e. resulting from severe degradation of the reactor core. It is expected that due consideration to these requirements is to be given while tailoring long term loss of electrical power mitigation strategies. In order to reliably maintain the containment barrier, the regulators believe that: - safety features specifically designed for fulfilling safety functions required in core melt accidents shall be independent to the extent reasonably practicable from the Systems, Structures and Components (SSC) of the other levels of defense; - safety features specifically designed for fulfilling safety functions required in core melt accidents shall be safety classified and adequately qualified for the core melt accident environmental conditions for the time frame for which they are required to operate. In the light of the Fukushima Daiichi accident, the regulators believe that those safety features shall be designed with an adequate margin as compared to the levels of natural hazards considered for the site hazard evaluation; - the systems and components necessary for ensuring the containment function in a core melt accident shall have reliability commensurate with the function that they are required to fulfil. This may require redundancy of

  1. Consequences of severe nuclear accidents in Europe

    Science.gov (United States)

    Seibert, Petra; Arnold, Delia; Mraz, Gabriele; Arnold, Nikolaus; Gufler, Klaus; Kromp-Kolb, Helga; Kromp, Wolfgang; Sutter, Philipp

    2013-04-01

    A first part of the presentation is devoted to the consequences of the severe accident in the 1986 Chernobyl NPP. It lead to a substantial radioactive contaminated of large parts of Europe and thus raised the awareness for off-site nuclear accident consequences. Spatial patterns of the (transient) contamination of the air and (persistent) contamination of the ground were studied by both measurements and model simulations. For a variety of reasons, ground contamination measurements have variability at a range of spatial scales. Results will be reviewed and discussed. Model simulations, including inverse modelling, have shown that the standard source term as defined in the ATMES study (1990) needs to be updated. Sensitive measurements of airborne activities still reveal the presence of low levels of airborne radiocaesium over the northern hemisphere which stems from resuspension. Over time scales of months and years, the distribution of radionuclides in the Earth system is constantly changing, for example relocated within plants, between plants and soil, in the soil, and into water bodies. Motivated by the permanent risk of transboundary impacts from potential major nuclear accidents, the multidisciplinary project flexRISK (see http://flexRISK.boku.ac.at) has been carried out from 2009 to 2012 in Austria to quantify such risks and hazards. An overview of methods and results of flexRISK is given as a second part of the presentation. For each of the 228 NPPs, severe accidents were identified together with relevant inventories, release fractions, and release frequencies. Then, Europe-wide dispersion and dose calculations were performed for 2788 cases, using the Lagrangian particle model FLEXPART. Maps of single-case results as well as various aggregated risk parameters were produced. It was found that substantial consequences (intervention measures) are possible for distances up to 500-1000 km, and occur more frequently for a distance range up to 100-300 km, which is in

  2. Bayes classifiers for imbalanced traffic accidents datasets.

    Science.gov (United States)

    Mujalli, Randa Oqab; López, Griselda; Garach, Laura

    2016-03-01

    Traffic accidents data sets are usually imbalanced, where the number of instances classified under the killed or severe injuries class (minority) is much lower than those classified under the slight injuries class (majority). This, however, supposes a challenging problem for classification algorithms and may cause obtaining a model that well cover the slight injuries instances whereas the killed or severe injuries instances are misclassified frequently. Based on traffic accidents data collected on urban and suburban roads in Jordan for three years (2009-2011); three different data balancing techniques were used: under-sampling which removes some instances of the majority class, oversampling which creates new instances of the minority class and a mix technique that combines both. In addition, different Bayes classifiers were compared for the different imbalanced and balanced data sets: Averaged One-Dependence Estimators, Weightily Average One-Dependence Estimators, and Bayesian networks in order to identify factors that affect the severity of an accident. The results indicated that using the balanced data sets, especially those created using oversampling techniques, with Bayesian networks improved classifying a traffic accident according to its severity and reduced the misclassification of killed and severe injuries instances. On the other hand, the following variables were found to contribute to the occurrence of a killed causality or a severe injury in a traffic accident: number of vehicles involved, accident pattern, number of directions, accident type, lighting, surface condition, and speed limit. This work, to the knowledge of the authors, is the first that aims at analyzing historical data records for traffic accidents occurring in Jordan and the first to apply balancing techniques to analyze injury severity of traffic accidents. Copyright © 2015 Elsevier Ltd. All rights reserved.

  3. The transport of hazardous materials

    International Nuclear Information System (INIS)

    Goemmel, F.

    1987-01-01

    The rapid development of all kinds of transports has been leading to a continuously increasing number of accidents involving the release and escape of hazardous materials. The risks involved for men and the environment have to be realized and reduced to a minimum. Efforts in this field have meanwhile been accumulating an enormous quantity of rules, recommendations and regulations. They comprise, among others, both national and international rail transport, maritime transport, inland shipping, air and road transport regulations adding up to a total of about 5000 pages. The publication discusses the necessity and justification of the existing quantity of regulations, it deals with their possible simplification and modified user-oriented arrangement as well as with a possible international harmonization of regulations. Apart from giving a general survey of the transport of hazardous materials the author reviews the intensive efforts which are going into the safety of the transport of hazardous materials and points out technical and legal problems which have remained unsolved so far. The publication essentially contributes to clearing up the background, perspectives and prospects of the complex regulations controlling the transport of hazardous materials. (orig./HP) [de

  4. Investigation of the management of the wastes from plant accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    The accident in Fukushima Daiichi Nuclear Power Plant discharged large amount of radio-nuclides and contaminated wide areas in and out of the site. The decontamination, storage, treatment and disposal of generated wastes are now under planning. Though regulations for the radioactive wastes arisen from normal operation and decommissioning of nuclear facilities have been prepared, it is necessary to make amendment of those regulations to deal with wastes from the severe accident which may have much different features on nuclides contents, or possible accompanying hazardous chemical materials. Characteristics of wastes from accidents in foreign nuclear installations, and the treatment and the disposal of those wastes were surveyed by literature and radionuclide migration from the assumed temporally storage yards of the disaster debris was analyzed for consideration of future regulation. (author)

  5. Radiofrequency Identification by using Drones in Railway Accidents and Disaster Situations

    Directory of Open Access Journals (Sweden)

    Géza Károly Kiss Leizer

    2017-06-01

    Full Text Available Today, railway operation procedures include the transportation of large amount of hazardous substances. Our research has been motivated by the desire to find concrete and urgent solutions to the safety issues of handling waste generated manly in case of accidents and disaster situations during the transportation of hazardous substances In order to ensure safety in the transportation of dangerous goods, and to facilitate the fast and efficient waste handling of hazardous substances released into the environment during unexpected events, we have elaborated a new method, in which we suggest the radiofrequency identification of dangerous consignments in case of disaster situations by the use of drones.

  6. Highlights from the literature on accident causation and system safety: Review of major ideas, recent contributions, and challenges

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, J.H., E-mail: jsaleh@gatech.ed [School of Aerospace Engineering, Georgia Institute of Technology (United States); Marais, K.B. [School of Aeronautics and Astronautics, Purdue University (United States); Bakolas, E.; Cowlagi, R.V. [School of Aerospace Engineering, Georgia Institute of Technology (United States)

    2010-11-15

    This work constitutes a short guide to the extensive but fragmented literature on accident causation and system safety. After briefly motivating the interest in accident causation and discussing the notion of a safety value chain, we delve into our multi-disciplinary review with discussions of Man Made Disasters, Normal Accident, and the High Reliability Organizations (HRO) paradigm. The HRO literature intersects an extensive literature on safety culture, a subject we then briefly touch upon. Following this discussion, we note that while these social and organizational contributions have significantly enriched our understanding of accident causation and system safety, they have important deficiencies and are lacking in their understanding of technical and design drivers of system safety and accident causation. These missing ingredients, we argue, were provided in part by the development of Probabilistic Risk Assessment (PRA). The idea of anticipating possible accident scenarios, based on the system design and configuration, as well as its technical and operational characteristics, constitutes an important contribution of PRA, which builds on and extends earlier contributions made by the development of Fault Tree and Event Tree Analysis. We follow the discussion of PRA with an exposition of the concept of safety barriers and the principle of defense-in-depth, both of which emphasize the functions and 'safety elements [that should be] deliberately inserted' along potential accident trajectories to prevent, contain, or mitigate accidents. Finally, we discuss two ideas that are emerging as foundational in the literature on system safety and accident causation, namely that system safety is a 'control problem', and that it requires a 'system theoretic' approach to be dealt with. We clarify these characterizations and indicate research opportunities to be pursued along these directions. We conclude this work with two general recommendations

  7. Highlights from the literature on accident causation and system safety: Review of major ideas, recent contributions, and challenges

    International Nuclear Information System (INIS)

    Saleh, J.H.; Marais, K.B.; Bakolas, E.; Cowlagi, R.V.

    2010-01-01

    This work constitutes a short guide to the extensive but fragmented literature on accident causation and system safety. After briefly motivating the interest in accident causation and discussing the notion of a safety value chain, we delve into our multi-disciplinary review with discussions of Man Made Disasters, Normal Accident, and the High Reliability Organizations (HRO) paradigm. The HRO literature intersects an extensive literature on safety culture, a subject we then briefly touch upon. Following this discussion, we note that while these social and organizational contributions have significantly enriched our understanding of accident causation and system safety, they have important deficiencies and are lacking in their understanding of technical and design drivers of system safety and accident causation. These missing ingredients, we argue, were provided in part by the development of Probabilistic Risk Assessment (PRA). The idea of anticipating possible accident scenarios, based on the system design and configuration, as well as its technical and operational characteristics, constitutes an important contribution of PRA, which builds on and extends earlier contributions made by the development of Fault Tree and Event Tree Analysis. We follow the discussion of PRA with an exposition of the concept of safety barriers and the principle of defense-in-depth, both of which emphasize the functions and 'safety elements [that should be] deliberately inserted' along potential accident trajectories to prevent, contain, or mitigate accidents. Finally, we discuss two ideas that are emerging as foundational in the literature on system safety and accident causation, namely that system safety is a 'control problem', and that it requires a 'system theoretic' approach to be dealt with. We clarify these characterizations and indicate research opportunities to be pursued along these directions. We conclude this work with two general recommendations: (1) that more fundamental

  8. Accidents and emergency conditions: Tasks of the radiation protection expert

    International Nuclear Information System (INIS)

    Hacke, J.

    1985-01-01

    This paper reviews and explains the tasks of the radiation protection expert at a given site in the event of accidents or emergencies involving a radiation hazard to the personnel. The various measures recommended discriminate between the main two types of hazards, namely external radiation or internal radiation. The paper discusses the first-aid and emergency measures recommended in various publications (BG, 1982; ICRP, 1980; MO, 1972; ME, 1980) and also cites recommendations contained therein, referring to preventive means and measures and to communications to the press and the general public. (DG) [de

  9. Hazard Identification and Risk Assessment of Health and Safety Approach JSA (Job Safety Analysis) in Plantation Company

    Science.gov (United States)

    Sugarindra, Muchamad; Ragil Suryoputro, Muhammad; Tiya Novitasari, Adi

    2017-06-01

    Plantation company needed to identify hazard and perform risk assessment as an Identification of Hazard and Risk Assessment Crime and Safety which was approached by using JSA (Job Safety Analysis). The identification was aimed to identify the potential hazards that might be the risk of workplace accidents so that preventive action could be taken to minimize the accidents. The data was collected by direct observation to the workers concerned and the results were recorded on a Job Safety Analysis form. The data were as forklift operator, macerator worker, worker’s creeper, shredder worker, workers’ workshop, mechanical line worker, trolley cleaning workers and workers’ crepe decline. The result showed that shredder worker value was 30 and had the working level with extreme risk with the risk value range was above 20. So to minimize the accidents could provide Personal Protective Equipment (PPE) which were appropriate, information about health and safety, the company should have watched the activities of workers, and rewards for the workers who obey the rules that applied in the plantation.

  10. Hazard screening application guide. Safety Analysis Report Update Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-06-01

    The basic purpose of hazard screening is to group precesses, facilities, and proposed modifications according to the magnitude of their hazards so as to determine the need for and extent of follow on safety analysis. A hazard is defined as a material, energy source, or operation that has the potential to cause injury or illness in human beings. The purpose of this document is to give guidance and provide standard methods for performing hazard screening. Hazard screening is applied to new and existing facilities and processes as well as to proposed modifications to existing facilities and processes. The hazard screening process evaluates an identified hazards in terms of the effects on people, both on-site and off-site. The process uses bounding analyses with no credit given for mitigation of an accident with the exception of certain containers meeting DOT specifications. The process is restricted to human safety issues only. Environmental effects are addressed by the environmental program. Interfaces with environmental organizations will be established in order to share information.

  11. Nursering assistance to the radiological accident patients in Goias-Brazil

    International Nuclear Information System (INIS)

    Graciotti, M.E.

    1989-01-01

    A report of a personal experience, during two months of nursering care to the radiological accident victims, due to the disruption of a caesium-137 source, is presented. The biological radiation effects, the radiation hazards due to the doses received and the Kind of exposure, are studied. (M.A.C.) [pt

  12. 340 Waste handling Facility Hazard Categorization and Safety Analysis

    International Nuclear Information System (INIS)

    Rodovsky, T.J.

    2010-01-01

    The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3. The final hazard categorization for the deactivated 340 Waste Handling Facility (340 Facility) is presented in this document. This hazard categorization was prepared in accordance with DOE-STD-1 027-92, Change Notice 1, Hazard Categorization and Accident Analysis Techniques for Compliance with Doe Order 5480.23, Nuclear Safety Analysis Reports. The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category (HC) 3. Routine nuclear waste receiving, storage, handling, and shipping operations at the 340 Facility have been deactivated, however, the facility contains a small amount of radioactive liquid and/or dry saltcake in two underground vault tanks. A seismic event and hydrogen deflagration were selected as bounding accidents. The generation of hydrogen in the vault tanks without active ventilation was determined to achieve a steady state volume of 0.33%, which is significantly less than the lower flammability limit of 4%. Therefore, a hydrogen deflagration is not possible in these tanks. The unmitigated release from a seismic event was used to categorize the facility consistent with the process defined in Nuclear Safety Technical Position (NSTP) 2002-2. The final sum-of-fractions calculation concluded that the facility is less than HC 3. The analysis did not identify any required engineered controls or design features. The Administrative Controls that were derived from the analysis are: (1) radiological inventory control, (2) facility change control, and (3) Safety Management Programs (SMPs). The facility configuration and radiological inventory shall be controlled to ensure that the assumptions in the analysis remain valid. The facility commitment to SMPs protects the integrity of the facility and environment by ensuring training, emergency response, and radiation protection. The full scale

  13. Applying of Reliability Techniques and Expert Systems in Management of Radioactive Accidents

    International Nuclear Information System (INIS)

    Aldaihan, S.; Alhbaib, A.; Alrushudi, S.; Karazaitri, C.

    1998-01-01

    Accidents including radioactive exposure have variety of nature and size. This makes such accidents complex situations to be handled by radiation protection agencies or any responsible authority. The situations becomes worse with introducing advanced technology with high complexity that provide operator huge information about system working on. This paper discusses the application of reliability techniques in radioactive risk management. Event tree technique from nuclear field is described as well as two other techniques from nonnuclear fields, Hazard and Operability and Quality Function Deployment. The objective is to show the importance and the applicability of these techniques in radiation risk management. Finally, Expert Systems in the field of accidents management are explored and classified upon their applications

  14. Potential behavior of depleted uranium penetrators under shipping and bulk storage accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; Parkhurst, M.A.; Scherpelz, R.I.

    1985-03-01

    An investigation of the potential hazard from airborne releases of depleted uranium (DU) from the Army's M829 munitions was conducted at the Pacific Northwest Laboratory. The study included: (1) assessing the characteristics of DU oxide from an April 1983 burn test, (2) postulating conditions of specific accident situations, and (3) reviewing laboratory and theoretical studies of oxidation and airborne transport of DU from accidents. Results of the experimental measurements of the DU oxides were combined with atmospheric transport models and lung and kidney exposure data to help establish reasonable exclusion boundaries to protect personnel and the public at an accident site. 121 references, 44 figures, 30 tables.

  15. Ammonium nitrate explosion hazards

    Directory of Open Access Journals (Sweden)

    Negovanović Milanka

    2015-01-01

    Full Text Available Ammonium nitrate (AN primarily is used as a fertilizer but it is also very important compound in the production of industrial explosives. The application of ammonium nitrate in the production of industrial explosives was related with the early era of Nobel dynamite and widely increased with the appearance of blasting agents such as ANFO and Slurry, in the middle of the last Century. Throughout the world millions of tons of ammonium nitrate are produced annually and handled without incident. Although ammonium nitrate generally is used safely, accidental explosions involving AN have high impact resulting in loss of lives and destruction of property. The paper presents the basic properties of ammonium nitrate as well as hazards in handling of ammonium nitrate in order to prevent accidents. Several accidents with explosions of ammonium nitrate resulted in catastrophic consequences are listed in the paper as examples of non-compliance with prescribed procedures.

  16. The Three Mile Island accident

    International Nuclear Information System (INIS)

    Zebroski, E.L.

    1980-01-01

    It is important that the causes of this accident (and other, similar accidents but with less dramatic consequences) are completely understood and that the role of every contributing factor is exactly determined in order to discuss modifications and to judge their relative importance and schedule in an objective way. If the role of the various factors contributing to an accident is not fully understood, there will always be a 'mythology' of prejudiced and highly simplified assumptions. The experience of failure analysis shows that the causes first assumed are hardly ever the right ones, and that in some major and complex cases even the second or third generation of assumed causes is wrong. (orig.) [de

  17. Symposium on the transportation of hazardous goods

    Energy Technology Data Exchange (ETDEWEB)

    Mackay, D; Canniff, W; Coleman, R J; Ellison, T D; Estrin, D

    1980-06-11

    A symposium on the transportation of hazardous goods sponsored by the University of Toronto, the Canadian Society for Chemical Engineering, and Oyez Ltd. (Toronto May 1980), in view of a 11/10/79 explosion at Mississauga, Ont., following derailment of a Canadian Pacific Railways train carrying chlorine gas, covers comments by D. MacKay (Univ. Toronto), on the importance of quantifying the probability of an accident in transporting such hazardous materials as LPG's, chlorine, and corrosive acids, and of formulating contingency plans to reduce the probability or mitigate the effects; by W. Canniff of the Canadian Chemical Producers Association, on that group's Transportation Emergency Assistance Plan, which relies on the shipper of the chemical involved in an accident to provide advice and assistance; by R.J. Coleman (San Clemente, Calif., Fire Dep.), on coordination of efforts between firefighting and other emergency-handling groups to avoid confusion; by T.D. Ellison (Transp. Can.), on proposed Canadian legislation on the transport of dangerous goods, which would adopt, among others, a product classification system now used for international sea transport and a new system of labeling packages; and by D. Estrin, on the limitations of this proposed legislation.

  18. Radiological accident 'The Citadel' medical aspects

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan; Fernandez, Isis M.; Lopez, Gladys; Garcia, Omar; Lamadrid, Ana I.; Ramos, Enma O.; Villa, Rosario; Giron, Carmen M.; Escobar, Myrian; Zerpa, Miguel; Romero, Argenis H.; Medina, Julio; Laurenti, Zenia; Oliva, Maria T.; Sierra, Nitza; Lorenzo, Alexis

    2008-01-01

    The work exposes the medical actions carried out in the mitigation of the consequences of the accident and its main results. In a facility of storage of radioactive waste in Caracas, Venezuela, it was happened a radiological accident. This event caused radioactive contamination of the environment, as well as the irradiation and radioactive contamination of at least 10 people involved in the fact, in its majority children. Cuban institutions participated in response to the accident. Among the decisions adopted by the team of combined work Cuban-Venezuelan, we find the one of transferring affected people to Cuba, for their dosimetric and medical evaluation. Being designed a work strategy to develop the investigations to people affected by the radiological accident, in correspondence with the circumstances, magnitude and consequences of the accident. The obtained main results are: 100% presented affectations in its health, not associate directly to the accident, although the accident influenced in its psychological state. In 3 of studied people they were detected radioactive contamination with Cesium -137 with dose among 2.01 X 10-4 Sv up to 2.78 X 10-4 Sv. This accident demonstrated the necessity to have technical capacities to face these events and the importance of the international solidarity. (author)

  19. A First Step toward the Understanding of Implicit Learning of Hazard Anticipation in Inexperienced Road Users Through a Moped-Riding Simulator

    Directory of Open Access Journals (Sweden)

    Mariaelena Tagliabue

    2017-05-01

    Full Text Available Hazard perception is considered one of the most important abilities in road safety. Several efforts have been devoted to investigating how it improves with experience and can be trained. Recently, research has focused on the implicit aspects of hazard detection, reaction, and anticipation. In the present study, we attempted to understand how the ability to anticipate hazards develops during training with a moped-riding simulator: the Honda Riding Trainer (HRT. Several studies have already validated the HRT as a tool to enhance adolescents’ hazard perception and riding abilities. In the present study, as an index of hazard anticipation, we used skin conductance response (SCR, which has been demonstrated to be linked to affective/implicit appraisal of risk. We administered to a group of inexperienced road users five road courses two times a week apart. In each course, participants had to deal with eight hazard scenes (except one course that included only seven hazard scenes. Participants had to ride along the HRT courses, facing the potentially hazardous situations, following traffic rules, and trying to avoid accidents. During the task, we measured SCR and monitored driving performance. The main results show that learning to ride the simulator leads to both a reduction in the number of accidents and anticipation of the somatic response related to hazard detection, as proven by the reduction of SCR onset recorded in the second session. The finding that the SCR signaling the impending hazard appears earlier when the already encountered hazard situations are faced anew suggests that training with the simulator acts on the somatic activation associated with the experience of risky situations, improving its effectiveness in detecting hazards in advance so as to avoid accidents. This represents the starting point for future investigations into the process of generalization of learning acquired in new virtual situations and in real-road situations.

  20. A major technological accident: the dispersion of a radioactive cesium - 137 pellet in Goiania, Brazil (1987)

    International Nuclear Information System (INIS)

    Guertzon, C.

    1994-01-01

    This study concerns the accidental dispersion of cesium 137 chloride via an abandoned radiotherapy device in Brazil, in september 1987. Since the accident occurred recently in a confined area and concerned a single radiochemical agent, it was possible to delimit the study parameters in each discipline: post-accident management, physics, medicine, environment, law, psychology, socio-economics and communication. Costs are difficult to evaluate but obviously very important. It is difficult to analyze all consequences. No official has been accused, there were no sentence. The results demonstrate the critical importance of the human factor in technological accidents. (A.L.B.)

  1. The survey of occupational accidents in Yazd gas agency (2013

    Directory of Open Access Journals (Sweden)

    Amir Hossein Khoshakhlagh

    2016-10-01

    Full Text Available Background: Existence of coordinated and professional safety system to prevent occurrence of accidents and potential hazards seem to be essential in installing networks of gas distribution projects. Objective: To survey work-related accidents and safety performance indices in project implementation unit of Yazd gas agency. Methods: This analytical study was conducted on 197 of workforce in Yazd gas agency in 2013 that were selected by census and they were male. Demographic and accident information were gathered using a self-made questionnaire and face- to- face interview, and required information obtained from dossier to determine the safety performance indicators. Safety performance indicators were calculated in separately of 13 types occupations in project implementation unit of gas agency and data were analyzed using T-test. Findings: The highest accident frequency and severity rate were related to digging occupation and then metal line welding. Consequences of accidents were cuts (%56.7 and soreness (%14.9. The causes of accidents were related to uselessness of personal protective equipment (%25.2 and lack of precision in the task (%19.3. The highest rate of accident was observed among the age group 20-29 years with work experience of 4-6 years. Conclusion: According to the findings of this study and the risk of gas processes, it seems to be necessary the implementation of integrated management systems and training of workers about safety rules to improve the safety culture and prevent accidents.

  2. A radioactive waste transportation package monitoring system for normal transport and accident emergency response conditions

    International Nuclear Information System (INIS)

    Brown, G.S.; Cashwell, J.W.; Apple, M.L.

    1991-01-01

    Shipments of radioactive material (RAM) constitute but a small fraction of the total hazardous materials shipped in the United States each year. Public perception, however, of the potential consequences of a release from a transportation package containing RAM has resulted in significant regulation of transport operations, both to ensure the integrity of a package in accident conditions and to place operational constraints on the shipper. Much of this attention has focused on shipments of spent nuclear fuel and high level wastes which, although comprising a very small number of total shipments, constitute a majority of the total curies transported on an annual basis. This report discusses the shipment of these highly radioactive materials

  3. Monitoring severe accidents using AI techniques

    Energy Technology Data Exchange (ETDEWEB)

    No, Young Gyu; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Ju Hyun; Na, Man Gyun [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of); Lim, Dong Hyuk [Korea Institute of Nuclear Nonproliferation and Control, Daejon (Korea, Republic of)

    2012-05-15

    After the Fukushima nuclear accident in 2011, there has been increasing concern regarding severe accidents in nuclear facilities. Severe accident scenarios are difficult for operators to monitor and identify. Therefore, accurate prediction of a severe accident is important in order to manage it appropriately in the unfavorable conditions. In this study, artificial intelligence (AI) techniques, such as support vector classification (SVC), probabilistic neural network (PNN), group method of data handling (GMDH), and fuzzy neural network (FNN), were used to monitor the major transient scenarios of a severe accident caused by three different initiating events, the hot-leg loss of coolant accident (LOCA), the cold-leg LOCA, and the steam generator tube rupture in pressurized water reactors (PWRs). The SVC and PNN models were used for the event classification. The GMDH and FNN models were employed to accurately predict the important timing representing severe accident scenarios. In addition, in order to verify the proposed algorithm, data from a number of numerical simulations were required in order to train the AI techniques due to the shortage of real LOCA data. The data was acquired by performing simulations using the MAAP4 code. The prediction accuracy of the three types of initiating events was sufficiently high to predict severe accident scenarios. Therefore, the AI techniques can be applied successfully in the identification and monitoring of severe accident scenarios in real PWRs.

  4. Monitoring severe accidents using AI techniques

    International Nuclear Information System (INIS)

    No, Young Gyu; Ahn, Kwang Il; Kim, Ju Hyun; Na, Man Gyun; Lim, Dong Hyuk

    2012-01-01

    After the Fukushima nuclear accident in 2011, there has been increasing concern regarding severe accidents in nuclear facilities. Severe accident scenarios are difficult for operators to monitor and identify. Therefore, accurate prediction of a severe accident is important in order to manage it appropriately in the unfavorable conditions. In this study, artificial intelligence (AI) techniques, such as support vector classification (SVC), probabilistic neural network (PNN), group method of data handling (GMDH), and fuzzy neural network (FNN), were used to monitor the major transient scenarios of a severe accident caused by three different initiating events, the hot-leg loss of coolant accident (LOCA), the cold-leg LOCA, and the steam generator tube rupture in pressurized water reactors (PWRs). The SVC and PNN models were used for the event classification. The GMDH and FNN models were employed to accurately predict the important timing representing severe accident scenarios. In addition, in order to verify the proposed algorithm, data from a number of numerical simulations were required in order to train the AI techniques due to the shortage of real LOCA data. The data was acquired by performing simulations using the MAAP4 code. The prediction accuracy of the three types of initiating events was sufficiently high to predict severe accident scenarios. Therefore, the AI techniques can be applied successfully in the identification and monitoring of severe accident scenarios in real PWRs.

  5. Investigate the causes of transport and tramming accidents on coal mines.

    CSIR Research Space (South Africa)

    Rushworth, AM

    1999-03-01

    Full Text Available Transport and tramming accidents on coal mines in South Africa are a major component in the overall pattern of colliery accidents. Furthermore, there is now a widespread acceptance that human error is a common cause of failure in accident patterns...

  6. Preliminary hazards analysis -- vitrification process

    International Nuclear Information System (INIS)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P.

    1994-06-01

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility's construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment

  7. Preliminary hazards analysis -- vitrification process

    Energy Technology Data Exchange (ETDEWEB)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P. [Science Applications International Corp., Pleasanton, CA (United States)

    1994-06-01

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.

  8. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    International Nuclear Information System (INIS)

    SCHULTZ, M.V.

    2000-01-01

    As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to

  9. Economic burden of motorcycle accidents in Northern Ghana ...

    African Journals Online (AJOL)

    Background: Motorcycles are the most popular means of transportation in northern Ghana, and their accidents are major causes of out-patient attendance and admis-sions in the Bolgatanga Municipality. Objective: This paper estimates the economic burden of motorcycle accidents in the Bolgatanga Municipality in Northern ...

  10. Conduct of Occupational Health During Major Disasters: A Comparison of Literature on Occupational Health Issues in the World Trade Center Terrorist Attack and the Fukushima Nuclear Power Plant Accident.

    Science.gov (United States)

    Toyoda, Hiroyuki; Mori, Koji

    2017-01-01

    Workers who respond to large-scale disasters can be exposed to health hazards that do not exist in routine work. It is assumed that learning from past cases is effective for preparing for and responding to such problems, but published information is still insufficient. Accordingly, we conducted a literature review about the health issues and occupational health activities at the World Trade Center (WTC) terrorist attack and at the Fukushima Nuclear Power Plant accident to investigate how occupational health activities during disasters should be conducted. Seven studies about the WTC attack were extracted and categorized into the following topics: "in relation to emergency systems including occupational health management"; "in relation to improvement and prevention of health effects and occupational hygiene"; and "in relation to care systems aimed at mitigating health effects." Studies about the Fukushima Nuclear Power Plant accident have been used in a previous review. We conclude that, to prevent health effects in workers who respond to large-scale disasters, it is necessary to incorporate occupational health regulations into the national response plan, and to develop practical support functions that enable support to continue for an extended period, training systems for workers with opportunities to report accidents, and care systems to mitigate the health effects.

  11. Radiological impact to the population of the three major accidents happened in the civil nuclear industry

    International Nuclear Information System (INIS)

    Ortiz M, J. R.

    2013-10-01

    The greatest fear of the population before a nuclear accident, is the radiological impact to the health of people, due to the exposure to the liberated radioactive material during the accident, this fear is generally exaggerated or not well managed by the media. The best estimate in the received doses and their possible effects is carried out based on the information obtained during a certain time after the accident event. This work contains a summary of the information in the topic that at the present time has presented institutions as: the World Health Organization (Who), the United Nations Scientific Committee on Effects of Atomic Radiation (UNSCEAR), the Nuclear Regulatory Commission (NRC) and the World Nuclear Association, among others. The considered accidents are: first, the Unit-2 of the nuclear power plant of the Three Mile Island in Pennsylvania, USA occurred 28 March of 1979, in the Reactor TMI-2, type PWR of 900 M We; the second accident was 26 April of 1986, in the Unit-4 of the nuclear power plant of Chernobyl, in Ukraine, the involved reactor was type BRMK, of 1000 M We moderated by graphite and cooled with light water, the power plant is located to 100 Km to the northwest of Kiev; 25 years later occurred the third accident in the nuclear power plant of Fukushima Dai-ichi, in Japan, affecting at four of the six reactors of the power plant. A brief description of the accident is presented in each case, including the magnitude of the provoked liberations of radioactive material, the estimate doses of the population and the affected workers are presented, as well as the possible consequences of these doses on the health. The objective of this diffusion work is to give knowledge to the nuclear and radiological community of the available information on the topic, in order to be located in the appropriate professional context. (author)

  12. Factors contributing to young moped rider accidents in Denmark.

    Science.gov (United States)

    Møller, Mette; Haustein, Sonja

    2016-02-01

    Young road users still constitute a high-risk group with regard to road traffic accidents. The crash rate of a moped is four times greater than that of a motorcycle, and the likelihood of being injured in a road traffic accident is 10-20 times higher among moped riders compared to car drivers. Nevertheless, research on the behaviour and accident involvement of young moped riders remains sparse. Based on analysis of 128 accident protocols, the purpose of this study was to increase knowledge about moped accidents. The study was performed in Denmark involving riders aged 16 or 17. A distinction was made between accident factors related to (1) the road and its surroundings, (2) the vehicle, and (3) the reported behaviour and condition of the road user. Thirteen accident factors were identified with the majority concerning the reported behaviour and condition of the road user. The average number of accident factors assigned per accident was 2.7. Riding speed was assigned in 45% of the accidents which made it the most frequently assigned factor on the part of the moped rider followed by attention errors (42%), a tuned up moped (29%) and position on the road (14%). For the other parties involved, attention error (52%) was the most frequently assigned accident factor. The majority (78%) of the accidents involved road rule breaching on the part of the moped rider. The results indicate that preventive measures should aim to eliminate violations and increase anticipatory skills among moped riders and awareness of mopeds among other road users. Due to their young age the effect of such measures could be enhanced by infrastructural measures facilitating safe interaction between mopeds and other road users. Copyright © 2015 Elsevier Ltd. All rights reserved.

  13. Consequence of potential accidents in heavy water plants

    International Nuclear Information System (INIS)

    Croitoru, C.; Lazar, R.E.; Preda, I.A.; Dumitrescu, M.

    1998-01-01

    Heavy water plants realize the primary isotopic concentrations of water using H 2 O-H 2 S chemical exchange and they are chemical plants. As these plants are handling and spreading large quantities of hydrogen sulphide (high toxic, corrosive, flammable and explosive as) maintained in the process at relative high temperatures and pressures, it is required an assessing of risks associated with the potential accidents. The H 2 S released in atmosphere as a result of an accident will have negative consequences to property, population and environment. This paper presents a model of consequences quantitative assessment and its outcome for the most dangerous accident in heavy water plants. Several states of the art risk based methods were modified and linked together to form a proper model for this analyse. Five basic steps to identify the risks involved in operating the plants are followed: hazard identification, accident sequence development, H 2 S emissions calculus, dispersion analyses and consequences determination. A brief description of each step and some information of analysis results are provided. The accident proportions, the atmospheric conditions and the population density in the respective area were accounted for consequences calculus. The specific results of the consequences analysis allow to develop the plant's operating safety requirements so that the risk remain at an acceptable level. (authors)

  14. [Work-related accidents in traditional fishermen from the Medium Araguaia River region, Tocantins, Brazil].

    Science.gov (United States)

    Garrone Neto, Domingos; Cordeiro, Ricardo Carlos; Haddad, Vidal

    2005-01-01

    This is a cross-sectional study of work-related accidents among traditional fishermen in the Medium Araguaia River region of Tocantins, Brazil. From June to August 2002, fishermen from the Municipality of Araguacema were interviewed about the organization of their work activities and work-related accidents during the previous six months. Of the 92 participating fishermen, 56 reported having suffered a work-related accident (annual incidence was 82.6%). Some 95.7% of those interviewed did not regularly pay social security insurance as self-employed workers and were not aware of their social rights and duties. For fishermen reporting accidents, this proportion was 98.2%. Approximately 23.0% had another work activity, mainly as construction workers (47.6%) or sport-fishing guides (23.9%). Injuries inflicted by aquatic animals were the main form of accidents (about 86.0%). From these results, it is apparent that accidents from aquatic animals are an important health hazard, in some cases causing temporary work incapacity.

  15. RAPID-N: Assessing and mapping the risk of natural-hazard impact at industrial installations

    Science.gov (United States)

    Girgin, Serkan; Krausmann, Elisabeth

    2015-04-01

    Natural hazard-triggered technological accidents (so-called Natech accidents) at hazardous installations can have major consequences due to the potential for release of hazardous materials, fires and explosions. Effective Natech risk reduction requires the identification of areas where this risk is high. However, recent studies have shown that there are hardly any methodologies and tools that would allow authorities to identify these areas. To work towards closing this gap, the European Commission's Joint Research Centre has developed the rapid Natech risk assessment and mapping framework RAPID-N. The tool, which is implemented in an online web-based environment, is unique in that it contains all functionalities required for running a full Natech risk analysis simulation (natural hazards severity estimation, equipment damage probability and severity calculation, modeling of the consequences of loss of containment scenarios) and for visualizing its results. The output of RAPID-N are risk summary reports and interactive risk maps which can be used for decision making. Currently, the tool focuses on Natech risk due to earthquakes at industrial installations. However, it will be extended to also analyse and map Natech risk due to floods in the near future. RAPID-N is available at http://rapidn.jrc.ec.europa.eu. This presentation will discuss the results of case-study calculations performed for selected flammable and toxic substances to test the capabilities of RAPID-N both for single- and multi-site earthquake Natech risk assessment. For this purpose, an Istanbul earthquake scenario provided by the Turkish government was used. The results of the exercise show that RAPID-N is a valuable decision-support tool that assesses the Natech risk and maps the consequence end-point distances. These end-point distances are currently defined by 7 kPa overpressure for Vapour Cloud Explosions, 2nd degree burns for pool fire (which is equivalent to a heat radiation of 5 kW/m2 for 40s

  16. Consistency between subjectively and objectively measured hazard perception skills among young male drivers

    DEFF Research Database (Denmark)

    Abele, Liva; Haustein, Sonja; Møller, Mette

    2018-01-01

    . Subjective measures of HPS include self-reports derived based on the Hazard Perception Questionnaire (HPQ), Driving Skill Questionnaire (DSQ), and Brief Sensation Seeking Scale (BSSS). Results show that drivers who respond to the hazards on time, as compared to drivers who do not respond, have higher scores......Young male drivers have lower hazard perception skills (HPS) than older and more experienced drivers and a tendency to overestimate their skills in hazardous situations. Both factors contribute to an over-representation in traffic accidents. Based on a sample of 63 drivers aged 18-24, this study...... negatively when the hazard is visible. To enhance the HPS among young drivers, the results of this study suggest that specific hazard perception training is relevant, especially for hazards that require more advanced HPS....

  17. An integrated graphic–taxonomic–associative approach to analyze human factors in aviation accidents

    Directory of Open Access Journals (Sweden)

    Gong Lei

    2014-04-01

    Full Text Available Human factors are critical causes of modern aviation accidents. However, existing accident analysis methods encounter limitations in addressing aviation human factors, especially in complex accident scenarios. The existing graphic approaches are effective for describing accident mechanisms within various categories of human factors, but cannot simultaneously describe inadequate human–aircraft–environment interactions and organizational deficiencies effectively, and highly depend on analysts’ skills and experiences. Moreover, the existing methods do not emphasize latent unsafe factors outside accidents. This paper focuses on the above three limitations and proposes an integrated graphic–taxonomic–associative approach. A new graphic model named accident tree (AcciTree, with a two-mode structure and a reaction-based concept, is developed for accident modeling and safety defense identification. The AcciTree model is then integrated with the well-established human factors analysis and classification system (HFACS to enhance both reliability of the graphic part and logicality of the taxonomic part for improving completeness of analysis. An associative hazard analysis technique is further put forward to extend analysis to factors outside accidents, to form extended safety requirements for proactive accident prevention. Two crash examples, a research flight demonstrator by our team and an industrial unmanned aircraft, illustrate that the integrated approach is effective for identifying more unsafe factors and safety requirements.

  18. Identification and Prioritization of “Black Spots” without Using Accident Information

    Directory of Open Access Journals (Sweden)

    Mahmoudreza Keymanesh

    2017-01-01

    Full Text Available It is attempted to identify and prioritize the accident prone points (black spots in “Iraanshahr-Sarbaaz-Chabahar” road located in Baluchistan, Iran, without no use of accident data but rather using Analytic Hierarchy Process (AHP, which is the enhanced procedure of road safety audit technique. First, by surveying the whole route, all factors that could influence accidents in this road were specified; then the route was divided into eight sections; this division was performed based on the uniformity and homogeny of each section in terms of geometric design and regional conditions. In each section, potentially hazardous locations were identified and some questionnaires were prepared, which were filled by 5 road traffic experts familiar with the route; then the collected data were analyzed by Analytical Hierarchy Process (AHP using Expert Choice Software and the black spots were identified and prioritized. Finally, these black spots were compared with the black spots that had been obtained by traffic police based on accident data.

  19. Emergency preparedness and response in case of a fire accident with UF6 packages traversing the Suez Canal

    International Nuclear Information System (INIS)

    Salama, M.

    2004-01-01

    Egypt has a unique problem, the Suez Canal. Radioactive cargo passes regularly through the canal carrying new and spent reactor fuel. There are also about 1000 metric tonnes of uranium hexafluoride (UF 6 ) passing through the canal every year. In spite of all the precautions taken in the transport, accidents with packages containing UF 6 shipped through the Suez Canal may arise, even though the probability is minimal. Such accidents may be accompanied by injuries to or death of persons and damage to property including radiation and criticality hazards and high chemical toxicity, particularly if the accident occurred close to one of the three densely populated cities (Port Said, Ismailia and Suez), which are located along the west bank of the Suez Canal. The government of Egypt has established a national radiological emergency plan in order to deal with any radiological accidents which may arise inside the country. This paper considers the effect of a fire accident to industrial packages containing UF 6 on board a cargo ship passing along the Suez Canal near Port Said City. The accident scenario and emergency response actions taken during the different phases of the accident are presented and discussed. The paper highlights the importance of public awareness for populations located in densely populated areas along the bank of the Suez Canal, in order to react in a timely and effective way to avoid the toxic and radiological hazards resulting from such a type of accident. The possibility of upgrading the capabilities of civil defence and fire-fighting personnel is also discussed (author)

  20. Accidents in nuclear facilities: classification, incidence and impact

    International Nuclear Information System (INIS)

    Galicia A, J.; Paredes G, L. C.

    2012-10-01

    A general analysis of the 146 accidents reported officially in nuclear facilities from 1945 to 2012 is presented, among them some took place in: power or research nuclear reactors, critical and subcritical nuclear assemblies, handling of nuclear materials inside laboratories belonging to institutes or universities, in radiochemistry industrial plants and nuclear fuel factories. In form graph the incidence of these accidents is illustrated classified for; category, decades, geographical localization, country classification before the OECD, failure type, and the immediate or later victims. On the other hand, the main learned lessons of the nuclear accidents of Three Mile Island, Chernobyl and Fukushima are stood out, among those that highlight; the human factors, the necessity of designs more innovative and major technology for the operation, control and surveillance of the nuclear facilities, to increase the criterions of nuclear, radiological and physics safety applied to these facilities, the necessity to carry out probabilistic analysis of safety more detailed for cases of not very probable accidents and their impact, to revalue the selection criterions of the sites for nuclear locations, the methodology of post-accident sites recovery and major instrumentation for parameters evaluation and the radiological monitoring among others. (Author)

  1. Accident rates amongst regular bicycle riders in Tasmania, Australia.

    Science.gov (United States)

    Palmer, Andrew J; Si, Lei; Gordon, Jared M; Saul, Tim; Curry, Beverley A; Otahal, Petr; Hitchens, Peta L

    2014-11-01

    To characterise the demographics, cycling habits and accident rates of adult cyclists in Tasmania. Volunteers ≥18 years of age who had cycled at least once/week over the previous month provided information on demographics; cycling experience; bicycles owned; hours/km/trips cycled per week; cycling purpose; protective equipment used; and major (required third-party medical treatment or resulted ≥1 day off work) or minor (interfered with individuals' regular daily activities and/or caused financial costs) accidents while cycling. Over 8-months, 136 cyclists (70.6% male) completed the telephone survey. Mean (standard deviation) age was 45.4 (12.1) years with 17.1 (11.4) years of cycling experience. In the week prior to interview, cyclists averaged 6.6 trips/week (totalling 105.7km or 5.0h). The most common reason for cycling was commuting/transport (34% of trips), followed by training/health/fitness (28%). The incidence of major and minor cycling accidents was 1.6 (95% CI 1.1-2.0) and 3.7 (2.3-5.0) per 100,000km, respectively. Male sex was associated with a significantly lower minor accident risk (incidence rate ratio=0.34, p=0.01). Mountain biking was associated with a significantly higher risk of minor accident compared with road or racing, touring, and city or commuting biking (phealth and wellbeing; cyclists also contributed substantially to the local economy. Accident rates are higher in this sample than previously reported in Tasmania and internationally. Mountain biking was associated with higher risks of both major and minor accidents compared to road/racing bike riding. Copyright © 2014 Elsevier Ltd. All rights reserved.

  2. Accident risks in nuclear facilities. (Latest citations from the NTIS Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1994-02-01

    The bibliography contains citations concerning risk analysis and hazards evaluation of the design, construction, and operation of nuclear facilities. The citations also explore the risk and hazards of transporting radioactive materials to and from these facilities. Radiological calculations for environmental effects of nuclear accidents and the use of computer models in risk analysis are also included. (Contains 250 citations and includes a subject term index and title list.)

  3. Evaluation of hazards from industrial activity near nuclear power plants. Study of typical accidents

    International Nuclear Information System (INIS)

    Lannoy, A.; Gobert, T.; Granier, J.P.

    1981-08-01

    The design and dimensioning of nuclear power plant structures necessitate the evaluation of risks due to industrial activity. Among these risks, those due to the storage or transport of dangerous products merit special attention. They result, inter alia, in the explosion of flammable gas clouds. Such clouds can drift before igniting and, once alight, the resulting pressure wave can cause serious damage, even at a distance. A methodology both deterministic and probabilistic enabling this risk to be quantified has therefore been developed. It is based in part on an analysis of the statistics of actual accidents that have occurred. After briefly recalling the probabilistic model, the typical accidents selected are described and for three usual cases (storage under pressure, rail tank cars and road units) the main characteristics of the rupture are explicited. The deterministic models that have been worked out to calculate the consequences of such an accident: flow rate at the bursting point, evaporation, drift and atmospheric dispersion of the cloud formed, explosion of this cloud, are then described. At the present time the overpressure wave is quantified against a TNT equivalent of the explosive mixture. Some data are given as examples for three commonly employed hydrocarbons (butane, propane, propylene) [fr

  4. Chernobyl accident. Exposures and effects

    International Nuclear Information System (INIS)

    Bennett, B.; Bouville, A.; Hall, P.; Savkin, M.; Storm, H.

    2000-01-01

    The Chernobyl accident that occurred in Ukraine in April 1986 happened during an experimental test of the electrical control system as the reactor was being shut down for routine maintenance. The operators, in violation of safety regulations, had switched off important control systems and allowed the reactor to reach unstable, low-power conditions. A sudden power surge caused a steam explosion that ruptured the reactor vessel and allowed further violent fuel-steam interactions that destroyed the reactor and the reactor building. The Chernobyl accident was the most serious to have ever occurred in the nuclear power industry. The accident caused the early death of 30 power plant employees and fire fighters and resulted in widespread radioactive contamination in areas of Belarus, the Russian Federation, and Ukraine inhabited by several million people. Radionuclides released from the reactor that caused exposure of individuals were mainly iodine-131, caesium-134 and caesium-137. Iodine-131 has a short radioactive half-life (8 days), but it can be transferred relatively rapidly through milk and leafy vegetables to humans. Iodine becomes localized in the thyroid gland. For reasons of intake of these foods, size of thyroid gland and metabolism, the thyroid doses are usually greater to infants and children than to adults. The isotopes of caesium have relatively long half-lives (caesium-134: 2 years; caesium-137: 30 years). These radionuclides cause long-term exposures through the ingestion pathway and from external exposure to these radionuclides deposited on the ground. In addition to radiation exposure, the accident caused long-term changes in the lives of people living in the contaminated regions, since measures intended to limit radiation doses included resettlements, changes in food supplies, and restrictions in activities of individuals and families. These changes were accompanied by major economic, social and political changes in the affected countries resulting

  5. Technical risk audit method (tram): development and application to the auditing of major hazard sites

    International Nuclear Information System (INIS)

    Maddison, T.; Kirk, P.; Stansfield, R.

    1998-01-01

    The Technical Risk Audit Method (TRAM) has been developed by the UK Health and Safety Executive (UK HSE) as a risk-based auditing and inspection tool for application to Major Hazard process plant covered by the Seveso-I/Seveso-II directives. The objective of TRAM is to provide a framework in which plant inspection or audit can be undertaken and results collated. TRAM comprises a paper audit procedure and a software tool which is used to analyse the results. TRAM includes a semi-quantitative risk model, which may be used to rank risks both within and between similar facilities, using qualitative data collected during the inspection. The results of this qualitative analysis may be used to identify where inspector resources would be best deployed. To date, TRAM has been applied to a number of LPG storage and processing facilities in the UK, and the lessons learnt are being used to develop a robust version suitable for use by inspectors. The methodology will be made consistent with the risk model included in IEC 61508 'Functional safety of electrical/electronic/programmable electronic safety-related systems' to permit its application to a wide range of process plant and other hazardous facilities. (authors)

  6. Policy on stable iodine prophylaxis following nuclear reactor accidents (1989)

    International Nuclear Information System (INIS)

    1989-09-01

    This policy considers the alleviation of possible hazards that may arise from any radioiodines inhaled from a plume of fission products emanating from a nuclear reactor accident. Such a nuclear reactor may be land or ship-based. In any accident that releases radioiodines to the environment, one countermeasure that may need to be considered to reduce the effect of inhalation of radioiodines by persons downwind of the point of release is to provide those persons with tablets containing stable iodine. Both potassium iodide (KI) and potassium iodate (KIO 3 ) are recommended as effective prophylactics tablets for this purpose in Australia. Action levels, doses and contraindicatories are briefly outlined

  7. Application of FISH method in evaluation of a radiation accident

    International Nuclear Information System (INIS)

    Wang Mingming; Zheng Siying; Duan Zhikai; Zhang Shuxian; Xu Honglan

    2004-01-01

    To study effects of long term radiation hazard and explore the possibility of the application of chromosome aberration and FISH method to dose retrospection and reconstruction, FISH method was used to detect biological destination of three accidental victims at 7.5 years after Xinzhou accident. In the meantime, conventional chromosomal aberration, G-banding, CB micronuclei and HPRT gene locus mutation assays were performed. In addition, the growth and development of Victim S, who suffered the radiation accident as a fetus, were examined. And comparison of dose estimations between chromosome aberration and FISH method of the victims was conducted. The results demonstrated that the biological dose estimated by translocation frequency is very close to the imitated dose by the physical way after the accident if enough cells are observed. It is suggested that FISH may be applied to dose retrospection and reconstruction. Obvious chromosomal aberrations still existed in the examined victims at 7.5 years after the accident and displayed good dose correlative dependence. The results also showed that the growth and development of S were basically normal after birth

  8. A major sporting event does not necessarily mean an increased workload for accident and emergency departments. Euro96 Group of Accident and Emergency Departments

    OpenAIRE

    Cooke, M. W.; Allan, T. F.; Wilson, S.

    1999-01-01

    AIM: To determine whether there were any changes in attendance at accident and emergency departments that could be related to international football matches (Euro96 tournament). METHOD: Fourteen accident and emergency departments (seven adjacent to and seven distant from a Euro96 venue) provided their daily attendance figures for a nine week period: three weeks before, during, and after the tournament. The relation between daily attendance rates and Euro96 football matches was assessed ...

  9. Technical basis for the aboveground structure failure and associated represented hazardous conditions

    International Nuclear Information System (INIS)

    GOETZ, T.G.

    2003-01-01

    This technical basis document describes the risk binning process and the technical basis for assigning risk bins for the aboveground structure failure representative accident and associated represented hazardous conditions. This document was developed to support the documented safety analysis

  10. Robotics and artificial intelligence for hazardous environments

    International Nuclear Information System (INIS)

    Spelt, P.F.

    1993-01-01

    In our technological society, hazardous materials including toxic chemicals, flammable, explosive, and radioactive substances, and biological agents, are used and handled routinely. Each year, many workers who handle these substances are accidently contaminated, in some cases resulting in injury, death, or chronic disabilities. If these hazardous materials could be handled remotely, either with a teleoperated robot (operated by a worker in a safe location) or by an autonomous robot, then human suffering and economic costs of accidental exposures could be dramatically reduced. At present, it is still difficult for commercial robotic technology to completely replace humans involved in performing complex work tasks in hazardous environments. The robotics efforts at the Center for Engineering Systems Advanced Research represent a significant effort at contributing to the advancement of robotics for use in hazardous environments. While this effort is very broad-based, ranging from dextrous manipulation to mobility and integrated sensing, the technical portion of this paper will focus on machine learning and the high-level decision making needed for autonomous robotics

  11. Accident management for severe accidents

    International Nuclear Information System (INIS)

    Bari, R.A.; Pratt, W.T.; Lehner, J.; Leonard, M.; Disalvo, R.; Sheron, B.

    1988-01-01

    The management of severe accidents in light water reactors is receiving much attention in several countries. The reduction of risk by measures and/or actions that would affect the behavior of a severe accident is discussed. The research program that is being conducted by the US Nuclear Regulatory Commission focuses on both in-vessel accident management and containment and release accident management. The key issues and approaches taken in this program are summarized. 6 refs

  12. Snow hazard potential evaluation along G217 highway in Tianshan mountains by using GIS and RS

    Science.gov (United States)

    Tao, Jianwei

    2007-11-01

    Snow hazard especially avalanche potential along G217 national highway in Tianshan Mountains using remote sensing and GIS is evaluated and compared with actual site records of avalanche in a test area. Most places of the actual avalanche accidents are consistent with the places with the high snow hazard potential. But there are several places of the avalanche were not in the high hazard potential areas. The reason for this difference is discussed.

  13. Review of US accident/incident experience involving the transportation of radioactive material (RAM) 1971-1980

    International Nuclear Information System (INIS)

    McClure, J.D.; Emerson, E.L.

    1980-01-01

    This paper analyzes the transportation accidents and incidents which have occurred in the United States in the period 1971-1980 based upon the information in the Radioactive Material Transportation Accident/Incident Data Base developed by the Transportation Technology Center (TTC) at Sandia National Laboratories. The accident/incident data base incorporates the files of the Hazardous Material Incident Report (HMIR) system operated by the Material Transportation Bureau of the US Department of Transportation (DOT) with additional information obtained from the files of the US Nuclear Regulatory Commission (NRC). A principal objective of this paper is to summarize US accident/incident experience for the past ten years, providing a concise statement of radioactive material (RAM) package failure description for the transport modes of truck, rail and air

  14. SAMEX: A severe accident management support expert

    International Nuclear Information System (INIS)

    Park, Soo-Yong; Ahn, Kwang-Il

    2010-01-01

    A decision support system for use in a severe accident management following an incident at a nuclear power plant is being developed which is aided by a severe accident risk database module and a severe accident management simulation module. The severe accident management support expert (SAMEX) system can provide the various types of diagnostic and predictive assistance based on the real-time plant specific safety parameters. It consists of four major modules as sub-systems: (a) severe accident risk data base module (SARDB), (b) risk-informed severe accident risk data base management module (RI-SARD), (c) severe accident management simulation module (SAMS), and (d) on-line severe accident management guidance module (on-line SAMG). The modules are integrated into a code package that executes within a WINDOWS XP operating environment, using extensive user friendly graphics control. In Korea, the integrated approach of the decision support system is being carried out under the nuclear R and D program planned by the Korean Ministry of Education, Science and Technology (MEST). An objective of the project is to develop the support system which can show a theoretical possibility. If the system is feasible, the project team will recommend the radiation protection technical support center of a national regulatory body to implement a plant specific system, which is applicable to a real accident, for the purpose of immediate and various diagnosis based on the given plant status information and of prediction of an expected accident progression under a severe accident situation.

  15. Stocks and energy shocks : the impact of energy accidents on stock market value

    NARCIS (Netherlands)

    Scholtens, B.; Boersen, A.

    We investigate how financial market participants value energy accidents. We employ an event study to look into the response of stock markets to 209 accidents. These accidents were derived from Sovacool's (2008) database on major energy accidents from 1907 to 2007. It appears that the stock market in

  16. The environmental impact of radioactive releases from accidents in nuclear power reactors

    International Nuclear Information System (INIS)

    Beattie, J.R.; Griffiths, R.F.; Kaiser, G.D.; Kinchin, G.H.

    1978-01-01

    A survey of accidental releases of radioactivity from thermal and fast reactors is presented. Following a general discussion on the hazards involved, the nature of the environmental impact of radioactive releases is examined. This includes a brief review of the natural radiation background, the effect on human health of various levels of radiation and radioactivity, permissible and reference levels, and the type of hazards from both passing clouds of airbourne radioactive material and from ground deposited material. The problem of atmospheric dispersion and methods of calculations of radioactive materials in the atmosphere are examined in order for the consequences of accidental release to be analysed. National accidents and their environmental consequences are then examined. Finally there is a review of the risks to which man is always exposed because of his environment. Common and collective risks are also considered. Conclusions are reached as to the acceptibility or otherwise of the environmental impact of reactor accidents. (U.K.)

  17. Elements to diminish radioactive accidents

    International Nuclear Information System (INIS)

    Cortes I, M.E.; Ramirez G, F.P.

    1998-01-01

    In this work it is presented an application of the cause-effect diagram method or Ichikawa method identifying the elements that allow to diminish accidents when the radioactive materials are transported. It is considered the transport of hazardous materials which include radioactive materials in the period: December 1996 until March 1997. Among the identified elements by this method it is possible to mention: the road type, the radioactive source protection, the grade driver responsibility and the preparation that the OEP has in the radioactive material management. It is showed the differences found between the country inner roads and the Mexico City area. (Author)

  18. Work-related accidents and occupational diseases in veterinarians and their staff.

    Science.gov (United States)

    Nienhaus, Albert; Skudlik, Christoph; Seidler, Andreas

    2005-04-01

    We assessed the occupational hazards in veterinary practice by analysing accident insurance data in order to stimulate strategies to prevent occupational accidents and diseases in veterinarians and their staff. Approximately 10,000 veterinary practices comprising about 27,500 veterinarians and their staff are covered by the Institution of Statutory Accident Insurance of the Health and Welfare Service (BGW). Each year about 2,000 accident and occupational disease claims are filed by these veterinarians and their staff. The claims for the 5-year period from 1998 to 2002 are analysed in this paper. For 2002, the incidence rate for accidents in the workplace was 105.4 per 1,000 full-time workers, a rate 2.9-times higher than for general practitioners of human medicine. When only severe accidents resulting in a loss of work time of more than 3 days were analysed, the relative risk increased to 9.2. Approximately 66% of the reported accidents are due to scratches, bites, or kicks from animals. Claims of occupational disease are filed 2.7-times more often by veterinarians and their staff than by general practitioners and their staff. The occupational diseases filed most often concern the skin (39%), followed by allergic respiratory diseases (30.5%), and infectious diseases (19.1%). Prevention strategies for veterinarians should focus on accidents caused by animals. The prevention of occupational diseases should focus on skin diseases, respiratory disease, and infections.

  19. Process business risk: a methodology for assessing and mitigating the financial impact of process plant accidents; Avaliacao de risco ao negocio devido a acidentes de processo em plantas industriais

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Ana Cristina C.; Bardy, Mariana B. [Det Norske Veritas (Brazil)

    2008-07-01

    Traditional risk management has focused on effects on people, particularly when using Quantitative Risk Assessment (QRA). A much broader approach is being adopted nowadays, with companies beginning to consider potential accidental losses in their decision making process. This paper describes a study where business risks from major accident hazards were assessed for a large petrochemical plant. The results are presented as F-Cost curves, which are similar to traditional F-N curves, but represent cumulative frequencies of events versus their cost, instead of fatalities. A different variety of costs can be evaluated as property damage, business interruption, inventory loss, environmental loss, clean-up costs, legal costs, fatality and injury costs, amongst others. As final objective of the study insurance values can be adjusted as well as decisions on reducing risk can be made based on the actual benefit, considering the reduction of losses and the amount to be spent on mitigating major risks. Also, values for civil liability insurance can be reviewed, based on the hazards that can result in fatalities and injuries, as well as property losses, for third parties. This paper presents the results of a study which involved the evaluation of the company's civil liability. The key driver was to consider a more accurate value for the company insurance policy, considering the different losses that major accident can lead on for a community and industries located nearby a petrochemical plant. The results of the analysis are presented as F-Cost curves and we describe the risk-based decision making process and criteria adopted by the company to set the maximum loss value to be insured for civil liability. In conclusion, this paper presents results from a real life example of the application of the quantitative evaluation of business risks, illustrating that a financial or business risk approach can help management in day-to-day decisions when considering possible effects of

  20. Modeling secondary accidents identified by traffic shock waves.

    Science.gov (United States)

    Junhua, Wang; Boya, Liu; Lanfang, Zhang; Ragland, David R

    2016-02-01

    The high potential for occurrence and the negative consequences of secondary accidents make them an issue of great concern affecting freeway safety. Using accident records from a three-year period together with California interstate freeway loop data, a dynamic method for more accurate classification based on the traffic shock wave detecting method was used to identify secondary accidents. Spatio-temporal gaps between the primary and secondary accident were proven be fit via a mixture of Weibull and normal distribution. A logistic regression model was developed to investigate major factors contributing to secondary accident occurrence. Traffic shock wave speed and volume at the occurrence of a primary accident were explicitly considered in the model, as a secondary accident is defined as an accident that occurs within the spatio-temporal impact scope of the primary accident. Results show that the shock waves originating in the wake of a primary accident have a more significant impact on the likelihood of a secondary accident occurrence than the effects of traffic volume. Primary accidents with long durations can significantly increase the possibility of secondary accidents. Unsafe speed and weather are other factors contributing to secondary crash occurrence. It is strongly suggested that when police or rescue personnel arrive at the scene of an accident, they should not suddenly block, decrease, or unblock the traffic flow, but instead endeavor to control traffic in a smooth and controlled manner. Also it is important to reduce accident processing time to reduce the risk of secondary accident. Copyright © 2015 Elsevier Ltd. All rights reserved.

  1. Radiation hazards in the neighbourhood of uranium reactors; Dangers des rayonnements aupres des piles a uranium

    Energy Technology Data Exchange (ETDEWEB)

    Joffre, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1956-07-01

    Radiation hazards near uranium reactors may be divided in two groups. Hazards when the reactor is normally operating: {gamma} radiation from hot uranium or air contamination by fission gases, {gamma} radiation or contamination by the coolant (air, nitrogen, heavy-water), {gamma} radiation from radioisotopes. Hazards in the case of an accident: presence of hot uranium in the atmosphere, soil contamination. (author) [French] Les dangers d'irradiation aupres des piles a uranium sont a classer essentiellement en deux groupes. Les dangers existant aupres d'une pile exploitee normalement: irradiation {gamma} par l'uranium irradie ou contamination de l'air par des gaz de fission, irradiation {gamma} ou contamination par les fluides de refroidissement (air, azote, eau lourde), irradiation {gamma} par les radioelements fabriques. Les dangers en cas d'accident survenant a un reacteur en fonctionnement, ayant pour consequence : la presence dans l'air d'uranium irradie, la contamination du sol. (auteur)

  2. Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

    1996-12-01

    This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

  3. Severe accident source term reassessment

    International Nuclear Information System (INIS)

    Hazzan, M.J.; Gardner, R.; Warman, E.A.; Jacobs, S.B.

    1987-01-01

    This paper summarizes the status of the reassessment of severe reactor accident source terms, which are defined as the quantity, type, and timing of fission product releases from such accidents. Concentration is on the major results and conclusions of analyses with modern methods for both pressurized water reactors (PWRs) and boiling water reactors (BWRs), and the special case of containment bypass. Some distinctions are drawn between analyses for PWRs and BWRs. In general, the more the matter is examined, the consequences, or probability of serious consequences, seem to be less. (author)

  4. Criticality accident alarm system

    International Nuclear Information System (INIS)

    Malenfant, R.E.

    1991-01-01

    The American National Standard ANSI/ANS-8.3-1986, Criticality Accident Alarm System provides guidance for the establishment and maintenance of an alarm system to initiate personnel evacuation in the event of inadvertent criticality. In addition to identifying the physical features of the components of the system, the characteristics of accidents of concern are carefully delineated. Unfortunately, this ANSI Standard has led to considerable confusion in interpretation, and there is evidence that the ''minimum accident of concern'' may not be appropriate. Furthermore, although intended as a guide, the provisions of the standard are being rigorously applied, sometimes with interpretations that are not consistent. Although the standard is clear in the use of absorbed dose in free air of 20 rad, at least one installation has interpreted the requirement to apply to dose in soft tissue. The standard is also clear in specifying the response to both neutrons and gamma rays. An assembly of uranyl fluoride enriched to 5% 235 U was operated to simulate a potential accident. The dose, delivered in a free run excursion 2 m from the surface of the vessel, was greater than 500 rad, without ever exceeding a rate of 20 rad/min, which is the set point for activating an alarm that meets the standard. The presence of an alarm system would not have prevented any of the five major accidents in chemical operations nor is it absolutely certain that the alarms were solely responsible for reducing personnel exposures following the accident. Nevertheless, criticality alarm systems are now the subject of great effort and expense. 13 refs

  5. [Fatal occupational accidents in Lombardy].

    Science.gov (United States)

    Pianosi, G

    1995-01-01

    All fatal occupational accidents compensated in Lombardy from 1984 to 1989 were analyzed (1259 cases): significant differences between geographical distribution of fatal occupational accidents and workers were observed. Males accounted for about 95% of fatalities; an excess of cases was shown in both young and elderly workers. Death was the consequence of injuries involving most frequently the head, thorax and spinal cord. An excess of fatalities was observed in agriculture and, at a lower level, in manufacturing industries; small enterprises were involved in approximately 25% of fatalities occurring in the manufacturing industries and services. Employers were the victims of fatal accidents in 50% of cases in agriculture and in 70% of cases in craft industries. Construction, agriculture and transport accounted for about 50% of all fatalities. About 50% of fatal occupational accidents were related to vehicle use: the victim was the driver in the majority of cases, sometimes the victim was run over by a vehicle or fell from a vehicle. The results agree with some previous observations (e.g.: sex and age distribution; construction, agriculture and transport as working activities at high accident risk); but some original observations have emerged, in particular about the frequency of employers as victims and the role of vehicles in the genesis of fatal occupational accidents. If further studies confirm these latter observations, important developments could follow in preventive action design and implementation.

  6. Nuclear power reactor core melt accidents. Current State of Knowledge

    International Nuclear Information System (INIS)

    Jacquemain, Didier; Cenerino, Gerard; Corenwinder, Francois; Raimond, Emmanuel IRSN; Bentaib, Ahmed; Bonneville, Herve; Clement, Bernard; Cranga, Michel; Fichot, Florian; Koundy, Vincent; Meignen, Renaud; Corenwinder, Francois; Leteinturier, Denis; Monroig, Frederique; Nahas, Georges; Pichereau, Frederique; Van-Dorsselaere, Jean-Pierre; Couturier, Jean; Debaudringhien, Cecile; Duprat, Anna; Dupuy, Patricia; Evrard, Jean-Michel; Nicaise, Gregory; Berthoud, Georges; Studer, Etienne; Boulaud, Denis; Chaumont, Bernard; Clement, Bernard; Gonzalez, Richard; Queniart, Daniel; Peltier, Jean; Goue, Georges; Lefevre, Odile; Marano, Sandrine; Gobin, Jean-Dominique; Schwarz, Michel; Repussard, Jacques; Haste, Tim; Ducros, Gerard; Journeau, Christophe; Magallon, Daniel; Seiler, Jean-Marie; Tourniaire, Bruno; Durin, Michel; Andreo, Francois; Atkhen, Kresna; Daguse, Thierry; Dubreuil-Chambardel, Alain; Kappler, Francois; Labadie, Gerard; Schumm, Andreas; Gauntt, Randall O.; Birchley, Jonathan

    2015-11-01

    For over thirty years, IPSN and subsequently IRSN has played a major international role in the field of nuclear power reactor core melt accidents through the undertaking of important experimental programmes (the most significant being the Phebus-FP programme), the development of validated simulation tools (the ASTEC code that is today the leading European tool for modelling severe accidents), and the coordination of the SARNET (Severe Accident Research Network) international network of excellence. These accidents are described as 'severe accidents' because they can lead to radioactive releases outside the plant concerned, with serious consequences for the general public and for the environment. This book compiles the sum of the knowledge acquired on this subject and summarises the lessons that have been learnt from severe accidents around the world for the prevention and reduction of the consequences of such accidents, without addressing those from the Fukushima accident, where knowledge of events is still evolving. The knowledge accumulated by the Institute on these subjects enabled it to play an active role in informing public authorities, the media and the public when this accident occurred, and continues to do so to this day. Following the introduction, which describes the structure of this book and highlights the objectives of R and D on core melt accidents, this book briefly presents the design and operating principles (Chapter 2) and safety principles (Chapter 3) of the reactors currently in operation in France, as well as the main accident scenarios envisaged and studied (Chapter 4). The objective of these chapters is not to provide exhaustive information on these subjects (the reader should refer to the general reference documents listed in the corresponding chapters), but instead to provide the information needed in order to understand, firstly, the general approach adopted in France for preventing and mitigating the consequences of core melt

  7. LWR and HTGR coolant dynamics: the containment of severe accidents

    International Nuclear Information System (INIS)

    Theofanous, T.G.; Gherson, P.; Nourbakhsh, H.P.; Hu, K.; Iyer, K.; Viskanta, R.; Lommers, L.

    1983-07-01

    This is the final report of a project containing three major tasks. Task I deals with the fundamental aspects of energetic fuel/coolant interactions (steam explosions) as they pertain to LWR core melt accidents. Task II deals with the applied aspects of LWR core melt accident sequences and mechanisms important to containment response, and includes consideration of energetic fuel/coolant interaction events, as well as non-explosive ones, corium material disposition and eventual coolability, and containment pressurization phenomena. Finally, Task III is concerned with HTGR loss of forced circulation accidents. This report is organized into three major parts corresponding to these three tasks respectively

  8. Woodworking injuries: a comparative study of work-related and hobby-related accidents.

    Science.gov (United States)

    Loisel, F; Bonin, S; Jeunet, L; Pauchot, J; Tropet, Y; Obert, L

    2014-10-01

    The primary objective of this study was to describe the injury characteristics and demographics of patients injured during woodworking activities, upon their arrival to the emergency department in a regional of France where this industry is prevalent. The secondary objective was to compare patient and injury characteristics for work-related and hobby-related accidents. A cohort of 87 patients who had suffered a woodworking accident over a two-year period was evaluated; 79 were available for follow-up. The context and circumstances of the accident, nature and location of the injuries and patient demographics were recorded. Hobby-related accidents accounted for two-thirds of the accidents (51/79). Most of the injured workers were either loggers (35%) or carpenters (46%). The hand was injured in 53 cases (67%). Work-related accidents resulted in significantly more serious consequences in terms of hospital stay, work stoppage, resumption of work or retraining than hobby-related accidents. For the workplace accidents, 86% occurred on new machines; more than 25% of the machines involved in accidents at home were over 15 years. Sixty-eight per cent of workers were wearing their safety gear, while only 31% of those injured during recreational woodworking wore the appropriate gear. Several elements of prevention should be improved: information about the need to maintain the equipment, protect the worker with suitable clothing, and learn which maneuvers are considered hazardous. Safety gear should be regularly inspected in the workplace. Copyright © 2014. Published by Elsevier SAS.

  9. 75 FR 5258 - Hazardous Materials Transportation; Registration and Fee Assessment Program

    Science.gov (United States)

    2010-02-02

    ...) train public sector hazardous materials emergency response employees to respond to accidents and... officers, and 500,000 emergency medical services (EMS) providers. Due to the high turnover rates of... planning grants; A new $4,000,000 grant program for non-profit hazmat employee organizations to train...

  10. The theatrical stage as accident site in professional dance.

    Science.gov (United States)

    Wanke, Eileen M; Arendt, Michael; Mill, Helmgard; Koch, Franziska; Davenport, Jacqueline; Fischer, Axel; Groneberg, David A

    2014-03-01

    Reducing work-related health hazards at the different theatre workplaces is one aspect of preventive options in professional dance. This also applies to hazards on the highly variable theatrical stage areas. However, detailed information on these stages and their risks is not available. The aim of this study was to analyze and evaluate work-related traumatic injuries in the stage area. The basis for the evaluation was accident reports, from the German National Statutory Insurance, of work-related traumatic injuries occurring on stage in professional dancers (n=790: 407 males, 383 females) over a 17-year period (1995-2011). Most (79.4%) of the accidents on stage occurred during an ongoing performance (frequency: 10.1/100 performances), with only 19.7% occurring during rehearsals on stage (p<0.001). Due to the sustained injury, 30.2% of the dancers sustained a time-loss injury. Most (57.7%) of the injured dancers were older than 25 years. Of the accidents, 59.3% were initiated by a definably extrinsic cause, with 40.7% caused by intrinsic factors (p<0.001). Injuries were most commonly caused by the "partner" (21.7%) or "floor" (21.0%). The lower extremity was the most commonly affected body region (63.6%) (p<0.001). Stage performances seem to carry an increased injury risk compared to rehearsals. The "risk" of on-stage work is spread across various factors that seem to be stage-specific. There is a need for further qualitative and quantitative research to be able to classify the stage as workplace more precisely.

  11. Occupational accidents involving biological material among public health workers.

    Science.gov (United States)

    Chiodi, Mônica Bonagamba; Marziale, Maria Helena Palucci; Robazzi, Maria Lúcia do Carmo Cruz

    2007-01-01

    This descriptive research aimed to recognize the occurrence of work accidents (WA) involving exposure to biological material among health workers at Public Health Units in Ribeirão Preto-SP, Brazil. A quantitative approach was adopted. In 2004, 155 accidents were notified by means of the Work Accident Communication (WAC). Sixty-two accidents (40%) involved exposure to biological material that could cause infections like Hepatitis and Aids. The highest number of victims (42 accidents) came from the category of nursing aids and technicians. Needles were responsible for 80.6% of accidents and blood was the biological material involved in a majority of occupational exposure cases. This subject needs greater attention, so that prevention measures can be implemented, which consider the peculiarities of the activities carried out by the different professional categories.

  12. The Contribution of Palaeoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    International Nuclear Information System (INIS)

    2015-06-01

    IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations, published in 2010, covers all aspects of site evaluation relating to seismic hazards and recommends the use of prehistoric, historical and instrumental earthquake data in seismic hazard assessments. Prehistoric data on earthquakes cover a much longer period than do historical and instrumental data. However, gathering such data is generally difficult in most regions of the world, owing to an absence of human records. Prehistoric data on earthquakes can be obtained through the use of palaeoseismic techniques. This publication describes the current status and practices of palaeoseismology, in order to support Member States in meeting the recommendations of SSG-9 and in establishing the necessary earthquake related database for seismic hazard assessment and reassessment. At a donors’ meeting of the International Seismic Safety Centre Extrabudgetary Project in January 2011, it was suggested to develop detailed guidelines on seismic hazards. Soon after the meeting, the disastrous Great East Japan Earthquake and Tsunami of 11 March 2011 and the consequent accident at the Fukushima Daiichi nuclear power plant occurred. The importance of palaeoseismology for seismic hazard assessment in site evaluation was highlighted by the lessons learned from the Fukushima Daiichi nuclear power plant accident. However, no methodology for performing investigations using palaeoseismic techniques has so far been available in an IAEA publication. The detailed guidelines and practical tools provided here will be of value to nuclear power plant operating organizations, regulatory bodies, vendors, technical support organizations and researchers in the area of seismic hazard assessment in site evaluation for nuclear installations, and the information will be of importance in support of hazard assessments in the future

  13. Logistic Regression in the Identification of Hazards in Construction

    Science.gov (United States)

    Drozd, Wojciech

    2017-10-01

    The construction site and its elements create circumstances that are conducive to the formation of risks to safety during the execution of works. Analysis indicates the critical importance of these factors in the set of characteristics that describe the causes of accidents in the construction industry. This article attempts to analyse the characteristics related to the construction site, in order to indicate their importance in defining the circumstances of accidents at work. The study includes sites inspected in 2014 - 2016 by the employees of the District Labour Inspectorate in Krakow (Poland). The analysed set of detailed (disaggregated) data includes both quantitative and qualitative characteristics. The substantive task focused on classification modelling in the identification of hazards in construction and identifying those of the analysed characteristics that are important in an accident. In terms of methodology, resource data analysis using statistical classifiers, in the form of logistic regression, was the method used.

  14. Advanced evacuation model managed through fuzzy logic during an accident in LNG terminal

    Energy Technology Data Exchange (ETDEWEB)

    Stankovicj, Goran; Petelin, Stojan [Faculty for Maritime Studies and Transport, University of Ljubljana, Portorozh (Sierra Leone); others, and

    2014-07-01

    Evacuation of people located inside the enclosed area of an LNG terminal is a complex problem, especially considering that accidents involving LNG are potentially very hazardous. In order to create an evacuation model managed through fuzzy logic, extensive influence must be generated from safety analyses. A very important moment in the optimal functioning of an evacuation model is the creation of a database which incorporates all input indicators. The output result is the creation of a safety evacuation route which is active at the moment of the accident. (Author)

  15. Risk assessment for the transportation of hazardous waste and hazardous waste components of low-level mixed waste and transuranic waste for the US Department of Energy waste management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    Lazaro, M.A.; Policastro, A.J.; Hartmann, H.M.; Chang, Y.S.

    1996-12-01

    This report, a supplement to Appendix E (Transportation Risk) of the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS), provides additional information supporting the accident data for chemical risk assessment and health risk methodology described in that appendix (Part II) and presents the uncertainty analysis and on-site risk calculations. This report focuses on hazardous material truck accident rates, release probabilities, and release quantities; provides the toxicological values derived for each hazardous chemical assessed in the WM PEIS and further details on the derivation of health criteria; describes the method used in the transportation risk assessments to address potential additivity of health effects from simultaneous exposure to several chemicals and the method used to address transportation risks for maximally exposed individuals; presents an expanded discussion of the uncertainty associated with transportation risk calculations; and includes the results of the on-site transportation risk analysis. In addition, two addenda are provided to detail the risk assessments conducted for the hazardous components of low-level mixed waste (Addendum I) and transuranic waste (Addendum II)

  16. Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung-yeop; Lim, Ho-Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study.

  17. Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

    International Nuclear Information System (INIS)

    Kim, Sung-yeop; Lim, Ho-Gon

    2016-01-01

    Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study

  18. Monitoring Severe Accidents Using AI Techniques

    International Nuclear Information System (INIS)

    No, Young Gyu; Kim, Ju Hyun; Na, Man Gyun; Ahn, Kwang Il

    2011-01-01

    It is very difficult for nuclear power plant operators to monitor and identify the major severe accident scenarios following an initiating event by staring at temporal trends of important parameters. The objective of this study is to develop and verify the monitoring for severe accidents using artificial intelligence (AI) techniques such as support vector classification (SVC), probabilistic neural network (PNN), group method of data handling (GMDH) and fuzzy neural network (FNN). The SVC and PNN are used for event classification among the severe accidents. Also, GMDH and FNN are used to monitor for severe accidents. The inputs to AI techniques are initial time-integrated values obtained by integrating measurement signals during a short time interval after reactor scram. In this study, 3 types of initiating events such as the hot-leg LOCA, the cold-leg LOCA and SGTR are considered and it is verified how well the proposed scenario identification algorithm using the GMDH and FNN models identifies the timings when the reactor core will be uncovered, when CET will exceed 1200 .deg. F and when the reactor vessel will fail. In cases that an initiating event develops into a severe accident, the proposed algorithm showed accurate classification of initiating events. Also, it well predicted timings for important occurrences during severe accident progression scenarios, which is very helpful for operators to perform severe accident management

  19. Hazardous substances shipping at inland water harbors

    International Nuclear Information System (INIS)

    Benkovic, Z.

    2009-01-01

    Safety measures and regulations system covering the aspects of fire protection, professional and ecological safety are aimed to create a safe working environment, by detection and remedy of conditions that are potentially hazardous for the well-being of the employees or are leading to certain undesired events. Such unwanted incidents may result in different consequences: operating person's injury, environment pollution or material damage. This study attempts to illustrate the organization of work during hazardous matter loading and unloading at inland water harbors, based on legal provisions and decrees involving safety precautions, and in order to achieve constant enhancement of operating procedure, decreasing thereby the number of work-related injuries and various accidental situations. Fundamental precondition required to prevent possible accidents and to optimize general safety policy is to recognize and control any danger or potential hazard, as well as to be familiar with the legal provisions covering the inland waterway transport of harmful substances.(author)

  20. Possibility of the development of a Serbian protection system against chemical accidents

    Directory of Open Access Journals (Sweden)

    Dejan R. Inđić

    2012-10-01

    Full Text Available The paper presents a draft of a system model for responding in case of chemical accidents in accordance with the current legislation regarding the environment protection, the structure and elements of the existing response system in case of chemical accidents, other works dealing with the issue as well as the prospects planned by those responsible for the environmental protection. The paper discuss the possibilities of different institutions and agencies of the Republic of Serbia to engage in specialized methods of cooperation and protection against chemical hazards in accordance with Article X of the Convention on the Prohibition of Chemical Weapons.

  1. Major Factors Affecting Incidence of Childhood Thyroid Cancer in Belarus after the Chernobyl Accident: Do Nitrates in Drinking Water Play a Role?

    Science.gov (United States)

    Drozd, Valentina M; Saenko, Vladimir A; Brenner, Alina V; Drozdovitch, Vladimir; Pashkevich, Vasilii I; Kudelsky, Anatoliy V; Demidchik, Yuri E; Branovan, Igor; Shiglik, Nikolay; Rogounovitch, Tatiana I; Yamashita, Shunichi; Biko, Johannes; Reiners, Christoph

    2015-01-01

    One of the major health consequences of the Chernobyl Nuclear Power Plant accident in 1986 was a dramatic increase in incidence of thyroid cancer among those who were aged less than 18 years at the time of the accident. This increase has been directly linked in several analytic epidemiological studies to iodine-131 (131I) thyroid doses received from the accident. However, there remains limited understanding of factors that modify the 131I-related risk. Focusing on post-Chernobyl pediatric thyroid cancer in Belarus, we reviewed evidence of the effects of radiation, thyroid screening, and iodine deficiency on regional differences in incidence rates of thyroid cancer. We also reviewed current evidence on content of nitrate in groundwater and thyroid cancer risk drawing attention to high levels of nitrates in open well water in several contaminated regions of Belarus, i.e. Gomel and Brest, related to the usage of nitrogen fertilizers. In this hypothesis generating study, based on ecological data and biological plausibility, we suggest that nitrate pollution may modify the radiation-related risk of thyroid cancer contributing to regional differences in rates of pediatric thyroid cancer in Belarus. Analytic epidemiological studies designed to evaluate joint effect of nitrate content in groundwater and radiation present a promising avenue of research and may provide useful insights into etiology of thyroid cancer.

  2. Major Factors Affecting Incidence of Childhood Thyroid Cancer in Belarus after the Chernobyl Accident: Do Nitrates in Drinking Water Play a Role?

    Directory of Open Access Journals (Sweden)

    Valentina M Drozd

    Full Text Available One of the major health consequences of the Chernobyl Nuclear Power Plant accident in 1986 was a dramatic increase in incidence of thyroid cancer among those who were aged less than 18 years at the time of the accident. This increase has been directly linked in several analytic epidemiological studies to iodine-131 (131I thyroid doses received from the accident. However, there remains limited understanding of factors that modify the 131I-related risk. Focusing on post-Chernobyl pediatric thyroid cancer in Belarus, we reviewed evidence of the effects of radiation, thyroid screening, and iodine deficiency on regional differences in incidence rates of thyroid cancer. We also reviewed current evidence on content of nitrate in groundwater and thyroid cancer risk drawing attention to high levels of nitrates in open well water in several contaminated regions of Belarus, i.e. Gomel and Brest, related to the usage of nitrogen fertilizers. In this hypothesis generating study, based on ecological data and biological plausibility, we suggest that nitrate pollution may modify the radiation-related risk of thyroid cancer contributing to regional differences in rates of pediatric thyroid cancer in Belarus. Analytic epidemiological studies designed to evaluate joint effect of nitrate content in groundwater and radiation present a promising avenue of research and may provide useful insights into etiology of thyroid cancer.

  3. [Medical certificates in occupational accidents, in common law and social affairs].

    Science.gov (United States)

    El Banna, S; Van de Vyvere, A; Beauthier, J-P

    2013-09-01

    Physicians are asked to complete certificates within their profession. These certificates relate to various aspects of an individual's life, from birth to the end of life. The nature of requests is striking by its diversity. As a first step, the authors recall the outline of a certificate and its structure, as well as traps, hazards and risks to avoid. In a second step they describe three specific situations for the certificate: in the context of work accidents, common law accidents and social matters. All materials can not be treated in this space, so they refer the reader to the main bibliographic sources useful in this matter.

  4. NPP Krsko Severe Accident Management Guidelines Upgrade

    International Nuclear Information System (INIS)

    Mihalina, Mario; Spalj, Srdjan; Glaser, Bruno; Jalovec, Robi; Jankovic, Gordan

    2014-01-01

    Nuclear Power Plant Krsko (NEK) has decided to take steps for upgrade of safety measures to prevent severe accidents, and to improve the means to successfully mitigate their consequences. The content of the program for the NEK Safety Upgrade is consistent with the nuclear industry response to Fukushima accident, which revealed many new insights into severe accidents. Therefore, new strategies and usage of new systems and components should be integrated into current NEK Severe Accident Management Guidelines (SAMG's). SAMG's are developed to arrest the progression of a core damage accident and to limit the extent of resulting releases of fission products. NEK new SAMG's revision major changes are made due to: replacement of Electrical Recombiners by Passive Autocatalytic Recombiners (PARs) and the installation of Passive Containment Filtered Vent System (PCFV); to handle a fuel damage situation in Spent Fuel Pool (SFP) and to assess risk of core damage situation during shutdown operation. (authors)

  5. Planning on a regional basis for a major radiation accident

    International Nuclear Information System (INIS)

    Casey, W.R.

    1981-01-01

    As a part of the Radiological Assistance Program, members of the Safety and Environmental Protection Division of Brookhaven National Laboratory have served as a response team for many years to the northeastern section of the United States. During this time, responses have been made to several significant incidents, including the accident at Three Mile Island. The planning and preparation for emergency response activities will be discussed. Included will be a review of instrument requirements, analytical and support equipment, modes of response, and communication needs. Interaction with and support from other response teams will be discussed. In particular, the lessons from the respone to Three Mile Island will be reviewed

  6. Frequency of damage by external hazards based on geographical information

    Energy Technology Data Exchange (ETDEWEB)

    Becker, G. [RISA Sicherheitsanalysen GmbH, Berlin (Germany); Camarinopoulos, A.; Karali, T. [ERRA, Athens (Greece); Camarinopoulos, L. [Piraeus Univ. (Greece); Schubert, B. [VENE, Hamburg (Germany)

    2013-07-01

    External explosions can significantly contribute to risk of damage for industrial plants. External explosions may origin from other plants in the neighborhood, which store and operate with explosive substances, or from transport of such substances on road, rail, or water. In all cases, some accident is a necessary condition for a hazard. Another probabilistic element is the probability of ignition. If transport causes the explosion, the location of the accident will influence the consequences. If deflagration is involved, ignition will not necessarily occur at the place of the accident, but a cloud of a combustible gas-air mixture may develop, which will ignite at some distance depending on wind velocity. In order to avoid unnecessarily pessimistic approaches, geographical information can be used in addition to local weather statistics. Geographical information systems provide map material for sites, roads, rail and rivers on a computer. This information can be used to find frequencies of damage based on numerical integration or on Monte Carlo simulation. A probabilistic model has been developed. It is based on: - A joint probability density function for wind direction and wind speed, which has been estimated from local weather statistics, - Frequency of hazards for neighboring plants and various types of traffic, - Statistics on the amounts and types of explosive materials, - The model has been implemented using one numerical integrations method and two variants of Monte Carlo method. Data has been collected and applied for a nuclear power plant in Northern Germany as an example. The method, however, can be used for any type of plant subject to external explosion hazards. In its present form, it makes use of design criteria specific for nuclear power plants, but these could be replaced by different criteria. (orig.)

  7. Frequency of damage by external hazards based on geographical information

    International Nuclear Information System (INIS)

    Becker, G.; Camarinopoulos, A.; Karali, T.; Camarinopoulos, L.; Schubert, B.

    2013-01-01

    External explosions can significantly contribute to risk of damage for industrial plants. External explosions may origin from other plants in the neighborhood, which store and operate with explosive substances, or from transport of such substances on road, rail, or water. In all cases, some accident is a necessary condition for a hazard. Another probabilistic element is the probability of ignition. If transport causes the explosion, the location of the accident will influence the consequences. If deflagration is involved, ignition will not necessarily occur at the place of the accident, but a cloud of a combustible gas-air mixture may develop, which will ignite at some distance depending on wind velocity. In order to avoid unnecessarily pessimistic approaches, geographical information can be used in addition to local weather statistics. Geographical information systems provide map material for sites, roads, rail and rivers on a computer. This information can be used to find frequencies of damage based on numerical integration or on Monte Carlo simulation. A probabilistic model has been developed. It is based on: - A joint probability density function for wind direction and wind speed, which has been estimated from local weather statistics, - Frequency of hazards for neighboring plants and various types of traffic, - Statistics on the amounts and types of explosive materials, - The model has been implemented using one numerical integrations method and two variants of Monte Carlo method. Data has been collected and applied for a nuclear power plant in Northern Germany as an example. The method, however, can be used for any type of plant subject to external explosion hazards. In its present form, it makes use of design criteria specific for nuclear power plants, but these could be replaced by different criteria. (orig.)

  8. Summary and conclusions of the specialist meeting on severe accident management programme development

    International Nuclear Information System (INIS)

    1992-01-01

    The CSNI Specialist meeting on severe accident management programme development was held in Rome and about seventy experts from thirteen countries attended the meeting. A total of 27 papers were presented in four sessions, covering specific aspects of accident management programme development. It purposely focused on the programmatic aspects of accident management rather than on some of the more complex technical issues associated with accident management strategies. Some of the major observations and conclusions from the meeting are that severe accident management is the ultimate part of the defense in depth concept within the plant. It is function and success oriented, not event oriented, as the aim is to prevent or minimize consequences of severe accidents. There is no guarantee it will always be successful but experts agree that it can reduce the risks significantly. It has to be exercised and the importance of emergency drills has been underlined. The basic structure and major elements of accident management programmes appear to be similar among OECD member countries. Dealing with significant phenomenological uncertainties in establishing accident management programmes continues to be an important issue, especially in confirming the appropriateness of specific accident management strategies

  9. Waste Issues Associated with the Safe Movement of Hazardous Chemicals

    International Nuclear Information System (INIS)

    Dare, J. H.; Cournoyer, M. E.

    2002-01-01

    Moving hazardous chemicals presents the risk of exposure for workers engaged in the activity and others that might be in the immediate area. Adverse affects are specific to the chemicals and can range from minor skin, eye, or mucous membrane irritation, to burns, respiratory distress, nervous system dysfunction, or even death. A case study is presented where in the interest of waste minimization; original shipping packaging was removed from a glass bottle of nitric acid, while moving corrosive liquid through a security protocol into a Radiological Control Area (RCA). During the transfer, the glass bottle broke. The resulting release of nitric acid possibly exposed 12 employees with one employee being admitted overnight at a hospital for observation. This is a clear example of administrative controls to reduce the generation of suspect radioactive waste being implemented at the expense of employee health. As a result of this event, material handling procedures that assure the safe movement of hazardous chemicals through a security protocol into a radiological control area were developed. Specifically, hazardous material must be transferred using original shipping containers and packaging. While this represents the potential to increase the generation of suspect radioactive waste in a radiological controlled area, arguments are presented that justify this change. Security protocols for accidental releases are also discussed. In summary, the 12th rule of ''Green Chemistry'' (Inherently Safer Chemistry for Accident Prevention) should be followed: the form of a substance used in a chemical process (Movement of Hazardous Chemicals) should be chosen to minimize the potential for chemical accidents, including releases

  10. Waste Issues Associated with the Safe Movement of Hazardous Chemicals

    Energy Technology Data Exchange (ETDEWEB)

    Dare, J. H.; Cournoyer, M. E.

    2002-02-26

    Moving hazardous chemicals presents the risk of exposure for workers engaged in the activity and others that might be in the immediate area. Adverse affects are specific to the chemicals and can range from minor skin, eye, or mucous membrane irritation, to burns, respiratory distress, nervous system dysfunction, or even death. A case study is presented where in the interest of waste minimization; original shipping packaging was removed from a glass bottle of nitric acid, while moving corrosive liquid through a security protocol into a Radiological Control Area (RCA). During the transfer, the glass bottle broke. The resulting release of nitric acid possibly exposed 12 employees with one employee being admitted overnight at a hospital for observation. This is a clear example of administrative controls to reduce the generation of suspect radioactive waste being implemented at the expense of employee health. As a result of this event, material handling procedures that assure the safe movement of hazardous chemicals through a security protocol into a radiological control area were developed. Specifically, hazardous material must be transferred using original shipping containers and packaging. While this represents the potential to increase the generation of suspect radioactive waste in a radiological controlled area, arguments are presented that justify this change. Security protocols for accidental releases are also discussed. In summary, the 12th rule of ''Green Chemistry'' (Inherently Safer Chemistry for Accident Prevention) should be followed: the form of a substance used in a chemical process (Movement of Hazardous Chemicals) should be chosen to minimize the potential for chemical accidents, including releases.

  11. User's guide for the KBERT 1.0 code: For the knowledge-based estimation of hazards of radioactive material releases from DOE nuclear facilities

    International Nuclear Information System (INIS)

    Browitt, D.S.; Washington, K.E.; Powers, D.A.

    1995-07-01

    The possibility of worker exposure to radioactive materials during accidents at nuclear facilities is a principal concern of the DOE. The KBERT software has been developed at Sandia National Laboratories under DOE support to address this issue by assisting in the estimation of risks posed by accidents at chemical and nuclear facilities. KBERT is an acronym for Knowledge-Based system for Estimating hazards of Radioactive material release Transients. The current prototype version of KBERT focuses on calculation of doses and consequences to in-facility workers due to accidental releases of radioactivity. This report gives detailed instructions on how a user who is familiar with the design, layout and potential hazards of a facility can use KBERT to assess the risks to workers in that facility. KBERT is a tool that allows a user to simulate possible accidents and observe the predicted consequences. Potential applications of KBERT include the evaluation of the efficacy of evacuation practices, worker shielding, personal protection equipment and the containment of hazardous materials

  12. Individual risk evaluation and interventions for mitigation in the transportation of hazardous goods: a case study

    Directory of Open Access Journals (Sweden)

    Rada Elena Cristina

    2017-01-01

    Full Text Available The transport of hazardous substances is an economic activity essential for goods’ transference chain. However, the risk in transporting hazardous materials is related to the occur of accidents causing environmental damages and public health dangerous consequences. A quite recent Italian example is the Viareggio accident (2010, which involved a train with tank cars containing liquefied petroleum gas (LPG which caused more than thirty deaths. This paper describes the safety state in the Varese district (an area of northern Italy with a very high population density and industrial activities, with the aim at comparing the current situation (considering the risks due to the transportation of hazardous materials on the main motorways and main national roads with a potential scenario that introduces a few mitigating interventions, such as a partial conversion from road haulage to rail transport. This comparison can be accomplished by developing the existing intermodal platforms and implementing new ones in strategic areas.

  13. Road traffic accident: The neglected health problem in Amhara ...

    African Journals Online (AJOL)

    Background: Road traffic accident is a major but neglected public health challenge. There is a paucity of published data on road traffic crashes in Amhara National Regional State. Objective: This study attempts to describe the main causes and consequences of road traffic accidents in the Amhara Region. Methods: This ...

  14. Risk assessment for the transportation of hazardous waste and hazardous waste components of low-level mixed waste and transuranic waste for the U.S. Department of Energy waste management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    Lazaro, M.A.; Policastro, A.J.; Hartmann, H.M.

    1995-04-01

    This report, a supplement to Appendix E (Transportation Risk) of the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS), provides additional information supporting the accident data for chemical risk assessment and health risk methodology described in that appendix (Part II), as well as providing the uncertainty analysis and on-site risk calculations. This report focuses on hazardous material truck accident rates, release probabilities, and release quantities; provides the toxicological values derived for each hazardous chemical assessed in the WM PEIS and further details on the derivation of health criteria; describes the method used in the transportation risk assessments to address potential additivity of health effects from simultaneous exposure to several chemicals and the method used to address transportation risks for maximally exposed individuals; presents an expanded discussion of the uncertainty associated with transportation risk calculations; and includes the results of the on-site transportation risk analysis. In addition, two addenda are provided to detail the risk assessments conducted for the hazardous components of low-level mixed waste (Addendum I) and transuranic waste (Addendum II)

  15. A Tool for Safety Officers Investigating " simple" Accidents

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2010-01-01

    Most workplace accidents that happen in enterprises are simple and seldom result in serious injuries. Very often these kinds of workplace accidents are not investigated, and if they are, then the investigation is very brief, with comments such as that it was the victim’s own fault or just...... accidents normally caused by apparent banalities occur much more frequently and with a higher rate of fatalities, disablements and other serious injuries than the ostensibly most dangerous kinds of accidents. In 1999 a practical tool for use by safety officers was developed; this tool is based...... on the investigation methods applied in major accidents, but comprises a simpler and more user-friendly presentation. The tool involves three steps: Mapping the facts, analysing the events, and developing preventive solutions. Practical application of the tool has shown that it affords managers and workers...

  16. Quality function deployment applied to local traffic accident reduction.

    Science.gov (United States)

    Sohn, S Y

    1999-11-01

    One of the major tasks of police stations is the management of local road traffic accidents. Proper prevention policy which reflects the local accident characteristics could immensely help individual police stations in decreasing various severity levels of road traffic accidents. In order to relate accident variation to local driving environmental characteristics, we use both cluster analysis and Poisson regression. The fitted result at the level of each cluster for each type of accident severity is utilized as an input to quality function deployment. Quality function deployment (QFD) has been applied to customer satisfaction in various industrial quality improvement settings, where several types of customer requirements are related to various control factors. We show how QFD enables one to set priorities on various road accident control policies to which each police station has to pay particular attention.

  17. The risk of accident in nuclear power plants - Quotes and questions. National debate on energy transition. Taking the risk of nuclear accident into account. Note to the 'scenarios' subgroup of the group of experts

    International Nuclear Information System (INIS)

    Laponche, Bernard

    2013-01-01

    After an overview of the production of electricity from nuclear energy and of its risks, the author discusses the issue of nuclear safety by distinguishing the different points of view, by describing the different levels between a severe and a major accident, and by recalling the statements made by the ASN and the IRSN on this issue. He describes the various reasons and consequences of accidents: types of accidents which could result in a core fusion, the containment failure as the major accident. He discusses the questions and comments about major issues like: strength of reactor vessels, hydrogen explosion, water vapour explosion, corium crossing the concrete sill plate, corium recovery, MOX as an aggravating situation for safety. In the last part, the author discusses the global assessment of a risk of a nuclear accident: probabilities and occurrences, significant accidents on PWRs, premonitory analysis, demonstration of nuclear safety

  18. Hazardous-environment problems: Mobile robots to the rescue

    International Nuclear Information System (INIS)

    Meieran, H.B.

    1992-01-01

    This paper presents a rationale for employing a spectrum of similar mobile robots to conduct appropriate common missions for the following five hazardous-environment issues: (1) dismantlement of nuclear weapons; (2) environmental restoration and waste management of US Department of Energy weapons sites; (3) operations in nuclear power plants and other facilities; (4) waste chemical site remediation and cleanup activities; and (5) assistance in handling toxic chemical/radiation accidents. Mobile robots have been developed for several hazardous-environment industries, the most visible ones being construction/excavation/tunneling, explosive ordnance/bomb disposal (EOD), fire-fighting, military operations, mining, nuclear, and security. A summary of the range of functions that mobile robots are currently capable of conducting is presented

  19. Oxygen deficiency at CERN: Hazards, risks & mitigation measures

    CERN Multimedia

    CERN. Geneva

    2016-01-01

    Compressed and liquified gases are used at many places at CERN. If they are introduced to the atmosphere, they can present an oxygen deficiency hazard (ODH) and lead to reduced abilities, unconsciousness or even death. The CERN method for ODH risk assessments is done on a case-by-case basis as each situation is unique. It is crucial to make sure the personnel can evacuate safely in case of an ODH situation. My talk will explain human reactions to reduced oxygen levels and I will give some practical examples on how one can assess and control the hazards from a possible oxygen deficient atmosphere. Some real accidents involving oxygen deficiency will also be mentioned.

  20. Water-molten uranium hazard analysis. Final report. LATA report No. 92

    International Nuclear Information System (INIS)

    Hughes, P.S.; Rigdon, L.D.; Donham, B.J.

    1979-01-01

    The hazard potential of cooling water leakage into the crucible of molten uranium in the MARS laser isotope separation experiment was investigated. A vapor-phase explosion is highly unlikely in any of the scenarios defined for MARS. For the operating basis accident, the gas pressure transient experienced by the vessel wall is 544 psia peak with a duration of 200 μs, and the peak hoop stress is about 20,000 psi in a 0.5-in. wall. Design and procedural recommendations are given for reducing the hazard

  1. Factors contributing to young moped rider accidents in Denmark

    DEFF Research Database (Denmark)

    Møller, Mette; Haustein, Sonja

    2016-01-01

    Young road users still constitute a high-risk group with regard to road traffic accidents. The crash rate of a moped is four times greater than that of a motorcycle, and the likelihood of being injured in a road traffic accident is 10-20 times higher among moped riders compared to car drivers...... was made between accident factors related to (1) the road and its surroundings, (2) the vehicle, and (3) the reported behaviour and condition of the road user. Thirteen accident factors were identified with the majority concerning the reported behaviour and condition of the road user. The average number...... of accident factors assigned per accident was 2.7. Riding speed was assigned in 45% of the accidents which made it the most frequently assigned factor on the part of the moped rider followed by attention errors (42%), a tuned up moped (29%) and position on the road (14%). For the other parties involved...

  2. [Accidents on Iceland's most dangerous roads].

    Science.gov (United States)

    Bjarnason, Thóroddur; Arnarsson, Sveinn

    2012-02-01

    The objective of this paper was to identify the most dangerous segments of the Icelandic road system in terms of the number of accidents pr km and the rate of accidents pr million km travelled. First to identify the segments where the number of accidents is highest and where the risk of the individual traveller is the greatest. Second to evaluate if the association between the number and the rate of accidents is positive or negative. Third to identify the road segments that are the most dangerous in the sense of many accidents and great risk to individual travellers. Main roads outside urban centers were divided into 45 segments that were on average 78 km in length. Infrequently travelled roads and roads within urban centers were omitted. Information on the length of roads, traffic density and number of accidents was used to calculate the number of accidents per km and the rate of accidents per million km travelled. The correlation between the number and rate of accidents was calculated and the most dangerous road segments were identified by the average rank order on both dimensions. Most accidents pr km occurred on the main roads to and from the capital region, but also east towards Hvolsvöllur, north towards Akureyri and in the Mideast region of the country. The rate of accidents pr million km travelled was highest in the northeast region, in northern Snæfellsnes and in the Westfjords. The most dangerous roads on both dimensions were in Mideast, northern Westfjords, in the north between Blönduós and Akureyri and in northern Snæfellsnes. Most accidents pr km occurred on roads with a low accident rate pr million km travelled. It is therefore possible to reduce accidents the most by increasing road safety where it is already the greatest but that would however increase inequalities in road safety. Policy development in transportation is therefore in part a question of priorities in healthcare. Individual equality in safety and health are not always fully

  3. Analysis of Aircraft Crash Accident for WETF

    International Nuclear Information System (INIS)

    Jordan, Hans

    2001-01-01

    This report applies the methodology of DOE-STD-3014-96, ''Accident Analysis for Aircraft Crash into Hazardous Facilities'', to the Weapons Engineering Tritium Facility (WETF) at LANL. Straightforward application of that methodology shows that including local helicopter flights with those of all other aircraft with potential to impact the facility poses a facility impact risk slightly in excess of the DOE standard's threshold--10 -6 impacts per year. It is also shown that helicopters can penetrate the facility if their engines impact that facility's roof. However, a refinement of the helicopter impact analysis shows that penetration risk of the facility for all aircraft lies below the DOE standard's threshold. By that standard, therefore, the potential for release of hazardous material from the facility as a result of an aircraft crashing into the facility is negligible and need not be analyzed further

  4. Disposal of hazardous wastes

    International Nuclear Information System (INIS)

    Barnhart, B.J.

    1978-01-01

    The Fifth Life Sciences Symposium entitled Hazardous Solid Wastes and Their Disposal on October 12 through 14, 1977 was summarized. The topic was the passage of the National Resources Conservation and Recovery Act of 1976 will force some type of action on all hazardous solid wastes. Some major points covered were: the formulation of a definition of a hazardous solid waste, assessment of long-term risk, list of specific materials or general criteria to specify the wastes of concern, Bioethics, sources of hazardous waste, industrial and agricultural wastes, coal wastes, radioactive wastes, and disposal of wastes

  5. Air ingress accidents in tokamaks

    International Nuclear Information System (INIS)

    Jones, A.V.; Roccok, P.

    1989-01-01

    Accidents are considered consisting in a breach in the vacuum wall of a fusion reactor, the ingress of air into the torus and the mobilization and expulsion of activated eroded-sputtered material. Previous evaluations on NET, assuming bare plasma-facing components, have been reviewed and new estimates of the rate of material discharge and of the total fraction of discharged material are calculated, including resettlement processes. The case of graphite-tiled walls, without and with combustion, is also examined. Radiological evaluations are then performed to assess the hazard posed by the discharged material both within the NET building and outside it. (author). 14 refs.; 4 figs.; 3 tabs

  6. URBAN TRAFFIC ACCIDENT ANALYSIS BY USING GEOGRAPHIC INFORMATION SYSTEM

    Directory of Open Access Journals (Sweden)

    Meltem SAPLIOĞLU

    2006-03-01

    Full Text Available In recent years, traffic accidents that cause more social and economic losses than that of natural disasters,have become a national problem in Turkey. To solve this problem and to reduce the casualties, road safety programs are tried to be developed. It is necessary to develop the most effective measures with low investment cost due to limited budgets allocated to such road safety programs. The most important program is to determine dangerous locations of traffic accidents and to improve these sections from the road safety view point. New Technologies are driving a cycle of continuous improvement that causes rapid changes in the traffic engineering and any engineering services within it. It is obvious that this developed services will be the potential for forward-thinking engineering studies to take a more influence role. In this study, Geographic Information System (GIS was used to identify the hazardous locations of traffic accidents in Isparta. Isparta city map was digitized by using Arcinfo 7.21. Traffic accident reports occurred between 1998-2002 were obtained from Directory of Isparta Traffic Region and had been used to form the database. Topology was set up by using Crash Diagrams and Geographic Position Reference Systems. Tables are formed according to the obtained results and interpreted.

  7. Automating Risk Assessments of Hazardous Material Shipments for Transportation Routes and Mode Selection

    International Nuclear Information System (INIS)

    Dolphin, Barbara H.; Richins, William D.; Novascone, Stephen R.

    2010-01-01

    The METEOR project at Idaho National Laboratory (INL) successfully addresses the difficult problem in risk assessment analyses of combining the results from bounding deterministic simulation results with probabilistic (Monte Carlo) risk assessment techniques. This paper describes a software suite designed to perform sensitivity and cost/benefit analyses on selected transportation routes and vehicles to minimize risk associated with the shipment of hazardous materials. METEOR uses Monte Carlo techniques to estimate the probability of an accidental release of a hazardous substance along a proposed transportation route. A METEOR user selects the mode of transportation, origin and destination points, and charts the route using interactive graphics. Inputs to METEOR (many selections built in) include crash rates for the specific aircraft, soil/rock type and population densities over the proposed route, and bounding limits for potential accident types (velocity, temperature, etc.). New vehicle, materials, and location data are added when available. If the risk estimates are unacceptable, the risks associated with alternate transportation modes or routes can be quickly evaluated and compared. Systematic optimizing methods will provide the user with the route and vehicle selection identified with the lowest risk of hazardous material release. The effects of a selected range of potential accidents such as vehicle impact, fire, fuel explosions, excessive containment pressure, flooding, etc. are evaluated primarily using hydrocodes capable of accurately simulating the material response of critical containment components. Bounding conditions that represent credible accidents (i.e; for an impact event, velocity, orientations, and soil conditions) are used as input parameters to the hydrocode models yielding correlation functions relating accident parameters to component damage. The Monte Carlo algorithms use random number generators to make selections at the various decision

  8. Identification of NPP accidents using support vector classification

    Energy Technology Data Exchange (ETDEWEB)

    Back, Ju Hyun; Yoo, Kwae Hwan; Na, Man Gyun [Chosun University, Gwangju (Korea, Republic of)

    2016-10-15

    In case of the accidents that happens in a nuclear power plants (NPPs), it is very important to identify its accidents for the operator. Therefore, in order to effectively manage the accidents, the initial short time trends of major parameters have to be observed and NPP accidents have to accurately be identified to provide its information to operators and technicians. In this regard, the objective of this study is to identify the accidents when the accidents happen in NPPs. In this study, we applied the support vector classification (SVC) model to classify the initiating events of critical accidents such as loss of coolant accidents (LOCA), total loss of feedwater (TLOFW), station blackout (SBO), and steam generator tube rupture (SGTR). Input variables were used as the initial integral value of the signal measured in the reactor coolant system (RCS), steam generator, and containment vessel after reactor trip. The proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. In this study, the proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. We used an initial integral value of the simulated sensor signals to identify the NPP accidents. The training data was used to train the SVC model. And, the trained model was confirmed using the test data. As a result, it was known that it can accurately classify five events.

  9. Control Analysis of Hazards Potential in Crude Distiller Unit III PT. Pertamina (Persero) Refinery Unit III Plaju Tahun 2011

    OpenAIRE

    Matariani, Ade; Hasyim, Hamzah; Faisya, Achmad Fickry

    2012-01-01

    Background: Activities in CDU III are very risk to any hazards potential; because of that hazards potential is much needed in controlling the hazards potential to decrease the accidents and occupational diseases. The aim of this study was to analyze the controlling of hazards potential in CDU III PT. Pertamina (Persero) RU III Plaju in 2011. Method: This study was a qualitative study. The methods of data collection were using in-depth interview and observation. The total of informants in this...

  10. Development of a Probabilistic Tsunami Hazard Analysis Method and Application to an NPP in Korea

    International Nuclear Information System (INIS)

    Kim, M. K.; Choi, Ik

    2012-01-01

    A methodology of tsunami PSA was developed in this study. A tsunami PSA consists of tsunami hazard analysis, tsunami fragility analysis and system analysis. In the case of tsunami hazard analysis, evaluation of tsunami return period is a major task. For the evaluation of tsunami return period was evaluated with empirical method using historical tsunami record and tidal gauge record. For the performing a tsunami fragility analysis, procedure of tsunami fragility analysis was established and target equipment and structures for investigation of tsunami fragility assessment were selected. A sample fragility calculation was performed for the equipment in a Nuclear Power Plant. For the system analysis, accident sequence of tsunami event was developed according to the tsunami run-up and draw down, and tsunami induced core damage frequency (CDF) is determined. For the application to the real nuclear power plant, the Ulchin 56 NPP which is located on the east coast of Korean peninsula was selected. Through this study, whole tsunami PSA (Probabilistic Safety Assessment) working procedure was established and an example calculation was performed for one nuclear power plant in Korea

  11. Final Hazard Classification and Auditable Safety Analysis for the 105-F Building Interim Safe Storage Project

    International Nuclear Information System (INIS)

    Rodovsky, T.J.; Bond, S.L.

    1998-07-01

    The auditable safety analysis (ASA) documents the authorization basis for the partial decommissioning and facility modifications to place the 105-F Building into interim safe storage (ISS). Placement into the ISS is consistent with the preferred alternative identified in the Record of Decision (58 FR). Modifications will reduce the potential for release and worker exposure to hazardous and radioactive materials, as well as lower surveillance and maintenance (S ampersand M) costs. This analysis includes the following: A description of the activities to be performed in the course of the 105-F Building ISS Project. An assessment of the inventory of radioactive and other hazardous materials within the 105-F Building. Identification of the hazards associated with the activities of the 105-F Building ISS Project. Identification of internally and externally initiated accident scenarios with the potential to produce significant local or offsite consequences during the 105-F Building ISS Project. Bounding evaluation of the consequences of the potentially significant accident scenarios. Hazard classification based on the bounding consequence evaluation. Associated safety function and controls, including commitments. Radiological and other employee safety and health considerations

  12. Flood control construction of Shidao Bay nuclear power plant and safety analysis for hypothetical accident of HTR-PM

    International Nuclear Information System (INIS)

    Chen Yongrong; Zhang Keke; Zhu Li

    2014-01-01

    A series of events triggered by tsunami eventually led to the Fukushima nuclear accident. For drawing lessons from the nuclear accident and applying to Shidao Bay nuclear power plant flood control construction, we compare with the state laws and regulations, and prove the design of Shidao Bay nuclear power plant flood construction. Through introducing the history of domestic tsunamis and the national researches before and after the Fukushima nuclear accident, we expound the tsunami hazards of Shidao Bay nuclear power plant. In addition, in order to verify the safety of HTR-PM, we anticipate the contingent accidents after ''superposition event of earthquake and extreme flood'', and analyse the abilities and measures of HTR-PM to deal with these beyond design basis accidents (BDBA). (author)

  13. Postulated accidents

    International Nuclear Information System (INIS)

    Ullrich, W.

    1980-01-01

    This lecture on 'Postulated Accidents' is the first of a series of lectures on the dynamic and transient behaviour of nuclear power plants, especially pressurized water reactors. The main points covered will be: Reactivity Accidents, Transients (Intact Loop) and Loss of Cooland Accidents (LOCA) including small leak. This lecture will discuss the accident analysis in general, the definition of the various operational phases, the accident classification, and, as an example, an accident sequence analysis on the basis of 'Postulated Accidents'. (orig./RW)

  14. Progress in Addressing DNFSB Recommendation 2002-1 Issues: Improving Accident Analysis Software Applications

    International Nuclear Information System (INIS)

    VINCENT, ANDREW

    2005-01-01

    Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1 (''Quality Assurance for Safety-Related Software'') identified a number of quality assurance issues on the use of software in Department of Energy (DOE) facilities for analyzing hazards, and designing and operating controls to prevent or mitigate potential accidents. Over the last year, DOE has begun several processes and programs as part of the Implementation Plan commitments, and in particular, has made significant progress in addressing several sets of issues particularly important in the application of software for performing hazard and accident analysis. The work discussed here demonstrates that through these actions, Software Quality Assurance (SQA) guidance and software tools are available that can be used to improve resulting safety analysis. Specifically, five of the primary actions corresponding to the commitments made in the Implementation Plan to Recommendation 2002-1 are identified and discussed in this paper. Included are the web-based DOE SQA Knowledge Portal and the Central Registry, guidance and gap analysis reports, electronic bulletin board and discussion forum, and a DOE safety software guide. These SQA products can benefit DOE safety contractors in the development of hazard and accident analysis by precluding inappropriate software applications and utilizing best practices when incorporating software results to safety basis documentation. The improvement actions discussed here mark a beginning to establishing stronger, standard-compliant programs, practices, and processes in SQA among safety software users, managers, and reviewers throughout the DOE Complex. Additional effort is needed, however, particularly in: (1) processes to add new software applications to the DOE Safety Software Toolbox; (2) improving the effectiveness of software issue communication; and (3) promoting a safety software quality assurance culture

  15. Study on the experimental VHTR safety with analysis for a hypothetical rapid depressurization accident

    International Nuclear Information System (INIS)

    Mitake, S.; Suzuki, K.; Ohno, T.; Okada, T.

    1982-01-01

    A hypothetical rapid depressurization accident of the experimental VHTR has been analyzed, including all phenomena in the accident, from its initiating depressurization of the coolant to consequential radiological hazard. Based on reliability analysis of the engineered safety features, all possible sequences, in which the safety systems are in success or in failure, have been investigated with event tree analysis. The result shows the inherent safety characteristics of the reactor and the effectiveness of the engineered safety features. And through the analysis, it has been indicated that further investigations on some phenomena in the accident, e.g., air ingress by natural circulation flow and fission product transport in the plant, will bring forth more reasonable and sufficient safety of the reactor

  16. Colloquium / Preparation for nuclear post-accident. Citizens and local authorities involvement in major risks governance - proceedings

    International Nuclear Information System (INIS)

    Pascal, Michel; Villers, Anita; Sene, Monique; Godin, Francois; Quilichini, Jean-Michel; Rollinger, Francois; Delalonde, Jean-Claude; Mehl-Auget, Isabelle; Autret, Jean-Claude; Heriard Dubreuil, Gilles; Petitfrere, Michael; Lochard, Jacques; Demet, Michel; Boucherie, Jean-Claude; Calafat, Alexis; Sommade, Christian; Villain, Alain; Ragazzo, Romeo; Rengot, Marielle; Sename, Jean; Thellier, Yvette; Tremelet, David; Olszewski, Richard; Fournier, Nicolas

    2009-12-01

    During 40 years, France has chosen nuclear energy as main energy source for power generation. Today, nuclear energy covers 80% of the French electricity needs. For this reason, in France, each inhabitant lives at less than 200 km of a nuclear power plant. The September 11, 2001 terror attack has led to reconsider the nuclear risk in terms of security. In 2005, the French nuclear safety authority (ASN) has been entrusted with the preparation of a nuclear post-accident management study. This study has been mainly based on the experience feedback of the Chernobyl accident and on the dialogue with different actors of the French territory: the local authorities, the habitants, the associations and the health, environment and education actors. This colloquium represents the opening act of the joint elaboration of the management of a potential nuclear accident at the region scale. The colloquium was organized around 5 round tables: 1 - Did the nuclear safety transparency law change the situation?; 2 - Examples of pluralistic dialogues: the long-term management of a nuclear accident; 3 - How to encourage the necessary skills development of citizens? 4 - Regional development strategies in terms of nuclear risks management (incidents, effluents, wastes, transports..); 5 - New territory liabilities and citizens' legitimate aspiration in terms of health/environment: building something together. This document is the proceedings of this colloquium. It reports the exchanges between the participants

  17. Diving accidents in sports divers in Orkney waters.

    Science.gov (United States)

    Trevett, A J; Forbes, R; Rae, C K; Sheehan, C; Ross, J; Watt, S J; Stephenson, R

    2001-12-01

    Scapa Flow in Orkney is one of the major world centres for wreck diving. Because of the geography of Orkney and the nature of the diving, it is possible to make relatively accurate estimates of the number of dives taking place. The denominator of dive activity allows the unusual opportunity of precise calculation of accident rates. In 1999, one in every 178 sports divers visiting Orkney was involved in a significant accident, in 2000 the figure was one in 102. Some of these accidents appear to have been predictable and could be avoided by better education and preparation of visiting divers.

  18. Development of instrumentation systems for severe accidents. 4. New accident tolerant in-containment pressure transducer for containment pressure monitoring system

    International Nuclear Information System (INIS)

    Oba, Masato; Teruya, Kuniyuki; Yoshitsugu, Makoto; Ikeuchi, Takeshi

    2015-01-01

    The accident at Tokyo Electric Power Company's Fukushima Dai-ichi Nuclear Power Plant (TF-1 accident) caused severe situations and resulted in a difficulty in measuring important parameters for monitoring plant conditions. Therefore, we have studied the TF-1 accident to select the important parameters that should be monitored at the severe accident and are developing the Severe Accident Instrumentations and Monitoring Systems that could measure the parameters in severe accident conditions. Mitsubishi Heavy Industries, LTD (MHI) developed a new accident tolerant containment pressure monitoring system and demonstrated that the monitoring system could endure extremely harsh environmental conditions that envelop severe accident environmental conditions inside a containment such as maximum operating temperature of up to 300degC and total integrated dose (TID) of 1 MGy gamma. The new containment pressure monitoring system comprises of a strain gage type pressure transducer and a mineral insulated (MI) cable with ceramic connectors, which are located in the containment, and a strain measuring amplifier located outside the containment. Less thermal and radiation degradation is achieved because of minimizing use of organic materials for in-containment equipment such as the transducer and connectors. Several tests were performed to demonstrate the performance and capability of the in-containment equipment under severe accident environmental conditions and the major steps in this testing were run in the following test sequences: (1) the baseline functional tests (e.g., repeatability, non-linearity, hysteresis, and so on) under normal conditions, (2) accident radiation testing, (3) seismic testing, and (4) steam/temperature test exposed to simulated severe accident environmental conditions. The test results demonstrate that the new pressure transducer can endure the simulated severe accident conditions. (author)

  19. In-depth investigation of escalator riding accidents in heavy capacity MRT stations.

    Science.gov (United States)

    Chi, Chia-Fen; Chang, Tin-Chang; Tsou, Chi-Lin

    2006-07-01

    In 2000, the accident rate for escalator riding was about 0.815 accidents per million passenger trips through Taipei Metro Rapid Transit (MRT) heavy capacity stations. In order to reduce the probability and severity of escalator riding accidents and enhance the safety of passengers, the Drury and Brill model [Drury, C.G., Brill, M., 1983. Human factors in consumer product accident investigation. Hum. Factors 25 (3), 329-342] for in-depth investigation was adopted to analyze the 194 escalator riding accidents in terms of victim, task, product and environment. Prevention measures have been developed based on the major causes of accidents and other related contributing factors. The results from the analysis indicated that the majority of the escalator riding accidents was caused by passengers' carrying out other tasks (38 cases, including carrying luggage 24 cases, looking after accompany persons 9 cases, and 5 others), loss of balance (26 cases, 13.4%), not holding the handrail (20 cases, 10.3%), unhealthy passengers (18 cases, 9.3%), followed by people struck by other passenger (16 cases, 8.2%). For female passengers aged 15-64 years, their rushing for trains accidents could have been prevented by wearing safer footwear or by appropriate signing being provided indicating the location and traveling direction of escalators. Female passengers aged 65 years and above whose accidents were caused by loss of balance, should be encouraged to take the elevator instead. To prevent entrapment injuries, following a stricter design code can be most effective. Further in-depth accident investigation is suggested to cover the activity of the victim prior to the accident, any involved product, the location of the accident on the escalator, any medical treatment, what went wrong, opinion of the respondent on the causes of the accident, and personal characteristics of the passengers. Also, management must trade off productivity and safety appropriately to prevent "Organizational

  20. A study of risk evaluation methodology selection for the external hazards

    International Nuclear Information System (INIS)

    Kuramoto, Takahiro; Yamaguchi, Akira; Narumiya, Yosiyuki

    2014-01-01

    Since the accident at Fukushima Daiichi Nuclear Power Plant caused by the Great East Japan Earthquake in March 2011, there has been growing demands for assessing the effects of external hazards, including natural events, such as earthquake and tsunami, and external human behaviors, and taking actions to address those external hazards. The newly established Japanese regulatory requirements claim design considerations associated with external hazards. The primary objective of the risk assessment for external hazards is to establish countermeasures against such hazards rather than grasping the risk figures. Therefore, applying detailed risk assessment methods, such as probabilistic risk assessment (PRA), to all the external hazards is not always the most appropriate. Risk assessment methods can vary in types including qualitative evaluation, hazard analysis (analyzing hazard frequencies or their influence), and margin assessment. To resolve these issues, a process has been established that enables us to identify the external hazards in a comprehensive and systematic manner, which have potential risks leading to core damage and to select an appropriate evaluation method according to the risks associated with each of the external hazards. This paper discusses the comprehensive and systematic identification process for the external hazards which have potential risks leading to core damage, and the approaches of selecting an appropriate evaluation method for each external hazard. This paper also describes some applications of specific risk evaluation methods. (author)