WorldWideScience

Sample records for accident data

  1. Three Mile Island Accident Data

    National Oceanic and Atmospheric Administration, Department of Commerce — Three Mile Island Accident Data consists of mostly upper air and wind observations immediately following the nuclear meltdown occurring on March 28, 1979, near...

  2. Meteorological data related to the Chernobyl accident

    This report presents a detailed technical description of the JRC-Ispra comprehensive collection of meteorological information related to the Chernobyl accident and attempts an analysis of the data in order to perform an initial checking of their quality and facilitate a suitable and compact way of display

  3. On the application of near accident data to risk analysis of major accidents

    Major accidents are low frequency high consequence events which are not well supported by conventional statistical methods due to data scarcity. In the absence or shortage of major accident direct data, the use of partially related data of near accidentsaccident precursor data – has drawn much attention. In the present work, a methodology has been proposed based on hierarchical Bayesian analysis and accident precursor data to risk analysis of major accidents. While hierarchical Bayesian analysis facilitates incorporation of generic data into the analysis, the dependency and interaction between accident and near accident data can be encoded via a multinomial likelihood function. We applied the proposed methodology to risk analysis of offshore blowouts and demonstrated its outperformance compared to conventional approaches. - Highlights: • Probabilistic risk analysis is applied to model major accidents. • Two-stage Bayesian updating is used to generate informative distributions. • Accident precursor data are used to develop likelihood function. • A multinomial likelihood function is introduced to model dependencies among data

  4. Determination of accident related release data

    For accident safety analyses, for the assessment of potential radiological consequences, for the review of current requirements of the Transport Regulations and for their possible further development as well as for the demonstration that radioactive materials such as LDM candidate material fulfil the regulatory requirements reliable release data following mechanical impact are required. This is definitely one of the demanding issues in the field of transport safety of radioactive materials. In this context special attention has to be paid to radioactive wastes immobilised in brittle materials, e.g. cement/concrete, glass, ceramics or other brittle materials such as fresh and spent fuel. In this presentation we report on a long-term experimental program aiming at improving the general physical understanding of the release process as well as the quantity and the quality of release data. By combining laboratory experiments using small scale test specimens with a few key scaling experiments with large scale test objects significant progress was achieved to meet this objective. The laboratory equipment enables the in-situ determination of the amount and aerodynamic size distribution of the airborne particles generated upon impact of the test specimen on a hard target. Impact energies cover the range experienced in transport accidents including aircraft accidents. The well defined experimental boundary conditions and the good reproducibility of the experimental procedure allowed for systematic studies to exactly measure the amount and aerodynamic size distribution of the airborne release and to quantify its dependence on relevant parameters such as energy input, material properties, and specimen geometry. The experimental program was performed within the scope of various national and international (e.g. EU-funded) projects. The small scale experiments with brittle materials revealed a pronounced universality of the airborne release in view of the material properties and

  5. Explaining and predicting workplace accidents using data-mining techniques

    Rivas, T., E-mail: trivas@uvigo.e [Dpto. Ingenieria de los Recursos Naturales y Medio Ambiente, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain); Paz, M., E-mail: mpaz.minas@gmail.co [Dpto. Ingenieria de los Recursos Naturales y Medio Ambiente, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain); Martin, J.E., E-mail: jmartin@cippinternacional.co [CIPP International, S.L. Parque Tecnologico de Asturias, Parcela 43, Oficina 11, 33428 Llanera (Spain); Matias, J.M., E-mail: jmmatias@uvigo.e [Dpto. Estadistica e Investigacion Operativa, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain); Garcia, J.F., E-mail: jgarcia@cippinternacional.co [CIPP International, S.L. Parque Tecnologico de Asturias, Parcela 43, Oficina 11, 33428 Llanera (Spain); Taboada, J., E-mail: jtaboada@uvigo.e [Dpto. Ingenieria de los Recursos Naturales y Medio Ambiente, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain)

    2011-07-15

    Current research into workplace risk is mainly conducted using conventional descriptive statistics, which, however, fail to properly identify cause-effect relationships and are unable to construct models that could predict accidents. The authors of the present study modelled incidents and accidents in two companies in the mining and construction sectors in order to identify the most important causes of accidents and develop predictive models. Data-mining techniques (decision rules, Bayesian networks, support vector machines and classification trees) were used to model accident and incident data compiled from the mining and construction sectors and obtained in interviews conducted soon after an incident/accident occurred. The results were compared with those for a classical statistical techniques (logistic regression), revealing the superiority of decision rules, classification trees and Bayesian networks in predicting and identifying the factors underlying accidents/incidents.

  6. Explaining and predicting workplace accidents using data-mining techniques

    Current research into workplace risk is mainly conducted using conventional descriptive statistics, which, however, fail to properly identify cause-effect relationships and are unable to construct models that could predict accidents. The authors of the present study modelled incidents and accidents in two companies in the mining and construction sectors in order to identify the most important causes of accidents and develop predictive models. Data-mining techniques (decision rules, Bayesian networks, support vector machines and classification trees) were used to model accident and incident data compiled from the mining and construction sectors and obtained in interviews conducted soon after an incident/accident occurred. The results were compared with those for a classical statistical techniques (logistic regression), revealing the superiority of decision rules, classification trees and Bayesian networks in predicting and identifying the factors underlying accidents/incidents.

  7. Unrecorded Accidents Detection on Highways Based on Temporal Data Mining

    Shi An

    2014-01-01

    Full Text Available Automatic traffic accident detection, especially not recorded by traffic police, is crucial to accident black spots identification and traffic safety. A new method of detecting traffic accidents is proposed based on temporal data mining, which can identify the unknown and unrecorded accidents by traffic police. Time series model was constructed using ternary numbers to reflect the state of traffic flow based on cell transmission model. In order to deal with the aftereffects of linear drift between time series and to reduce the computational cost, discrete Fourier transform was implemented to turn time series from time domain to frequency domain. The pattern of the time series when an accident happened could be recognized using the historical crash data. Then taking Euclidean distance as the similarity evaluation function, similarity data mining of the transformed time series was carried out. If the result was less than the given threshold, the two time series were similar and an accident happened probably. A numerical example was carried out and the results verified the effectiveness of the proposed method.

  8. Test Data for USEPR Severe Accident Code Validation

    J. L. Rempe

    2007-05-01

    This document identifies data that can be used for assessing various models embodied in severe accident analysis codes. Phenomena considered in this document, which were limited to those anticipated to be of interest in assessing severe accidents in the USEPR developed by AREVA, include: • Fuel Heatup and Melt Progression • Reactor Coolant System (RCS) Thermal Hydraulics • In-Vessel Molten Pool Formation and Heat Transfer • Fuel/Coolant Interactions during Relocation • Debris Heat Loads to the Vessel • Vessel Failure • Molten Core Concrete Interaction (MCCI) and Reactor Cavity Plug Failure • Melt Spreading and Coolability • Hydrogen Control Each section of this report discusses one phenomenon of interest to the USEPR. Within each section, an effort is made to describe the phenomenon and identify what data are available modeling it. As noted in this document, models in US accident analysis codes (MAAP, MELCOR, and SCDAP/RELAP5) differ. Where possible, this report identifies previous assessments that illustrate the impact of modeling differences on predicting various phenomena. Finally, recommendations regarding the status of data available for modeling USEPR severe accident phenomena are summarized.

  9. A regulatory assessment of test data for reactivity accidents

    Meyer, R.O.; Scott, H.H. [Nuclear Regulatory Commission, Washington, DC (United States); Chung, Hee M. [Argonne National Lab., IL (United States)] [and others

    1997-09-01

    An assessment is made of recent test data from France, Japan, and Russia, and of earlier test data from the U.S., in relation to the safety analysis performed for power reactors in the U.S. Considerations include mode of cladding failure, oxidation, hydriding, and pulse-width effects. From the data trend and from these considerations, it is concluded that the cladding failure threshold for fuel rods with moderate-to-high burnup is roughly 100 cal/g for BWRs and PWRs. Realistic plant calculations suggest that cladding failure would not occur for rod-ejection or rod-drop accidents and, therefore, that pellet fragmentation and enhanced fission product release from fuel pellets should not have to be considered in the safety analysis for these accidents. However, the data base is sparse and contains a lot of uncertainty.

  10. Accidents in Malaysian construction industry: statistical data and court cases.

    Chong, Heap Yih; Low, Thuan Siang

    2014-01-01

    Safety and health issues remain critical to the construction industry due to its working environment and the complexity of working practises. This research attempts to adopt 2 research approaches using statistical data and court cases to address and identify the causes and behavior underlying construction safety and health issues in Malaysia. Factual data on the period of 2000-2009 were retrieved to identify the causes and agents that contributed to health issues. Moreover, court cases were tabulated and analyzed to identify legal patterns of parties involved in construction site accidents. Approaches of this research produced consistent results and highlighted a significant reduction in the rate of accidents per construction project in Malaysia. PMID:25189753

  11. Statistical analysis of accident data associated with sea transport (data from 1994-1997). Annex 1

    This analysis is based on Lloyd's database concerning sea transport accidents for the 1994-1997 period and completes the previous analysis based on 1994 data. It gives an accurate description of the world fleet and the most severe ship accidents (total losses), as well as the frequencies of accident (in average on the 1994-1997 period the frequency of accident for cargo carrying ships is 2.57.10-3 loss /ship.year). Furthermore, an analysis has been performed on the ship casualties recorded by the Marine Accident Investigation Branch (MAIB) for UK vessels for the 1990-1996 period, this database including all accidents for which a declaration has been made to authorities (for example, the average frequency of fires derived from this analysis is 1.36.10-2 per ship.year, this occurrence corresponding to the occurrence of initiating events of fire). Concerning fire accidents aboard ships supposed to be representative of the radioactive material transporters, a specific analysis was achieved by the French Bureau Veritas, on a selection of the world casualties (total losses) for the 1978-1988 period. This analysis related to the origin of the fire points out that it originates mainly in the machinery room and quarters. In a few cases the fire duration recorded is more than one day. (author)

  12. Study of Spanish mining accidents using data mining techniques

    Sanmiquel Pera, Lluís; Rossell Garriga, Josep Maria; Vintró Sánchez, Carla

    2015-01-01

    Mining is an economic sector with a high number of accidents. Mines are hazardous places and workers can suffer a wide variety of injuries. Utilizing a database composed of almost 70,000 occupational accidents and fatality reports corresponding to the decade 2003–2012 in the Spanish mining sector, the paper analyzes the main causes of those accidents. To carry out the study, powerful statistical tools have been applied, such as Bayesian classi¿ers, decision trees or contingency t...

  13. Exploring the potential of data mining techniques for the analysis of accident patterns

    Prato, Carlo Giacomo; Bekhor, Shlomo; Galtzur, Ayelet;

    2010-01-01

    Research in road safety faces major challenges: individuation of the most significant determinants of traffic accidents, recognition of the most recurrent accident patterns, and allocation of resources necessary to address the most relevant issues. This paper intends to comprehend which data mining...... association rules) data mining techniques are implemented for the analysis of traffic accidents occurred in Israel between 2001 and 2004. Results show that descriptive techniques are useful to classify the large amount of analyzed accidents, even though introduce problems with respect to the clear...... importance of input and intermediate neurons, and the relative importance of hundreds of association rules. Further research should investigate whether limiting the analysis to fatal accidents would simplify the task of data mining techniques in recognizing accident patterns without the “noise” probably...

  14. Statistical analysis of accident data associated with sea transport (invited paper)

    This analysis, based on Lloyd's database, gives an accurate description of the world fleet and the most severe ship accidents, as well as the frequencies of accident per ship type, accident category and age category. Complementary analyses were achieved using fire accident databases from AEA Technology and the French Bureau Veritas. The results should be used in the perspective of safety assessments of maritime shipments of radioactive material. For this purpose the existence of the regulations of the International Maritime Organisation has to be considered, leading to the introduction of correction factors to these statistical data derived from general cargo-carrying ships. (author)

  15. Knowledge data base for severe accident management of nuclear power plants

    For the reinforcement of the safety of NPPs, the continuous efforts are very important to take in the up-to-date scientific and technical knowledge positively and to reflect them into the safety regulation. The purpose of this present study is to gather effectively the scientific and technical knowledge about the severe accident (SA) phenomena and the accident management (AM) for prevention and mitigation of severe accident, and to take in the experimental data by participating in the international cooperative experiments regarding the important SA phenomena and the effectiveness of accident management. Based on those data and knowledge, JNES is developing and improving severe accident analysis models to maintain the severe accident analysis codes and the accident management knowledge base for assessment of the NPPs in Japan. The activities in fiscal year 2010 are as follows; Experimental study on OECD/NEA projects such as MCCI, SERENA, SFP and international cooperative PSI-ARTIST project, and analytical study on accident management review of new plant and making regulation for severe accident. (author)

  16. Knowledge data base for severe accident management of nuclear power plants

    For the reinforcement of the safety of NPPs, the continuous efforts are very important to take in the up-to-date scientific and technical knowledge positively and to reflect them into the safety regulation. The purpose of this present study is to gather effectively the scientific and technical knowledge about the severe accident (SA) phenomena and the accident management (AM) for prevention and mitigation of severe accident, and to take in the experimental data by participating in the international cooperative experiments regarding the important SA phenomena and the effectiveness of accident management. Based on those data and knowledge, JNES is developing and improving severe accident analysis models to maintain the severe accident analysis codes and the accident management knowledge base for assessment of the NPPs in Japan. The activities in fiscal year 2011 are as follows; Experimental study on OECD/NEA projects such as MCCI, SERENA, SFP and international cooperative PSI-ARTIST project, and analytical study on accident management review of new plant and making regulation for severe accident. (author)

  17. A Hybrid Algorithm of Traffic Accident Data Mining on Cause Analysis

    Jianfeng Xi

    2013-01-01

    Full Text Available Road traffic accident databases provide the basis for road traffic accident analysis, the data inside which usually has a radial, multidimensional, and multilayered structure. Traditional data mining algorithms such as association rules, when applied alone, often yield uncertain and unreliable results. An improved association rule algorithm based on Particle Swarm Optimization (PSO put forward by this paper can be used to analyze the correlation between accident attributes and causes. The new algorithm focuses on characteristics of the hyperstereo structure of road traffic accident data, and the association rules of accident causes can be calculated more accurately and in higher rates. A new concept of Association Entropy is also defined to help compare the importance between different accident attributes. T-test model and Delphi method were deployed to test and verify the accuracy of the improved algorithm, the result of which was a ten times faster speed for random traffic accident data sampling analyses on average. In the paper, the algorithms were tested on a sample database of more than twenty thousand items, each with 56 accident attributes. And the final result proves that the improved algorithm was accurate and stable.

  18. Data base of accident and agricultural statistics for transportation risk assessment

    A state-level data base of accident and agricultural statistics has been developed to support risk assessment for transportation of spent nuclear fuels and high-level radioactive wastes. This data base will enhance the modeling capabilities for more route-specific analyses of potential risks associated with transportation of these wastes to a disposal site. The data base and methodology used to develop state-specific accident and agricultural data bases are described, and summaries of accident and agricultural statistics are provided. 27 refs., 9 tabs

  19. Data base of accident and agricultural statistics for transportation risk assessment

    Saricks, C.L.; Williams, R.G.; Hopf, M.R.

    1989-11-01

    A state-level data base of accident and agricultural statistics has been developed to support risk assessment for transportation of spent nuclear fuels and high-level radioactive wastes. This data base will enhance the modeling capabilities for more route-specific analyses of potential risks associated with transportation of these wastes to a disposal site. The data base and methodology used to develop state-specific accident and agricultural data bases are described, and summaries of accident and agricultural statistics are provided. 27 refs., 9 tabs.

  20. Study of the Severity of Accidents in Tehran Using Statistical Modeling and Data Mining Techniques

    Hesamaldin Razi

    2013-01-01

    Full Text Available AbstractBackgrounds and Aims: The Tehran province was subject to the second highest incidence of fatalities due to traffic accidents in 1390. Most studies in this field examine rural traffic accidents, but this study is based on the use of logit models and artificial neural networks to evaluate the factors that affect the severity of accidents within the city of Tehran.Materials and Methods: Among the various types of crashes, head-on collisions are specified as the most serious type, which is investigated in this study with the use of Tehran’s accident data. In the modeling process, the severity of the accident is the dependent variable and defined as a binary covariate, which are non-injury accidents and injury accidents. The independent variables are parameters such as the characteristics of the driver, time of the accident, traffic and environmental characteristics. In addition to the prediction accuracy comparison of the two models, the elasticity of the logit model is compared with a sensitivity analysis of the neural network.Results: The results show that the proposed model provides a good estimate of an accident's severity. The explanatory variables that have been determined to be significant in the final models are the driver’s gender, age and education, along with negligence of the traffic rules, inappropriate acceleration, deviation to the left, type of vehicle, pavement conditions, time of the crash and street width.Conclusion: An artificial neural network model can be useful as a statistical model in the analysis of factors that affect the severity of accidents. According to the results, human errors and illiteracy of drivers increase the severity of crashes, and therefore, educating drivers is the main strategy that will reduce accident severity in Iran. Special attention should be given to a driver’s age group, with particular care taken when they are very young.

  1. A Novel Real-Time Video And Data Capture Of Vehicular Accident In Intelligent Transportation Systems

    Fekri M. Abduljalil

    2014-03-01

    Full Text Available In this paper, a novel real-time video and data cap ture of vehicle accident is proposed in Intelligent Transportation System (ITS. The proposed scheme so lves the problem of huge storage needed for recording vehicle accident in the smart vehicle and in the remote ITS server. It works efficiently wit h small amount of storage size and guarantee saving acciden t video in secondary storage. It enables user to capture real-time video and data of running vehicle . It enables user to get vehicle accident video and data anytime anywhere. The scheme is implemented using t estbed and its performance is evaluated. The result s show that the proposed scheme guarantees record the vehicle accident in the ITS server. The proposed scheme has better results in comparison with full t ime video recording scheme.

  2. Quantifying the Relationship Between Skid Resistance and Wet Weather Accidents for Virginia Data

    Kuttesch, Jeffrey S

    2004-01-01

    One of the factors contributing to motor vehicle crashes is lack of sufficient friction at the tire-pavement interface. Although the relationship between surface friction and roadway safety has long been recognized, attempts to quantify the effect of pavement skid resistance on wet accident rates have produced inconsistent results. This thesis analyzes the relationships between skid resistance, accident, and traffic data for the state of Virginia. The correlation between wet skid resistance...

  3. Avalanche risk in backcountry terrain based on usage frequency and accident data

    F. Techel

    2014-08-01

    Full Text Available In Switzerland, the vast majority of avalanche accidents occurs during recreational activities. Risk analysis studies mostly rely on accident statistics without considering exposure (or the elements at risk, i.e. how many and where people are recreating. We compared the accident data (backcountry touring with reports from two social media mountaineering networks – bergportal.ch and camptocamp.org. On these websites, users reported more than 15 000 backcountry tours during the five winters 2009/2010 to 2013/2014. We noted similar patterns in avalanche accident data and user data like demographics of recreationists, distribution of the day of the week (weekday vs. weekend or weather conditions (fine vs. poor weather. However, we also found differences such as the avalanche danger conditions on days with activities and accidents, but also the geographic distribution. While backcountry activities are concentrated in proximity to the main population centres in the West and North of the Swiss Alps, a large proportion of the severe avalanche accidents occurred in the inner-alpine, more continental regions with frequently unfavorably snowpack structure. This suggests that even greater emphasis should be put on the type of avalanche problem in avalanche education and avalanche forecasting to increase the safety of backcountry recreationists.

  4. Statistical evaluation of population data for calculation of radioactive material transport accident risks

    Calculation of accident dose-risk estimates with the RADTRAN code requires input data describing the population likely to be affected by the plume of radioactive material (RAM) released in a hypothetical transportation accident. In the existing model, population densities within 1/2 mile (0.8 km) of the route centerline are tabulated in three ranges (Rural, Suburban, and Urban). These population densities may be of questionable validity since the plume in the RADTRAN analysis is assumed to extend out to 120 km from the hypothetical accident site. The authors present a GIS-based population model which accounts for the actual distribution of population under a potential plume, and compare accident-risk estimates based on the resulting population densities with those based on the existing model. Results for individual points along a route differ greatly, but the cumulative accident risks for a sample route of a few hundred kilometers are found to be comparable, if not identical. The authors conclude, therefore, that for estimation of aggregate accident risks over typical routes of several hundred kilometers, the existing, simpler RADTRAN model is sufficiently detailed and accurate

  5. Transport accident frequency data, their sources and their application in risk assessment

    Base transport accident frequency data and sources of these data are presented. Both generic information and rates specific to particular routes or packages are included. Strong packages, such as those containing significant quantities of radioactive materials, will survive most of the accidents represented by these base frequencies without a containment breach. The association of severity probability distributions with a base frequency, and package and contents response, leading to the quantification of release frequency and magnitude, are often more important in risk assessment than the base frequency itself. This paper therefore also includes brief comments on techniques adopted to utilize the base frequencies. This paper reports an accident frequency data survey undertaken at the end of 1986. It has not been updated to take account of work published between January 1987 and the Report publication date. (author)

  6. 32 CFR 634.30 - Use of traffic accident investigation report data.

    2010-07-01

    ... data will be used to inform and educate drivers and to conduct traffic engineering studies. (e) Army... 32 National Defense 4 2010-07-01 2010-07-01 true Use of traffic accident investigation report data... (CONTINUED) LAW ENFORCEMENT AND CRIMINAL INVESTIGATIONS MOTOR VEHICLE TRAFFIC SUPERVISION Traffic...

  7. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: UPDATE 2, VOLUME III

    The original report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem St...

  8. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: UPDATE 2, VOLUME I

    The original report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem St...

  9. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: UPDATE 2, VOLUME II

    The original report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem St...

  10. Assessment of Trend and Seasonality in Road Accident Data: An Iranian Case Study

    Farzaneh Zolala

    2013-05-01

    Full Text Available Road traffic accidents and their related deaths have become a major concern, particularly in developing countries. Iran has adopted a series of policies and interventions to control the high number of accidents occurring over the past few years. In this study we used a time series model to understand the trend of accidents, and ascertain the viability of applying ARIMA models on data from Taybad city. Methods This study is a cross-sectional study. We used data from accidents occurring in Taybad between 2007 and 2011. We obtained the data from the Ministry of Health (MOH and used the time series method with a time lag of one month. After plotting the trend, non stationary data in mean and variance were removed using Box-Cox transformation and a differencing method respectively. The ACF and PACF plots were used to control the stationary situation. Results The traffic accidents in our study had an increasing trend over the five years of study. Based on ACF and PACF plots gained after applying Box-Cox transformation and differencing, data did not fit to a time series model. Therefore, neither ARIMA model nor seasonality were observed. Conclusion Traffic accidents in Taybad have an upward trend. In addition, we expected either the AR model, MA model or ARIMA model to have a seasonal trend, yet this was not observed in this analysis. Several reasons may have contributed to this situation, such as uncertainty of the quality of data, weather changes, and behavioural factors that are not taken into account by time series analysis.

  11. Primary Seat-Belt Laws and Driver Behavior: Evidence from Accident Data

    Bae, Yong-Kyun

    2013-01-01

    This paper investigates the offsetting effect theory, using individual-level accident data to analyze how drivers respond to seat-belt laws. I find that drivers drive their vehicles more carefully when more stringent seat-belt laws are in effect. I also find that careful driving is not associated with pedestrian involvement in accidents. Using synthetic panel data, I find that the change in the laws results in an increased number of careful drivers and a decreased number of careless drivers i...

  12. Serious work accidents and their causes - An analysis of data from Eurostat

    Jørgensen, Kirsten

    2015-01-01

    Europe each year. Despite the uncertainty of the data collected by Eurostat over two years stile provide a picture of the seriousness of the accidents, the sources of risk and the events taking place when the accidents occur. Data from Eurostat were analysed to find out which hazards and accidental...... events led to serious consequences. The aim was to determine which accidental events should be prioritised for prevention and to make recommendations regarding suitable risk reduction methods. There are many different hazards and accidental events each of which requires a different form of prevention...

  13. Statistical processing of natality data for the Czech Republic before and after the Chernobyl accident

    All available data regarding natality in Czechoslovakia (or the Czech Republic) before and after the Chernobyl accident are summarized. Data from the databases of the Czech Statistical Office and of the State Office for Nuclear Safety were used to analyze natality and mortality of children in the Czech Republic and to evaluate the relationship between the level of contamination and the change in the sex ratio at time of birth that was observed in some areas in November of 1986. Although the change in the ratio of newborn boys-to-girls ratio was statistically significant, no direct relationship between that ratio and the level of contamination was found. Statistically significant changes in the sex ratio also occurred in Czechoslovakia (or in the Czech Republic) in the past, both before and after the accident. Furthermore, no statistically significant changes in the rate of stillbirths and multiple pregnancies were observed after the Chernobyl accident

  14. Knowledge data base for severe accident management of nuclear power plants

    For the safety enhancement of Nuclear Power Plants (NPPs), continuous efforts are very important to take in the up-to-date scientific and technical knowledge positively and to reflect them into the safety regulation. The purpose of the present study is to gather effectively the scientific and technical knowledge about the severe accident (SA) phenomena and the accident management (AM) for prevention and mitigation of SA, and to take in the experimental data by participating in the international cooperative experiments regarding the important SA phenomena and the effectiveness of AM. Based on those data and knowledge, JNES is developing and improving severe accident analysis models to maintain the SA analysis codes and the AM knowledge base for assessment of the NPPs in Japan. The activities in fiscal year 2012 are as follows; Analytical study on OECD/NEA projects such as MCCI, SERENA and SFP projects, and support in making regulation for SA. (author)

  15. Qualification of data obtained during a severe accident. Illustrative examples from TMI-2 evaluations

    Rempe, Joy L. [Rempe and Associates, Idaho Falls, ID (United States); Knudson, Darrell L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. Post-TMI-2 instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. Prior efforts also focused on sensors providing data required for subsequent forensic evaluations and accident simulations. This paper provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: reactor coolant system (RCS) pressure; containment building temperature; and containment pressure. These selected examples illustrate the types of activities completed in the TMI-2 data qualification process and the importance of such a qualification effort. These details are described to facilitate implementation of a similar process using data and examinations at the Daiichi Units 1, 2, and 3 reactors so that BWR-specific benefits can be obtained.

  16. Mobile real-time data monitoring system for nuclear accident emergency

    A mobile real-time data monitoring system is designed for nuclear accident emergency, accomplished real-time data acquisition and transmission. For its special application, the system realized the real-time data acquisition of multi-serial device, GPS orientation and route record of the emergency monitoring vehicle, wireless data communications based on CDMA 1X network, database, etc. It is confirmed, by many times practical test, that such system satisfies the requirements of nuclear emergency monitoring. (authors)

  17. Traffic accident in Cuiabá-MT: an analysis through the data mining technology.

    Galvão, Noemi Dreyer; de Fátima Marin, Heimar

    2010-01-01

    The traffic road accidents (ATT) are non-intentional events with an important magnitude worldwide, mainly in the urban centers. This article aims to analyzes data related to the victims of ATT recorded by the Justice Secretariat and Public Security (SEJUSP) in hospital morbidity and mortality incidence at the city of Cuiabá-MT during 2006, using data mining technology. An observational, retrospective and exploratory study of the secondary data bases was carried out. The three database selected were related using the probabilistic method, through the free software RecLink. One hundred and thirty-nine (139) real pairs of victims of ATT were obtained. In this related database the data mining technology was applied with the software WEKA using the Apriori algorithm. The result generated 10 best rules, six of them were considered according to the parameters established that indicated a useful and comprehensible knowledge to characterize the victims of accidents in Cuiabá. Finally, the findings of the associative rules showed peculiarities of the road traffic accident victims in Cuiabá and highlight the need of prevention measures in the collision accidents for males. PMID:20841739

  18. MINING INDUSTRY ACCIDENT, INJURIES, EMPLOYMENT, AND PRODUCTION DATA (HISTORICAL STATISTICS, 1931-2001)

    Mining industry accident, injuries, employment and production data are given between the years 1931-2001. In 1983, the U.S. Congress limited the Mine Safety and Health Administration's (MSHA) enforcement activities over surface mining and milling of stone, clay, feldspar, colloid...

  19. Effect of JCO critical accident seen on an opinion poll data

    Formation of the first critical accident in Japan at an uranium fuel processing facility (Tokai Works of JCO) on September 30, 1999, gave a large impact to Japanese society. It was made much anxious if this accident largely affected to opinions on nuclear power generation because it was an inexperienced accident which was the worst one in Japan at level 4 of the international nuclear phenomenon evaluation scale, gave some radioactive exposures on human lives, gave, in a large scale, some effects to citizens' lives through requirement of their in-door sheltering, and so forth. Then, in order to understand trends of consciousness on nuclear power, the Research Institute of Nuclear Safety System, Ltd. have carried out five times surveys since 1993 at a center of the Kansai area, to accumulate comparable data. By comparing the surveyed results after two months of the accident with data before it, some objective effect of the JCO accident were tried to elucidate. As a result, it was at first found to reduce safety sense for description on safety security of the nuclear power generation such as increase of accidental anxiety, increase on formation anxiety of large accident like Chernobyl's one, micro amount of radiation, fail safe system, multiple protection, and so forth. On next, it was shown to relate on managing and operating organization of the nuclear power generation such as reduction of images for laborers and managers at the power plants, enforcement on education of employees for expectation of the electric power companies, and so on. And, it was elucidated to change some opinions such as reduction of common feelings on tales and articles on nuclear safety, increase of negative answers on good use of nuclear power generation, reduction of agreement on necessity opinion of the generation, and increase of agreement on its unnecessity opinion. (G.K.)

  20. Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Update 2, Volume II

    The original report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. This final update consists of additional data for 1979 by the same participating organizations, which has not been previously reported

  1. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: VOLUME III. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  2. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: VOLUME II. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  3. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: VOLUME VI. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  4. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: VOLUME V. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  5. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: VOLUME I. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  6. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: VOLUME IV. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  7. THREE MILE ISLAND NUCLEAR REACTOR ACCIDENT OF MARCH 1979. ENVIRONMENTAL RADIATION DATA: UPDATE. A REPORT TO THE PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

    This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corp...

  8. Development of a software platform for providing environmental monitoring data for the Fukushima Daiichi nuclear accident

    In nuclear emergencies, it is especially important to carry out a wide range of environmental monitoring and provide the data immediately so as to understand the current distribution of radionuclides and investigate countermeasures. Therefore, it is indispensable for a nuclear emergency response to establish a system that supports rapid provision of these data. The authors have been developing the software platform by integrating technologies of environmental monitoring, information processing and network communication, based on the experience of the Fukushima Daiichi Nuclear Accident. It was discovered that the platform is effective in reducing the time needed to publish the monitoring data. Reducing the cost and workload for publishing the monitoring data is also important because monitoring should be continued over a few decades in the case of the Fukushima accident. The authors' platform is expected to help to mitigate the problem, too. (authors)

  9. New methods for rapid data acquisition of contaminated land cover after NPP accident

    Aim of the research project is the analysis of the modem and rapid reliable data acquisition methods for agricultural countermeasures, feed-stuff restrictions and clean-up of large contaminated areas after NPP accident. Acquiring agricultural reliable data especially based on satellite technology and analysis of landscape contamination (based on computer code vs. in situ measurements, airborne and/or terrestrial mapping of contamination) are discussed. (authors)

  10. Initial VHTR accident scenario classification: models and data.

    Vilim, R. B.; Feldman, E. E.; Pointer, W. D.; Wei, T. Y. C.; Nuclear Engineering Division

    2005-09-30

    mixed convection regime for circular channel geometry were identified in the literature. We describe the use of computational experiments to obtain correction factors for applying these circular channel results to the specialized channel geometry of the RCCS. The intent is to reduce the number of laboratory experiments required. The FLUENT and Star-CD codes contain models that in principle can handle mixed convection but no data were found to indicate that their empirical models for turbulence have been benchmarked for mixed convection conditions. Separate effects experiments were proposed for gathering the needed data. In future work we will use the PIRTs to guide review of other components and phenomena in a similar manner as was done for the mixed convection mode in the RCCS. This is consistent with the project objective of identifying weaknesses or gaps in the code models for representing thermal-hydraulic phenomena expected to occur in the VHTR both during normal operation and upsets, identifying the models that need to be developed, and identifying the experiments that must be performed to support model development.

  11. Analysis of medicostatistical data to assess the genetic and teratogenic effects of the Chernobyl accident

    Analysis of the official medicodemographic statistical data (provided by the Ukrainian Ministry of Health) revealed variations in the mean rates of congenital developmental defects (CDD) before 1987 (1985-1986) and in the period of 1987-1989 in all the areas irrespective of a degree of contamination with radionuclides (i.e. variations are determined by the time factor rather than by the irradiation factor). According to the medical statistical data, the rates of CDD and spontaneous abortions varied within a wide range, making it difficult to assess probable mutagenic and teratogenic effects of the Chernobyl accident. Medicostatistical data on spontaneous abortions understated the actual rates 2-3-fold, therefore they were not recommended for assessment of mutagenic effects of the Chernobyl accident

  12. Data assimilation in early phase of radiation accident using particle filter

    Hofman, Radek; Šmídl, Václav; Pecha, Petr

    Melbourne : Australian Government - Bureau of Meteorology, 2009 - (Kepert, J.), s. 1-8 [The Fifth WMO International Symposium on Data Assimilation. Melbourne (AU), 05.10.2009-09.10.2009] R&D Projects: GA MŠk(CZ) 1M0572; GA ČR(CZ) GA102/07/1596; GA ČR GP102/08/P250 Institutional research plan: CEZ:AV0Z10750506 Keywords : data assimilation * particle filter * prediction * cloud shine * Gaussian puff * dose rate * reactor accident * decision support Subject RIV: DL - Nuclear Waste, Radioactive Pollution ; Quality http://library.utia.cas.cz/separaty/2009/AS/hofman-data assimilation in early phase of radiation accident using particle filter.pdf

  13. The prediction of the LWR plant accident based on the measured plant data

    In case of accident affecting a nuclear reactor, it is essential to anticipate the possible development of the situation to efficiently succeed in emergency response actions, i.e. firstly to be early warned, to get sufficient information on the plant: and as far as possible. The ASTRID (Assessment of Source Term for Emergency Response based on Installation Data) project consists in developing a methodology: of expertise to; structure the work of technical teams and to facilitate cross competence communications among EP players and a qualified computer tool that could be commonly used by the European countries to reliably predict source term in case of an accident in a light water reactor, using the information available on the plant. In many accident conditions the team of analysts may be located far away from the plant experiencing the accident and their decision making is based on the on-line plant data transmitted into the crisis centre in an interval of 30 - 600 seconds. The plant condition has to be diagnosed based on this information, In the ASTRID project the plant status diagnostics has been studied for the European reactor types including BWR, PWR and VVER plants. The directly measured plant data may be used for estimations of the break size from the primary system and its locations. The break size prediction may be based on the pressurizer level, reactor vessel level, primary pressure and steam generator level in the case of the steam generator tube rupture. In the ASTRID project the break predictions concept was developed and its validity for different plant types and is presented in the paper, when the plant data has been created with the plant specific thermohydraulic simulation model. The tracking simulator attempts to follow the plant behavior on-line based on the measured plant data for the main process parameters and most important boundary conditions. When the plant state tracking fails, the plant may be experiencing an accident, and the tracking

  14. Finding occupational accident patterns in the extractive industry using a systematic data mining approach

    This paper deals with occupational accident patterns of in the Portuguese Extractive Industry. It constitutes a significant advance with relation to a previous study made in 2008, both in terms of methodology and extended knowledge on the patterns’ details. This work uses more recent data (2005–2007) and this time the identification of the “typical accident” shifts from a bivariate, to a multivariate pattern, for characterising more accurately the accident mechanisms. Instead of crossing only two variables (Deviation x Contact), the new methodology developed here uses data mining techniques to associate nine variables, through their categories, and to quantify the statistical cohesion of each pattern. The results confirmed the “typical accident” of the 2008 study, but went much further: it reveals three statistically significant patterns (the top-3 categories in frequency); moreover, each pattern includes now more variables (4–5 categories) and indicates their statistical cohesion. This approach allowed a more accurate vision of the reality, which is fundamental for risk management. The methodology is best suited for large groups, such as national Authorities, Insurers or Corporate Groups, to assist them planning target-oriented safety strategies. Not least importantly, researchers can apply the same algorithm to other study areas, as it is not restricted to accidents, neither to safety.

  15. How accurate is accident data in road safety research? An application of vehicle black box data regarding pedestrian-to-taxi accidents in Korea.

    Chung, Younshik; Chang, IlJoon

    2015-11-01

    Recently, the introduction of vehicle black box systems or in-vehicle video event data recorders enables the driver to use the system to collect more accurate crash information such as location, time, and situation at the pre-crash and crash moment, which can be analyzed to find the crash causal factors more accurately. This study presents the vehicle black box system in brief and its application status in Korea. Based on the crash data obtained from the vehicle black box system, this study analyzes the accuracy of the crash data collected from existing road crash data recording method, which has been recorded by police officers based on accident parties' statements or eyewitness's account. The analysis results show that the crash data observed by the existing method have an average of 84.48m of spatial difference and standard deviation of 157.75m as well as average 29.05min of temporal error and standard deviation of 19.24min. Additionally, the average and standard deviation of crash speed errors were found to be 9.03km/h and 7.21km/h, respectively. PMID:26298271

  16. Accident Statistics

    Department of Homeland Security — Accident statistics available on the Coast Guard’s website by state, year, and one variable to obtain tables and/or graphs. Data from reports has been loaded for...

  17. Nuclear incidents/accidents data visualization with combined 2D/3D displays

    Along with the development of IT technology, information on the Internet has been diversifying. A practical management of information on the Web is essential for the detailed understanding of them. In order to represent information efficiently, we developed a combined display system with both merits of 2D and 3D displays. We visualized nuclear incidents/accidents data, which need user-friendly interface for information sharing, by the developed 2D/3D displays. The effects of our system on information sharing were verified. Moreover, we showed effectiveness of the visualization system with combined 2D/3D displays. (author)

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

    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. Persistence on airline accidents.

    L. A. GIL-ALANA; Barros, C.P. (Carlos P.); J.R. Faria

    2009-01-01

    This paper analyses airline accidents data from 1927-2006. The fractional integration methodology is adopted. It is shown that airline accidents are persistent and (fractionally) cointegrated with airline traffic. Thus, there exists an equilibrium relation between air accidents and airline traffic, with the effect of the shocks to that relationship disappearing in the long run. Policy implications are derived for countering accidents events.

  20. Persistence in Airline Accidents

    Carlos Pestana Barros; João Ricardo Faria; Luis A. Gil-Alana

    2008-01-01

    This paper analyses airline accident data from 1927-2006, through fractional integration. It is shown that airline accidents are persistent and (fractionally) cointegrated with airline traffic. There exists a negative relation between air accidents and airline traffic, with the effect of the shocks to that relationship disappearing in the long run. Policy implications are derived for countering accident events.

  1. Core damage frequency estimation using accident sequence precursor data: 1990--1993

    Martz, H.F.

    1998-12-01

    The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses probabilistic risk assessment (PRA) techniques to assess the potential for severe core damage (henceforth referred to simply as core damage) based on operating events. The types of operating events considered include accident sequence initiators, safety equipment failures, and degradation of plant conditions that could increase the probability that various postulated accident sequences occur. Such operating events potentially reduce the margin of safety available for prevention of core damage an thus can be considered as precursors to core damage. The current process for identifying, analyzing, and documenting ASP events is described in detail in Vanden Heuval et al. The significance of a Licensee Event Report (LER) event (or events) is measured by means of the conditional probability that the event leads to core damage, the so-called conditional core damage probability or, simply, CCDP. When the first ASP study results were published in 1982, it covered the period 1969--1979. In addition to identification and ranking of precursors, the original study attempted to estimate core damage frequency (CDF) based on the precursor events. The purpose of this paper is to compare the average annual CDF estimates calculated using the CCDP sum, Cooke-Goossens, Bier, and Abramson estimators for various reactor classes using the combined ASP data for the four years, 1990--1993. An important outcome of this comparison is an answer to the persistent question regarding the degree and effect of the positive bias of the CCDP sum method in practice. Note that this paper only compares the estimators with each other. Because the true average CDF is unknown, the estimation error is also unknown. Therefore, any observations or characterizations of bias are based on purely theoretical considerations.

  2. Preservation of thermalhydraulic and severe accident experimental data produced by the European Commission

    Pla, Patricia; Ammirabile, Luca; Pascal, Ghislain; Annunziato, Alessandro [European Commission Joint Research Centre, Petten (Netherlands). Inst. for Energy and Transport; European Commission Joint Research Centre, Ispra (Italy). Inst. for the Protection and Security of the Citizen

    2014-07-15

    The experimental data recorded in Integral Effect Test Facilities (ITFs) are traditionally used in order to validate Best Estimate (BE) system codes and to investigate the behaviour of Nuclear Power Plants (NPP) under accident scenarios. In the same way, facilities dedicated to specific thermalhydraulic (TH) Severe Accident (SA) phenomena are used for the development and improvement of specific analytical models and codes used in the SA analysis for Light Water Reactors (LWR). The extent to which the existing reactor safety experimental databases are preserved was well known and frequently debated and questioned in the nuclear community. The Joint Research Centre (JRC) of the European Commission (EC) has been deeply involved in several projects for experimental data production and experimental data preservation. The paper is presenting these large EC initiatives on the production of experimental data and its storage in the JRC STRESA node. The objective of the paper is to further disseminate and promote the usage of the database containing these experimental data and to demonstrate long-term importance of well maintained experimental databases. At present time the Nuclear Reactor Safety Assessment Unit (NRSA) of the JRC Institute of Energy and Transport in Petten is engaged in the development of a new STRESA tool to secure EU storage for SA experimental data and calculations. The target is to keep the main features of the existing STRESA structure but using the new informatics technologies that are nowadays available and providing new capabilities. The development of this new STRESA tool should be completed by the end of 2014. (orig.)

  3. Pattern extraction for high-risk accidents in the construction industry: a data-mining approach.

    Amiri, Mehran; Ardeshir, Abdollah; Fazel Zarandi, Mohammad Hossein; Soltanaghaei, Elahe

    2016-09-01

    Accidents involving falls and falling objects (group I) are highly frequent accidents in the construction industry. While being hit by a vehicle, electric shock, collapse in the excavation and fire or explosion accidents (group II) are much less frequent, they make up a considerable proportion of severe accidents. In this study, multiple-correspondence analysis, decision tree, ensembles of decision tree and association rules methods are employed to analyse a database of construction accidents throughout Iran between 2007 and 2011. The findings indicate that in group I, there is a significant correspondence among these variables: time of accident, place of accident, body part affected, final consequence of accident and lost workdays. Moreover, the frequency of accidents in the night shift is less than others, and the frequency of injury to the head, back, spine and limbs are more. In group II, the variables time of accident and body part affected are mostly related and the frequency of accidents among married and older workers is more than single and young workers. There was a higher frequency in the evening, night shifts and weekends. The results of this study are totally in line with the previous research. PMID:25997167

  4. Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2

    Highlights: • MCCI research in SARNET2 consisted of large and small-scale testing and modelling. • Heavy (U,Zr)O2 melt interacts with light concrete oxide to produce multiple, mixed phases. • Anisotropic concrete erosion of high SiO2 concrete by melts may be linked with crust stability. • Understanding this anisotropy is important for reliable 3-D modelling. • Precise measures of refractory oxide data greatly improve phase diagram accuracy. - Abstract: In a severe accident transient, corium composition and its properties determine its behaviour and its potential interactions both with the reactor vessel and in the later phases with the concrete basemat. This, in turn, requires a detailed knowledge of the phases present at temperature and how they are formed. Because it implies mainly the investigation of chemical systems at high temperature, these data are often difficult to obtain or are uncertain if it already exists. Therefore more data are required both to complete the thermodynamic databanks (such as NUCLEA) and to construct accurate equilibrium phase diagrams and to finally contribute to the improvement of the codes simulating these severe accident conditions. The MCCI work package (WP6) of the SARNET 2 Network of Excellence has been addressing these problems. In this framework in large facilities such as VULCANO tests have been performed on the interactions and ablation of UO2-containing melts with concrete. They have been completed by large scale MCCI testing such EPICOR on vessel steel corrosion. In parallel in major EU-funded ISTC projects co-ordinated with national institutes, such as the CORPHAD and PRECOS, smaller, single effect tests have been carried out on the more difficult phase diagrams. These have produced data that can be directly used by databanks and for modelling improvement/validation. From these data significant advances in the melt chemistry and pool behaviour have been made. A selection of experiments from participating

  5. Statistical evaluation of internal contamination data in the man following the Chernobyl accident

    The main implications of the general interest derived from the statistical analysis of the internal human contamination data obtained by ENEA-PAS with Whole Body Counter mesurements performed in Bologna in consequence of the Chernobyl accident are presented. In particular the trend with time of the individual body activity of members of a homogeneous group, the variability of individual contamination in ralation to the mean contamination, the statistical distribution of the data, the significance of mean values concerning small, homogeneous groups of subjects, the difference between subjects of different sex and its trend with time, are examined. Finally, the substantial independence of the individual committed dose equivalent evaluation due to the Chernobyl contamination on the Whole from the hypothesized values of the metabolic parameters is pointed out when the evaluation is performed on the basis of direct measurements with a Whole Body Counter

  6. Data Mining of Causal Relations from Text: Analysing Maritime Accident Investigation Reports

    Tirunagari, Santosh

    2015-01-01

    Text mining is a process of extracting information of interest from text. Such a method includes techniques from various areas such as Information Retrieval (IR), Natural Language Processing (NLP), and Information Extraction (IE). In this study, text mining methods are applied to extract causal relations from maritime accident investigation reports collected from the Marine Accident Investigation Branch (MAIB). These causal relations provide information on various mechanisms behind accidents,...

  7. Analysis of avalanche risk factors in backcountry terrain based on usage frequency and accident data in Switzerland

    Techel, F.; Zweifel, B.; Winkler, K.

    2015-09-01

    Recreational activities in snow-covered mountainous terrain in the backcountry account for the vast majority of avalanche accidents. Studies analyzing avalanche risk mostly rely on accident statistics without considering exposure (or the elements at risk), i.e., how many, when and where people are recreating, as data on recreational activity in the winter mountains are scarce. To fill this gap, we explored volunteered geographic information on two social media mountaineering websites - bergportal.ch and camptocamp.org. Based on these data, we present a spatiotemporal pattern of winter backcountry touring activity in the Swiss Alps and compare this with accident statistics. Geographically, activity was concentrated in Alpine regions relatively close to the main Swiss population centers in the west and north. In contrast, accidents occurred equally often in the less-frequented inner-alpine regions. Weekends, weather and avalanche conditions influenced the number of recreationists, while the odds to be involved in a severe avalanche accident did not depend on weekends or weather conditions. However, the likelihood of being involved in an accident increased with increasing avalanche danger level, but also with a more unfavorable snowpack containing persistent weak layers (also referred to as an old snow problem). In fact, the most critical situation for backcountry recreationists and professionals occurred on days and in regions when both the avalanche danger was critical and when the snowpack contained persistent weak layers. The frequently occurring geographical pattern of a more unfavorable snowpack structure also explains the relatively high proportion of accidents in the less-frequented inner-alpine regions. These results have practical implications: avalanche forecasters should clearly communicate the avalanche danger and the avalanche problem to the backcountry user, particularly if persistent weak layers are of concern. Professionals and recreationists, on the

  8. Generation IV benchmarking of TRISO fuel performance models under accident conditions. Modeling input data

    Blaise Collin

    2014-09-01

    This document presents the benchmark plan for the calculation of particle fuel performance on safety testing experiments that are representative of operational accidental transients. The benchmark is dedicated to the modeling of fission product release under accident conditions by fuel performance codes from around the world, and the subsequent comparison to post-irradiation experiment (PIE) data from the modeled heating tests. The accident condition benchmark is divided into three parts: the modeling of a simplified benchmark problem to assess potential numerical calculation issues at low fission product release; the modeling of the AGR-1 and HFR-EU1bis safety testing experiments; and, the comparison of the AGR-1 and HFR-EU1bis modeling results with PIE data. The simplified benchmark case, thereafter named NCC (Numerical Calculation Case), is derived from ''Case 5'' of the International Atomic Energy Agency (IAEA) Coordinated Research Program (CRP) on coated particle fuel technology [IAEA 2012]. It is included so participants can evaluate their codes at low fission product release. ''Case 5'' of the IAEA CRP-6 showed large code-to-code discrepancies in the release of fission products, which were attributed to ''effects of the numerical calculation method rather than the physical model''[IAEA 2012]. The NCC is therefore intended to check if these numerical effects subsist. The first two steps imply the involvement of the benchmark participants with a modeling effort following the guidelines and recommendations provided by this document. The third step involves the collection of the modeling results by Idaho National Laboratory (INL) and the comparison of these results with the available PIE data. The objective of this document is to provide all necessary input data to model the benchmark cases, and to give some methodology guidelines and recommendations in order to make all results suitable for comparison

  9. Database development for understanding the wet deposition and dispersion processes after the Fukushima nuclear plant accident. Radar data

    This manuscript describes datasets of meteorological information being developed for understanding the dispersion and deposition process of radionuclides associated with the Fukushima accident in March 2011. Among several products, this paper reports mainly our original radar data images including the X-band radar data from Fukushima University as well as the three-dimensional reflectivity data from the Japan Meteorological Agency C-band radar network. (author)

  10. Accidents - Chernobyl accident

    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.)

  11. Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2

    Bakardjieva, Snejana; Barrachin, M.; Bechta, S.; Bezdička, Petr; Bottomley, D.; Brissoneau, L.; Cheynet, B.; Dugne, O.; Fischer, E.; Fischer, M.; Gusarov, V.; Journeau, C.; Khabensky, V.; Kiselová, M.; Manara, D.; Piluso, P.; Sheindlin, M.; Tyrpekl, V.; Wiss, T.

    2014-01-01

    Roč. 74, SI (2014), s. 110-124. ISSN 0306-4549 Institutional support: RVO:61388980 Keywords : Corium * Severe accidents * Thermodynamic database Subject RIV: CA - Inorganic Chemistry Impact factor: 0.960, year: 2014

  12. Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions

    Massih, Ali R. [Quantum Technologies AB, Uppsala Science Park (Sweden)

    2007-02-15

    Extensive range of experiments has been conducted in the past to quantitatively identify and understand the behaviour of fuel rod under loss-of-coolant accident (LOCA) conditions in light water reactors (LWRs). The obtained experimental data provide the basis for the current emergency core cooling system acceptance criteria under LOCA conditions for LWRs. The results of recent experiments indicate that the cladding alloy composition and high burnup effects influence LOCA acceptance criteria margins. In this report, we review some past important and recent experimental results. We first discuss the background to acceptance criteria for LOCA, namely, clad embrittlement phenomenology, clad embrittlement criteria (limitations on maximum clad oxidation and peak clad temperature) and the experimental bases for the criteria. Two broad kinds of test have been carried out under LOCA conditions: (i) Separate effect tests to study clad oxidation, clad deformation and rupture, and zirconium alloy allotropic phase transition during LOCA. (ii) Integral LOCA tests, in which the entire LOCA sequence is simulated on a single rod or a multi-rod array in a fuel bundle, in laboratory or in a tests and results are discussed and empirical correlations deduced from these tests and quantitative models are conferred. In particular, the impact of niobium in zirconium base clad and hydrogen content of the clad on allotropic phase transformation during LOCA and also the burst stress are discussed. We review some recent LOCA integral test results with emphasis on thermal shock tests. Finally, suggestions for modelling and further evaluation of certain experimental results are made.

  13. Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions

    Extensive range of experiments has been conducted in the past to quantitatively identify and understand the behaviour of fuel rod under loss-of-coolant accident (LOCA) conditions in light water reactors (LWRs). The obtained experimental data provide the basis for the current emergency core cooling system acceptance criteria under LOCA conditions for LWRs. The results of recent experiments indicate that the cladding alloy composition and high burnup effects influence LOCA acceptance criteria margins. In this report, we review some past important and recent experimental results. We first discuss the background to acceptance criteria for LOCA, namely, clad embrittlement phenomenology, clad embrittlement criteria (limitations on maximum clad oxidation and peak clad temperature) and the experimental bases for the criteria. Two broad kinds of test have been carried out under LOCA conditions: (i) Separate effect tests to study clad oxidation, clad deformation and rupture, and zirconium alloy allotropic phase transition during LOCA. (ii) Integral LOCA tests, in which the entire LOCA sequence is simulated on a single rod or a multi-rod array in a fuel bundle, in laboratory or in a tests and results are discussed and empirical correlations deduced from these tests and quantitative models are conferred. In particular, the impact of niobium in zirconium base clad and hydrogen content of the clad on allotropic phase transformation during LOCA and also the burst stress are discussed. We review some recent LOCA integral test results with emphasis on thermal shock tests. Finally, suggestions for modelling and further evaluation of certain experimental results are made

  14. Framework for consistent traffic and accident statistical data bases = Cadre pour des bases de données statistiques cohérentes sur la circulation et les accidents.

    OECD Scientific Expert Group T8

    1988-01-01

    The OECD Road Transport Research Scientific Expert Group T8 "Framework for Consistent Traffic and Accident Statistical Data Bases" was confronted with the old problem of the inconsistency of data between countries, and the lack of some data altogether, especially traffic data for use as a measure of

  15. Research on risk assessment for maritime transport of radioactive materials. Preparation of maritime accident data for risk assessment

    Maritime transport of radioactive materials has been playing an important role in the nuclear fuel cycle in Japan. Due to recent increase of transported radioactive materials and diversification of transport packages with enlargement of nuclear research, development and utilization, safety securement for maritime transport of radioactive materials is one of important issues in the nuclear fuel cycle. Based squarely on the current circumstances, this paper summarizes discussion on importance of utilization of results of risk assessment for maritime transport of radioactive materials. A plan for development of comprehensive methodology to assess risks in maritime transport of radioactive materials is also described. Preparations of database of maritime accident to be necessary for risk assessment are also summarized. The prepared data could be utilized for future quantitative risk assessment, such as the event trees and fault trees analyses, for maritime transport of radioactive materials. The frequency of severe accident that the package might be damaged is also estimated using prepared data. (author)

  16. FATAL ACCIDENT REPORTING SYSTEM (FARS)

    The Fatal Accident Reporting System (FARS) database consist of three relational tables, containing data on automobile accidents on public U.S. roads that resulted in the death of one or more people within 30 days of the accident. Truck and trailer accidents are also included.

  17. [Accidents and acts of violence in Brazil: I--Analysis of mortality data].

    Jorge, M H; Gawryszewski, V P; Latorre, M do R

    1997-08-01

    accidents are a major problem in Vitória, Goiânia, Macapá, the Distrito Federal and Curitiba. Homicides have increased greatly in Porto Velho, Rio Branco, Recife, S. Luís, Vitória, S. Paulo, Curitiba, Porto Alegre, Cuiabá and the Distrito Federal. The mortality due to external causes in Brazil has become a major public health problem, especially because of homicides. It is important to emphasize that the quality of the mortality data on external causes is not the same for all capitals, because it is a question very closely related to the quality of legal information. PMID:9595755

  18. The use of data in evaluating radiation hazards associated with a reactor accident

    Wind speed, wind direction and stability measurements collected by the Meteorology Group at the Argonne National Laboratory have been used to evaluate the hazards associated with an assumed maximum credible reactor accident. Comparison of these results with those based on a constant wind direction, 2 meter per second wind speed and inversion conditions indicates a reduction factor of 10 for a 30-day iodine inhalation dose is reasonable when meteorological conditions are used. (author)

  19. Psychosocial service needs of pediatric transport accident survivors: Using clinical data-mining to establish demographic and service usage characteristics.

    Manguy, Alys-Marie; Joubert, Lynette; Bansemer, Leah

    2016-09-01

    The objectives in this article are the exploration of demographic and service usage data gained through clinical data mining audit and suggesting recommendations for social work service delivery model and future research. The method is clinical data-mining audit of 100 sequentially sampled cases gathering quantitative demographic and service usage data. Descriptive analysis of file audit data raised interesting trends with potential to inform service delivery and usage; the key areas of the results included patient demographics, family involvement and impact, and child safety and risk issues. Transport accidents involving children often include other family members. Care planning must take into account psychosocial issues including patient and family emotional responses, availability of primary carers, and other practical needs that may impact on recovery and discharge planning. This study provides evidence to plan for further research and development of more integrated models of care. PMID:27586428

  20. Reduction of Accident Rate in Heat Supply Networks by the Analysis of Pipe Rupture Statistical Data

    Adomas Ūselis

    2011-04-01

    Full Text Available Due to the lack of reliable methods to determine the conditions of the pipes buried-in-the-ground, the analysis of the crack history was performed in order to offer an alternative method for planning the pipe condition inspections and the system refurbishment. The results of analysis have shown that the oldest pipes of big diameter, mounted in a non-inspectable channels, loam, silt loam or sandy loam soil fall under the category of pipes with the highest accident rate.Article in Lithuanian

  1. Reduction of Accident Rate in Heat Supply Networks by the Analysis of Pipe Rupture Statistical Data

    Adomas Ūselis; Artur Rogoža

    2011-01-01

    Due to the lack of reliable methods to determine the conditions of the pipes buried-in-the-ground, the analysis of the crack history was performed in order to offer an alternative method for planning the pipe condition inspections and the system refurbishment. The results of analysis have shown that the oldest pipes of big diameter, mounted in a non-inspectable channels, loam, silt loam or sandy loam soil fall under the category of pipes with the highest accident rate.Article in Lithuanian

  2. Fission product release from UO/sub 2/ under LWR accident conditions: recent data compared with review values

    Studies of fission product release from commercial LWR fuel at temperatures up to 20000C in steam have shown that >50% of the Kr, I, and Cs may be released within 20 min. These data are in fairly good agreement with the results of a previous NRC review, but the influences of specific test/accident conditions other than temperature (which is the most important variable) on the behavior of these and other fission products are apparent. In particular, chemical effects related to the extent of cladding oxidation may dominate, as in the case of tellurium. 14 refs., 5 figs., 2 tabs

  3. Methods and data for HTGR fuel performance and radionuclide release modeling during normal operation and accidents for safety analysis

    The previous status report released in 1987 on reference data and calculation models for fission product transport in High-Temperature, Gas-Cooled Reactor (HTGR) safety analyses has been updated to reflect the current state of knowledge in the German HTGR program. The content of the status report has been expanded to include information from other national programs in HTGRs to provide comparative information on methods of analysis and the underlying database for fuel performance and fission product transport. The release and transport of fission products during normal operating conditions and during the accident scenarios of core heatup, water and air ingress, and depressurization are discussed. (orig.)

  4. Pilot Study for the Creation of a European Union Radiation Accident and Incident Data Exchange System (EURAIDE)

    This study has had the objective of evaluating the feasibility of: (i) facilitating the establishment of national radiation accident and incident databases where there are none and to encourage the compatibility of such databases, (ii) establishing a European network to exchange radiological protection feedback from accidents and incidents, (iii) establishing summary reports of relevant accidents and incidents with the aim of identifying lessons to be learned, so that they can be used in radiation protection training programs, and (iv) upgrading the radiological safety in the countries applying to join the EU, by integrating them into the above efficient feedback exchange system. This report details the first stage of the project, which was to review the status of existing (or proposed) national mechanisms for collating data on radiation incidents. The objectives of this initial review were to: i) obtain detailed information regarding the means of capturing and collating data, the format of established or proposed data systems and accessibility of the final data, ii) to use this information to consider how a European platform to gather relevant data/accident reports might be established., and iii) to consider how the various elements of national data systems might be harmonised in order to facilitate the presentation and distribution of lessons learned. It was considered that the key aspects that would need to be addressed in order to determine the feasibility of a European wide data exchange mechanism were: - the criteria used for the classification and categorisation of incidents, - criteria for the selection of incidents from national data systems for inclusion in a European-wide system, - the implication of possible language problems. In order to illicit the required information a detailed questionnaire was sent to a total of 31 countries, being existing European Member States, applicant or associated countries. A full list of the countries and institutions

  5. Chernobyl accident and Danmark

    The report describes the Chernobyl accident and its consequences for Denmark in particular. It was commissioned by the Secretary of State for the Environment. Volume 1 contains copies of original documents issued by Danish authorities during the first accident phase and afterwards. Evaluations, monitoring data, press releases, legislation acts etc. are included. (author)

  6. Chernobyl accident and Denmark

    The report describes the Chernobyl accident and its consequences for Denmark in particular. It was commissioned by The Secretary of State for the Environment. Volume 2 contains copies of original documents issued by Danish authorities during the first accident phase and afterwards. Evaluations, monitoring data, press releases, legislation acts etc. are included. (author)

  7. Transportation accidents

    Predicting the possible consequences of transportation accidents provides a severe challenge to an analyst who must make a judgment of the likely consequences of a release event at an unpredictable time and place. Since it is impractical to try to obtain detailed knowledge of the meteorology and terrain for every potential accident location on a route or to obtain accurate descriptions of population distributions or sensitive property to be protected (data which are more likely to be more readily available when one deals with fixed-site problems), he is constrained to make conservative assumptions in response to a demanding public audience. These conservative assumptions are frequently offset by very small source terms (relative to a fixed site) created when a transport vehicle is involved in an accident. For radioactive materials, which are the principal interest of the authors, only the most elementary models have been used for assessing the consequences of release of these materials in the transportation setting. Risk analysis and environmental impact statements frequently have used the Pasquill-Gifford/gaussian techniques for releases of short duration, which are both simple and easy to apply and require a minimum amount of detailed information. However, after deciding to use such a model, the problem of selecting what specific parameters to use in specific transportation situations still presents itself. Additional complications arise because source terms are not well characterized, release rates can be variable over short and long time periods, and mechanisms by which source aerosols become entrained in air are not always obvious. Some approaches that have been used to address these problems will be reviewed with emphasis on guidelines to avoid the Worst-Case Scenario Syndrome

  8. Linking road accident data to other files : an integrated road accident recordkeeping system. Contribution in Proceedings of Seminar P 'Road Safety' held at the 14th PTHC Summer Annual Meeting, University of Sussex, England, from 14-17 July 1986. Volume P 284, p. 55-86.

    Harris, S.

    1986-01-01

    The road accident data which the police collect is of great value to road safety research and is used extensively. This data increases greatly in value if it can be linked to other files which contain more detailed information on exposure. Linking road accident data to other files results in what we call an Integrated Road Accident Recordkeeping System in -which the combined value of the linked files is greater than that of the sum of their individual values.

  9. Removal of Radiocesium from Food by Processing: Data Collected after the Fukushima Daiichi Nuclear Power Plant Accident - 13167

    Removal of radiocesium from food by processing is of great concern following the accident of TEPCO's Fukushima Daiichi Nuclear Power Plant accident. Foods in markets are monitored and recent monitoring results have shown that almost all food materials were under the standard limit concentration levels for radiocesium (Cs-134+137), that is, 100 Bq kg-1 in raw foods, 50 Bq kg-1 in baby foods, and 10 Bq kg-1 in drinking water; those food materials above the limit cannot be sold. However, one of the most frequently asked questions from the public is how much radiocesium in food would be removed by processing. Hence, information about radioactivity removal by processing of food crops native to Japan is actively sought by consumers. In this study, the food processing retention factor, Fr, which is expressed as total activity in processed food divided by total activity in raw food, is reported for various types of corps. For white rice at a typical polishing yield of 90-92% from brown rice, the Fr value range was 0.42-0.47. For leafy vegetable (indirect contamination), the average Fr values were 0.92 (range: 0.27-1.2) after washing and 0.55 (range: 0.22-0.93) after washing and boiling. The data for some fruits are also reported. (authors)

  10. Removal of Radiocesium from Food by Processing: Data Collected after the Fukushima Daiichi Nuclear Power Plant Accident - 13167

    Uchida, Shigeo; Tagami, Keiko [Office of Biospheric Assessment for Waste Disposal, National Institute of Radiological Sciences, Anagawa 4-9-1, Inage-ku, Chiba 263-8555 (Japan)

    2013-07-01

    Removal of radiocesium from food by processing is of great concern following the accident of TEPCO's Fukushima Daiichi Nuclear Power Plant accident. Foods in markets are monitored and recent monitoring results have shown that almost all food materials were under the standard limit concentration levels for radiocesium (Cs-134+137), that is, 100 Bq kg{sup -1} in raw foods, 50 Bq kg{sup -1} in baby foods, and 10 Bq kg{sup -1} in drinking water; those food materials above the limit cannot be sold. However, one of the most frequently asked questions from the public is how much radiocesium in food would be removed by processing. Hence, information about radioactivity removal by processing of food crops native to Japan is actively sought by consumers. In this study, the food processing retention factor, F{sub r}, which is expressed as total activity in processed food divided by total activity in raw food, is reported for various types of corps. For white rice at a typical polishing yield of 90-92% from brown rice, the F{sub r} value range was 0.42-0.47. For leafy vegetable (indirect contamination), the average F{sub r} values were 0.92 (range: 0.27-1.2) after washing and 0.55 (range: 0.22-0.93) after washing and boiling. The data for some fruits are also reported. (authors)

  11. Description of Survey Data Regarding the Chemical Repackaging Plant Accident West Helena, Arkansas

    Sorensen, J.H.; Vogt, B.M.

    1999-03-01

    Shortly after 1:00 p.m. on Thursday, May 8, 1997, clouds of foul-smelling smoke began pouring from an herbicide and pesticide packaging plant in West Helena, Arkansas. An alert was sounded, employees evacuated, and the West Helena fire department was called. As three firefighters prepared to enter the plant, the chemical compounds exploded, collapsing a solid concrete block wall, and killing all three firefighters. As the odorous smoky cloud drifted away from the plant, authorities ordered residents in a 2-mile area downwind of the plant to evacuate and those in the 2- to 3-mile zone to shelter in place. This study examines and compares the responses to a mail survey of those ordered to evacuate and those told to shelter in place. Among the variables examined are compliance with official orders and perceived warnings, threat perception, time and source of first warning, response times, and behavior characteristics for both populations. The findings indicate that 90% of those that were told to evacuate did so but only 27% of those told to shelter-in-place did so, with 68% opting to evacuate instead. The implications of these findings for emergency managers is that people will likely choose to evacuate when both warnings to evacuate and warnings to shelter are issued to residents in close proximity to each other. The findings on warning times closely resemble other findings from evacuations when chemical accidents occur and route notification is used for warning residents.

  12. Road Traffic Accidents in Kazakhstan

    Alma Aubakirova; Alibek Kossumov; Nurbek Igissinov

    2013-01-01

    Background: The article provides the analysis of death rates in road traffic accidents in Kazakhstan from 2004 to 2010 and explores the use of sanitary aviation. Methods: Data of fatalities caused by road traffic accidents were collected and analysed. Descriptive and analytical methods of epidemiology and biomedical statistics were applied. Results: Totaly 27,003 people died as a result of road traffic accidents in this period. The death rate for the total population due to road traffic accid...

  13. Linking road accident data to other files : an integrated road accident recordkeeping system. Contribution in Proceedings of Seminar P 'Road Safety' held at the 14th PTHC Summer Annual Meeting, University of Sussex, England, from 14-17 July 1986. Volume P 284, p. 55-86.

    Harris, S.

    1986-01-01

    The road accident data which the police collect is of great value to road safety research and is used extensively. This data increases greatly in value if it can be linked to other files which contain more detailed information on exposure. Linking road accident data to other files results in what we

  14. Description of interview data regarding Pittsburgh and confluence toxic chemical accidents

    Rogers, G.O.; Shumpert, B.L.; Sorensen, J.H.

    1990-11-01

    Evacuation is the protective action most often recommended in response to chemical releases in the United States. The appropriateness of a decision to evacuate depends on whether the affected areas can be cleared of residents before it is contaminated by the chemical release. In determining whether an evacuation can be completed in time, emergency officials must consider both technical and behavioral aspects. The technical components can be readily conceived and quantified. In contrast, the behavioral components are much more abstract and more difficult to estimate. This report summarizes the univariate analysis of responses to surveys conducted in two communities where evacuation was recommended following train derailments involving hazardous chemicals. The surveys were designed to identify the actions taken by residents upon receiving the emergency warning; determine when people received the warning, decided to take action, and implemented the action; and ascertain factors that might explain the nature and timing of their actions. The surveys were conducted in the Bloomfield section of Pittsburgh, Pennsylvania, and in the town of Confluence, Pennsylvania. The study confirms that compliance with an emergency warning to evacuate varies and that potentially dangerous delays can be expected. Significant differences were noted, however, in the rate and speed of compliance in the two communities. The surveys provide information on several factors that may be useful in determining the reasons for differences in the responses from the two communities as well as differences among individual respondents. Such factors include the time of day when the accident occurred, where the respondent was at the time, whether the family was together, previous disaster experience, pet ownership, the content of the warning message, and demographic characteristics. 4 refs., 4 figs., 18 tabs.

  15. Atmospheric dispersion modelling and the use of radiological data in the event of a nuclear accident overseas

    This report considers what radiological measurements are most useful for use in conjunction with computer simulations based on meteorological data to provide the best possible estimates of areas affected and the likely levels of contamination in the event of a nuclear accident overseas. The context is defined according to the needs at different stages in emergency procedures - before radioactivity reaches the UK, during the period of passage overhead, after passage of the material. The ability to identify localised areas where precipitation has concentrated deposition is emphasized. It is made clear that γ detectors tend to be dominated by local levels of deposited activity and are inadequate to define when radioactivity is passing overhead. Facilities for airborne monitoring are recommended. (author)

  16. Nuclear accidents

    On 27 May 1986 the Norwegian government appointed an inter-ministerial committee of senior officials to prepare a report on experiences in connection with the Chernobyl accident. The present second part of the committee's report describes proposals for measures to prevent and deal with similar accidents in the future. The committee's evaluations and proposals are grouped into four main sections: Safety and risk at nuclear power plants; the Norwegian contingency organization for dealing with nuclear accidents; compensation issues; and international cooperation

  17. Boating Accident Statistics

    Department of Homeland Security — Accident statistics available on the Coast Guard’s website by state, year, and one variable to obtain tables and/or graphs. Data from reports has been loaded for...

  18. Radiation accidents

    Radiation accidents may be viewed as unusual exposure event which provide possible high exposure to a few people and, in the case of nuclear plants events, low exposure to large population. A number of radiation accidents have occurred over the past 50 years, involving radiation machines, radioactive materials and uncontrolled nuclear reactors. These accidents have resulted in number of people have been exposed to a range of internal and external radiation doses and those involving radioactive materials have involved multiple routs of exposure. Some of the more important accidents involving significant radiation doses or releases of radioactive materials, including any known health effects involves in it. An analysis of the common characteristics of accidents is useful resolving overarching issues, as has been done following nuclear power, industrial radiography and medical accidents. Success in avoiding accidents and responding when they do occur requires planning in order to have adequately trained and prepared health physics organization; well defined and developed instrument program; close cooperation among radiation protection experts, local and state authorities. Focus is given to the successful avoidance of accidents and response in the events they do occur. Palomares, spain in late 1960, Goiania, Brazil in 1987, Thule, Greenland in 1968, Rocky flats, Colorado in 1957 and 1969, Three mile island, Pennsylvania in 1979, Chernobyl Ukraine in april 1986, Kyshtym, former Soviet Union in 1957, Windscale, UK in Oct. 1957 Tomsk, Russian Federation in 1993, and many others are the important examples of major radiation accidents. (author)

  19. Occupational accidents aboard merchant ships

    Hansen, H.L.; Nielsen, D.; Frydenberg, Morten

    2002-01-01

    Objectives: To investigate the frequency, circumstances, and causes of occupational accidents aboard merchant ships in international trade, and to identify risk factors for the occurrence of occupational accidents as well as dangerous working situations where possible preventive measures may be...... initiated. Methods: The study is a historical follow up on occupational accidents among crew aboard Danish merchant ships in the period 1993–7. Data were extracted from the Danish Maritime Authority and insurance data. Exact data on time at risk were available. Results: A total of 1993 accidents were...... identified during a total of 31 140 years at sea. Among these, 209 accidents resulted in permanent disability of 5% or more, and 27 were fatal. The mean risk of having an occupational accident was 6.4/100 years at sea and the risk of an accident causing a permanent disability of 5% or more was 0.67/100 years...

  20. Applicability of small-scale integral test data to the 4500 MWt ESBWR loss-of-coolant accidents

    Saha, Pradip [GE Hitachi Nuclear Energy, 3901 Castle Hayne Road, Wilmington, NC 28401 (United States)], E-mail: pradip.saha@ge.com; Gamble, Robert E.; Shiralkar, Bharat S.; Fitch, James R. [GE Hitachi Nuclear Energy, 3901 Castle Hayne Road, Wilmington, NC 28401 (United States)

    2009-05-15

    This paper discusses the scaling methodology used by GE Hitachi Nuclear Energy (GEH) to show that the data obtained from the small-scale integral test facilities, namely, GIST and GIRAFFE-SIT, are relevant to the postulated loss-of-coolant accident (LOCA) of the 4500 MWt ESBWR. The conservation of mass and energy equations for the steam-water mixture in the reactor pressure vessel (RPV) are transformed to the equations for the rates of pressure change and water mass or inventory change. These equations are non-dimensionalized based on the most dominant physical processes of the individual stages of a LOCA, namely, the late blowdown stage, the GDCS (gravity driven cooling system) transition stage and the full GDCS stage. The magnitudes of the non-dimensional Pi-groups, obtained from these equations, for the 4500 MWt ESBWR are compared with those obtained for the small-scale integral tests mentioned earlier. In addition, simplified analyses were conducted for the first two stages by integrating the non-dimensional RPV depressurization rate and the water inventory change rate equations. The results of the 4500 MWt ESBWR are very similar to the test data obtained from the GIST and the GIRAFFE-SIT test facilities. Therefore, based on both the Pi-group magnitudes and the simplified analyses, it is concluded that the small-scale integral test data mentioned above are applicable to the 4500 MWt ESBWR LOCA applications.

  1. Big Data Analysis on Power Grid Security Accident%电网安全事故大数据分析

    刘友春; 卜晓; 卢逢婷

    2015-01-01

    Power was one of the social production factors, whether the power industry was safe or not had a big significance on national economy. This paper elaborated the current situation of big data development on China's power industry briefly, and introduced the specific application that big data acted on power grid security accident and evaluation model of power grid safety operation; pointed out big data problems to be solved in power industry and put forward a series of countermeasures.%电力是当今社会的生产要素之一,电力行业能否实现安全稳定生产对我国国民经济的发展至关重要。文章对我国电力行业大数据的发展现状进行了简要阐述,并介绍了大数据在电网安全事故方面的具体应用以及电网运行安全性评价分析模型,指出了大数据在电力行业中亟待解决的问题,并针对这些问题提出了一系列应对措施。

  2. Database on aircraft accidents

    The Reactor Safety Subcommittee in the Nuclear Safety and Preservation Committee published the report 'The criteria on assessment of probability of aircraft crash into light water reactor facilities' as the standard method for evaluating probability of aircraft crash into nuclear reactor facilities in July 2002. In response to the report, Japan Nuclear Energy Safety Organization has been collecting open information on aircraft accidents of commercial airplanes, self-defense force (SDF) airplanes and US force airplanes every year since 2003, sorting out them and developing the database of aircraft accidents for latest 20 years to evaluate probability of aircraft crash into nuclear reactor facilities. This year, the database was revised by adding aircraft accidents in 2010 to the existing database and deleting aircraft accidents in 1991 from it, resulting in development of the revised 2011 database for latest 20 years from 1991 to 2010. Furthermore, the flight information on commercial aircrafts was also collected to develop the flight database for latest 20 years from 1991 to 2010 to evaluate probability of aircraft crash into reactor facilities. The method for developing the database of aircraft accidents to evaluate probability of aircraft crash into reactor facilities is based on the report 'The criteria on assessment of probability of aircraft crash into light water reactor facilities' described above. The 2011 revised database for latest 20 years from 1991 to 2010 shows the followings. The trend of the 2011 database changes little as compared to the last year's one. (1) The data of commercial aircraft accidents is based on 'Aircraft accident investigation reports of Japan transport safety board' of Ministry of Land, Infrastructure, Transport and Tourism. 4 large fixed-wing aircraft accidents, 58 small fixed-wing aircraft accidents, 5 large bladed aircraft accidents and 114 small bladed aircraft accidents occurred. The relevant accidents for evaluating

  3. Modelling the radionuclide contamination of the Black Sea in the result of Chernobyl accident using circulation model and data assimilation

    Assimilation of observations is powerful tool to improve the predictive capabilities of models for radionuclide transport and fate. We describe results of numerical experiments on assimilation of data on radionuclide contamination of the Black Sea in the result of Chernobyl accident in the three-dimensional model of circulation and radionuclide transport THREETOX. Data assimilation in THREETOX can be formulated as procedure that contains two steps: update and forecast. On update step THREETOX is to be run from the time of release or the time of deposition to the time of forecast using updated input from all the data available at this period to be assimilated. On forecast step THREETOX is to be run from forecast time to the end of modeling period using results of update step to produce forecast of radionuclide transport. Two data assimilation methods were used: steady state specific Kalman filter (SSKF) and method iteration of optimal solution (IOS). These methods have been applied to the assimilation observational data of 137Cs concentration in the typhoon surveys for the period June 1986 to September 1990. From results of numerical experiments we conclude, that data assimilation can essentially improve predictive capability of models for radionuclide transport. The IOS was more effective than SSSKF and computational time for this method is small in comparison with general time for calculation. Results from the study will provide a better understanding of the processes of radionuclide transport in the seas. This novel approach is implemented in the EU DSS RODOS for a real-time simulation of the radioactivity transport in the marine environment. (author)

  4. Accidents with sulfuric acid

    Rajković Miloš B.

    2006-01-01

    Full Text Available Sulfuric acid is an important industrial and strategic raw material, the production of which is developing on all continents, in many factories in the world and with an annual production of over 160 million tons. On the other hand, the production, transport and usage are very dangerous and demand measures of precaution because the consequences could be catastrophic, and not only at the local level where the accident would happen. Accidents that have been publicly recorded during the last eighteen years (from 1988 till the beginning of 2006 are analyzed in this paper. It is very alarming data that, according to all the recorded accidents, over 1.6 million tons of sulfuric acid were exuded. Although water transport is the safest (only 16.38% of the total amount of accidents in that way 98.88% of the total amount of sulfuric acid was exuded into the environment. Human factor was the common factor in all the accidents, whether there was enough control of the production process, of reservoirs or transportation tanks or the transport was done by inadequate (old tanks, or the accidents arose from human factor (inadequate speed, lock of caution etc. The fact is that huge energy, sacrifice and courage were involved in the recovery from accidents where rescue teams and fire brigades showed great courage to prevent real environmental catastrophes and very often they lost their lives during the events. So, the phrase that sulfuric acid is a real "environmental bomb" has become clearer.

  5. Development of mobile laboratory methodology and data interpretation of environmental radiological situation after major nuclear accidents

    Full text: 1) Project Summary: The main objective of the work for the recent year was the development of a software package supporting on-site data evaluation and preparation for decision making. This software expert system consists of the following items: a new version of ERIDANUS for the geographical presentation of the data measured by the route monitoring system; a programme for flexible, interactive human dose prediction calculations based on measured and assumed radionuclide concentrations; and a code for optimum estimation of the radiological parameters by using all available data measured by mobile laboratory. 2) Summary of Proposed Work for the Next Year: Certain features of the above software are not completed yet, further work is needed to finish them during 1995. In addition, some technical development of the mobile laboratory is planned to solve the transmission of the data from the mobile unit to the evaluation centre. This task will be solved by establishing digital data transfer using radiotelephone connection between on-board and central PCs. (author)

  6. PRYMA-TO: A model of radionuclide transfer from air into food stuff. Test with data from the Chernobyl accident

    Garcia-Olivares, A.; Carrasco, E.; Suanez, A.; Josep, L.

    1994-07-01

    This report describes a dynamical model developed in the Environmental Institute of the CIEMAT. Its aims are the calculation of the integrated as well as time-dependent concentrations of ''131l and ''137Cs over time in soils, in forage pasture (or other vegetation species), and in milk and meat. The source contamination is assumed to come from a radioactive cloud confined in the atmospheric mixing layer. Data monitored in different locations the days following the Chernobyl accident have been used. The model was tested against post-Chernobyl data from 13 locations around the world, in the framework of the A4 exercise from the BIOMOVS program (Biospheric Models Validation Studies). The performance of the model is illustrated in 9 scenarios which have been chosen of these 13 because they have more information or they are better described. Default Probability Density Functions for the main parameters used by the model have been obtained by statistical processing of some post-Chernobyl evidence. (Author) 30 refs.

  7. PRYMA-TO: A model of radionuclide transfer from air into foodstuff. Test with data from the Chernobyl accident

    This report describes a dynamical model developed in the Environmental Institute of the CIEMAT. Its aims are the calculation of the integrated as well as time-dependent concentrations of ''131 I and ''137 Cs over time in soils, in forage pasture (or other vegetation species), and in milk and meat. The source contamination is assumed to come from a radioactive cloud confined in the atmospheric mixing layer. Data monitored in different locations the days following the Chernobyl accident have been used. The model was tested against post-Chernobyl data from 13 locations around the world, in the framework of the A4 exercise from the BIOMOVS program (Biospheric Models Validation Studies). The performance of the model is illustrated in 9 scenarios which have been chosen of these 13 because they have more information or they are better described. Default Probability Density Functions for the main parameters used by the model have been obtained by statistical processing of some post-Chernobyl evidence

  8. Simplified approach for reconstructing the atmospheric source term for Fukushima Daiichi nuclear power plant accident using scanty meteorological data

    Highlights: • Estimation of source terms for I-131 and Cs-137 for Fukushima Daiichi NPP. • Simplified Gaussian puff based atmospheric dispersion model is used. • Good agreement of estimated values as compared to that given by NISA, TEPCO and IRSN. - Abstract: The atmospheric source term for the Fukushima Daiichi nuclear power plant accident in March 2011 has been estimated by a Gaussian puff based atmospheric dispersion model. The scanty meteorological data available at irregular time intervals are utilized to demonstrate the utility of such data along with a simplified modeling approach to derive useful information. The source terms for I-131 and Cs-137 have been estimated as a function of time from the observed values of activity concentration in the air and deposited activity on the ground. The model results suggest that during 12th March 2011–16th March 2011, 9.29 × 1016 Bq of I-131 and 6.15 × 1015 Bq of Cs-137 might have got released to the environment

  9. PRYMA-TO: A model of radionuclide transfer from air into food stuff. Test with data from the Chernobyl accident

    This report describes a dynamical model developed in the Environmental Institute of the CIEMAT. Its aims are the calculation of the integrated as well as time-dependent concentrations of ''131l and ''137Cs over time in soils, in forage pasture (or other vegetation species), and in milk and meat. The source contamination is assumed to come from a radioactive cloud confined in the atmospheric mixing layer. Data monitored in different locations the days following the Chernobyl accident have been used. The model was tested against post-Chernobyl data from 13 locations around the world, in the framework of the A4 exercise from the BIOMOVS program (Biospheric Models Validation Studies). The performance of the model is illustrated in 9 scenarios which have been chosen of these 13 because they have more information or they are better described. Default Probability Density Functions for the main parameters used by the model have been obtained by statistical processing of some post-Chernobyl evidence. (Author) 30 refs

  10. Simplified data assimilation for simulating wet deposition distribution of radioactive materials in FDNPP accident

    Saya, A.; Yoshikane, T.; Chang, E. C.; Yoshimura, K.

    2015-12-01

    Due to the massive earthquakes and tsunami on March 11th 2011 in Eastern Japan, Fukushima Daiichi Nuclear Power Plant (FDNPP) was severely damaged. Radioactive materials were released and spread out by atmospheric advection-diffusion. Especially on March 21 - 23th when precipitation was observed, "hotspot" where the high concentration was detected locally. This area was formed in the metropolitan area in Kanto region. Thus, pollution at water treatment plants because of the deposition became a concern. Therefore, the reliable information of the hotspot is expected. Currently, atmospheric transport simulations by numerical models are developed for reproduction of the distribution. However, there are some uncertainties in the simulations. In the case of hotspot, accuracy of simulated precipitation have to be well considered because the hotspot seemed to be formed by wet deposition. We modified the stable isotope mode of Regional Spectral Model (IsoRSM) to enable to simulate the transport of the radioactive tracers, namely 131I and 137Cs, by including the dry and wet deposition processes. As the simplified data assimilation, simulated precipitation was replaced with Radar-AMeDAS precipitation data (RAP). RAP was assimilated in the post-process, after running simulations, to redistribute wet deposition of 137Cs. The ratio of 137Cs deposited from the cumulative vertical column with precipitation in the domain was not changed, however its pattern was redistributed corresponding with RAP and simulated concentration. As a result, the redistributed wet deposition was within factor 10 to 2 compared with the fallout data in Kanto region, and further data assimilation would be contributed. In addition, we found that due to the arrival time of the plume in the morning on 21st and the border time of daily observation data of fallout, validation result might be worse even though hourly distributions are well simulated.

  11. A Multiple Criteria Decision-Making Approach for Prioritizing Accident Hotspots in the Absence of Crash Data

    Pirdavani, Ali; Brijs, Tom; Wets, Geert

    2010-01-01

    In an efficient transportation system, traffic safety is an important issue and it is influenced by many factors. In a country like Iran, until now safety improvements are mainly concentrated on road engineering activities, without much attention for vehicle technology or driving behaviour. One important aspect of road safety engineering activities is the so-called treatment of hotspots or dangerous accident locations. Until recently, accident hotspots were identified and remedied by the esxp...

  12. Multiple Criteria Decision-Making Approach for Prioritizing Accident Hot Spots in Developing Countries in the Absence of Crash Data

    Pirdavani, Ali; Brijs, Tom; Wets, Geert

    2010-01-01

    In an efficient transportation system, traffic safety is an important issue and it is influenced by many factors. In a country like Iran, until now safety improvements are mainly concentrated on road engineering activities, without much attention for vehicle technology or driving behavior. One important aspect of road safety engineering activities is the so-called treatment of hotspots or dangerous accident locations. Until recently, accident hotspots were identified and remedied by the exper...

  13. Data assimilation and source term estimation during the early phase of a nuclear accident

    Golubenkov, A.; Borodin, R. [SPA Typhoon, Emergency Centre (Russian Federation); Sohier, A.; Rojas Palma, C. [Centre de l`Etude de l`Energie Nucleaire, Mol (Belgium)

    1996-02-01

    The mathematical/physical base of possible methods to model the source term during an accidental release of radionuclides is discussed. Knowledge of the source term is important in view of optimizing urgent countermeasures to the population. In most cases however, it will be impossible to assess directly the release dynamics. Therefore methods are under development in which the source term is modelled, based on the comparison of off-site monitoring data and model predictions using an atmospheric dispersion model. The degree of agreement between the measured and calculated characteristics of the radioactive contamination of the air and the ground surface is an important criterion in this process. Due to the inherent complexity, some geometrical transformations taking space-time discrepancies between observed and modelled contamination fields are defined before the source term is adapted. This work describes the developed algorithms which are also tested against data from some tracer experiments performed in the past. This method is also used to reconstruct the dynamics of the Chernobyl source term. Finally this report presents a concept of software to reconstruct a multi-isotopic source term in real-time.

  14. Code portability and data management considerations in the SAS3D LMFBR accident-analysis code

    The SAS3D code was produced from a predecessor in order to reduce or eliminate interrelated problems in the areas of code portability, the large size of the code, inflexibility in the use of memory and the size of cases that can be run, code maintenance, and running speed. Many conventional solutions, such as variable dimensioning, disk storage, virtual memory, and existing code-maintenance utilities were not feasible or did not help in this case. A new data management scheme was developed, coding standards and procedures were adopted, special machine-dependent routines were written, and a portable source code processing code was written. The resulting code is quite portable, quite flexible in the use of memory and the size of cases that can be run, much easier to maintain, and faster running. SAS3D is still a large, long running code that only runs well if sufficient main memory is available

  15. Data bank for the data at early measurements of radioactive contamination in Belarus after Chernobyl NPP accident

    Owing to active participation of many organizations in the works on selection and measurement of soil samples, as well as to timely processing of the data with the help of the formed data bank, in August 1986 the map of the contamination with 137Cs of the whole territory of Belarus was drawn up at the Institute, and in November 1996 - the maps of contamination with 90Sr and isotopes of plutonium. For mapping more than 11,600 gamma spectrometric measurements of the objects of the environment from 1386 settlements and about 2100 radiochemical measurements were used. Further the data bank was modified to some extent and added with a package of applied programs what made the preliminary processing and verification of the data be easy. (author)

  16. Experimental data report for Test TS-1 Reactivity Initiated Accident Test in NSRR with pre-irradiated BWR fuel rod

    This report presents experimental data for Test TS-1 which was the first in a series of tests, simulating Reactivity Initiated Accident (RIA) conditions using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in October, 1989. Test fuel rod used in the Test TS-1 was a short-sized BWR (7 x 7) type rod which was fabricated from a commercial rod provided from Tsuruga Unit 1 power reactor. The fuel had an initial enrichment of 2.79 % and burnup of 21.3 GWd/t (bundle average). Pulse irradiation was performed at a condition of stagnant water cooling, atmospheric pressure and ambient temperature using a newly developed double container-type capsule. Energy deposition of the rod in this test was evaluated to be about 61 cal/g·fuel (55 cal/g·fuel in peak fuel enthalpy) and no fuel failure was observed. Descriptions on test conditions, test procedures, fuel burnup measurements, transient behavior of the test rod during pulse irradiation and results of post pulse irradiation examinations are contained in this report. (author)

  17. Time-to-burnout data for a prototypical ITER divertor tube during a simulated loss of flow accident

    The Loss of Flow Accident (LOFA) is a serious safety concern for the International Thermonuclear Experimental Reactor (ITER) as it has been suggested that greater than 100 seconds are necessary to safely shutdown the plasma when ITER is operating at full power. In this experiment, the thermal response of a prototypical ITER divertor tube during a simulated LOFA was studied. The divertor tube was fabricated from oxygen-free high-conductivity copper to have a square geometry with a circular coolant channel. The coolant channel inner diameter was 0.77 cm, the heated length was 4.0 cm, and the heated width was 1.6 cm. The mockup did not feature any flow enhancement techniques, i.e., swirl tape, helical coils, or internal fins. One-sided surface heating of the mockup was accomplished through the use of the 30 kW Sandia Electron Beam Test System. After reaching steady state temperatures in the mockup, as determined by two Type-K thermocouples installed 0.5 mm beneath the heated surface, the coolant pump was manually tripped off and the coolant flow allowed to naturally coast down. Electron beam heating continued after the pump trip until the divertor tube's heated surface exhibited the high temperature transient normally indicative of rapidly approaching burnout. Experimental data showed that time-to-burnout increases proportionally with increasing inlet velocity and decreases proportionally with increasing incident heat flux

  18. Accident and emergency management

    There is an increasing potential for severe accidents as the industrial development tends towards large, centralised production units. In several industries this has led to the formation of large organisations which are prepared for accidents fighting and for emergency management. The functioning of these organisations critically depends upon efficient decision making and exchange of information. This project is aimed at securing and possibly improving the functionality and efficiency of the accident and emergency management by verifying, demonstrating, and validating the possible use of advanced information technology in the organisations mentioned above. With the nuclear industry in focus the project consists of five main activities: 1) The study and detailed analysis of accident and emergency scenarios based on records from incidents and rills in nuclear installations. 2) Development of a conceptual understanding of accident and emergency management with emphasis on distributed decision making, information flow, and control structure sthat are involved. 3) Development of a general experimental methodology for evaluating the effects of different kinds of decision aids and forms of organisation for emergency management systems with distributed decision making. 4) Development and test of a prototype system for a limited part of an accident and emergency organisation to demonstrate the potential use of computer and communication systems, data-base and knowledge base technology, and applications of expert systems and methods used in artificial intelligence. 5) Production of guidelines for the introduction of advanced information technology in the organisations based on evaluation and validation of the prototype system. (author)

  19. The Chernobyl accident and radiation risks: dynamics of epidemiological rates (morbidity, disability and death rates) according to the data in the national registry

    Ten years have elapsed since the Chernobyl accident. The gravest technologically generated accident throughout human history has attracted considerable attention from the whole world community. At the same time, the problem of estimating the total damage to life and health of people exposed to radiation remains very complicated. The negative effects of Chernobyl include a spectrum of factors which may reinforce each other. In particular, to date there are no theoretical models or practical recommendations on estimating the contribution of the social, psychological or emotional factors that surround diseases due to radiation accidents. On the other hand, for maximum effective rehabilitation of the affected population, the impartial determination of the contribution by both radiation and non-radiation components is necessary. Therefore, the continuation of long-standing investigations within the framework of the National Radiation and Epidemiological Registry along with obtaining new scientific data in the field of radiation epidemiology is of great practical importance in limiting the health consequences of the accident. 5 refs, 5 figs, 4 tabs

  20. Qualification of Daiichi Units 1, 2, and 3 Data for Severe Accident Evaluations - Process and Illustrative Examples from Prior TMI-2 Evaluations

    Rempe, Joy Lynn [Idaho National Lab. (INL), Idaho Falls, ID (United States); Knudson, Darrell Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This initial review focused on the set of sensors deemed most important by post-TMI-2 instrumentation evaluation programs. Instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. In addition, prior efforts focused on sensors providing data required for subsequent forensic evaluations and accident simulations. To encourage the potential for similar activities to be completed for qualifying data from Daiichi Units 1, 2, and 3, this report provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: primary system pressure; containment building temperature; and containment pressure. As described within this report, sensor evaluations and data qualification required implementation of various processes, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design to instruments easily removed from the TMI-2 plant for evaluations. As documented

  1. Qualification of Daiichi Units 1, 2, and 3 Data for Severe Accident Evaluations - Process and Illustrative Examples from Prior TMI-2 Evaluations

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This initial review focused on the set of sensors deemed most important by post-TMI-2 instrumentation evaluation programs. Instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. In addition, prior efforts focused on sensors providing data required for subsequent forensic evaluations and accident simulations. To encourage the potential for similar activities to be completed for qualifying data from Daiichi Units 1, 2, and 3, this report provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: primary system pressure; containment building temperature; and containment pressure. As described within this report, sensor evaluations and data qualification required implementation of various processes, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design to instruments easily removed from the TMI-2 plant for evaluations. As documented

  2. Changes in the dynamics of hematological indices one decade after the Chernobyl accident: Databases, mathematical modelling, medical data analysis

    The changes in dynamic of clinical and immunological indices of preleucoses and hemobastoses one decade after Chernobyl accident were carried out. Level of disease has risen from 4.41 to 12.02 per 100000 men since 1987 till 1992 years. The investigation, had demonstrated the complex of distinct clinical morphological and functional changes in hemopoiesys system. 4 refs, 5 figs, 1 tab

  3. [Psychogenesis of accidents].

    Giannattasio, E; Nencini, R; Nicolosi, N

    1988-01-01

    After having carried out a historical review of industrial psychology with specific attention to the evolution of the concept of causality in accidents, the Authors formulate their work hypothesis from that research which take into highest consideration the executives' attitudes in the genesis of the accidents. As dogmatism appears to be one of the most negative of executives' attitudes, the Authors administered Rockeach's Scale to 130 intermediate executives from 6 industries in Latium and observed the frequency index for accidents and the morbidity index (absenteeism) of the 2149 workhand. The Authors assumed that to high degree of dogmatism on the executives' side should correspond o a higher level of accidents and absenteeism among the staff. The data processing revealed that, due to the type of machinery employed, three of the industries examined should be considered as High Risk Industrie (HRI), while the remaining three could be considered as Low Risk Industries (LRI): in fact, due to the different working conditions, a significant lower number of accidents occurred in last the three. A statistically significant correlation between the executives' dogmatism and the number of accidents among their workhand in the HRI has been noticed, while this has not been observed in the LRI. This confirms, as had already been pointed out by Gemelli in 1944, that some "objective conditions" are requested so that the accident may actually take place. On the other hand the morbidity index has not shown any difference related to the different kind of industries (HRI, LRI): in both cases statistically significant correlations were obtained between the executives' dogmatism and the staff's absenteeism. absenteeism.(ABSTRACT TRUNCATED AT 250 WORDS) PMID:3154344

  4. Information credibility for radiation contamination of foods after the Fukushima nuclear accident (3). Undergraduates panel data from one and four months after

    We examined the changes in information credibility, attitude of mass media, and risk perception concerning radiation contamination of foods after the Fukushima nuclear accident. We used a two-wave panel data of 277 undergraduates who completed the scales twice, one month and four months after the accident. Our findings indicated that the information credibility of optimistic experts, citizens' web pages and government press conferences decreased with time. On the other hand, the credibility of newspaper and TV news programs increased. In addition, while the critical attitude of mass media and the knowledge of radiation health effects increased after four months, the risk perception for foods under legal limits of radiation contamination decreased. A causal analysis carried out with the panel data found that (1) critical thinking attitude affected media literacy. In turn, (2) media literacy affected bias perception of mass media, information credibility, active information search, and risk perception of contamination foods. Finally, (3) this causal relationship was constant from the first to the fourth month after the accident. (author)

  5. Congestion by accident? Traffic and accidents in England

    Pasidis, Ilias-Nikiforos

    2015-01-01

    The goal of this paper is the estimation of the effect of accidents on traffic congestion and vice versa. In order to do this, I use ?big data? of highway traffic and accidents in England for the period 2007-2013. The data exhibit some remarkably stable cyclical pattern of highway traffic which is used as a research setting that enables the identification of the causal effect of accidents on traffic congestion and vice versa. The estimation draws on panel data methods that have previously bee...

  6. Mortal radiological accident

    After defining the concept of 'Radiological accident', statistical data from Radiation Emergency Assistance Center of ORNL (United States of America) are given about the deaths caused by acute irradiation between 1944 and April 24, 1986 -ie, the day before Chernobyl nuclear accident- as well as on the number of deaths caused by the latter. Next the different clinical stages of the Acute Irradiation Syndrome (AIS) as well as its possible treatment are described, and finally the different physical, clinical and biological characteristics linked to the AIS and to its diagnosis and prognosis are discussed. (M.E.L.)

  7. The TMI-2 accident evaluation program

    The accident at the Three Mile Island Unit 2 (TMI-2) reactor, now 10 years old, remains as the United States' worst commercial nuclear reactor accident. Although the consequences of the accident were restricted primarily to the plant itself, the potential consequences of the accident, should it have progressed further, are large enough to warrant close scrutiny of all aspects of the event. TMI-2 accident research is being conducted by the US Department of Energy (DOE) to provide the basis for more accurate calculations of source terms for postulated severe accidents. Research objectives supporting this goal include developing a comprehensive and consistent understanding of the mechanisms that controlled the progression of core damage and subsequent fission product behavior during the TMI-2 accident, and applying that understanding to the resolution of important severe accident safety issues. Developing a best-estimate scenario of the core melt progression during the accident is the focal point of the research and involves analytical work to interpret and integrate: (1) data recorded during the accident from plant instrumentation, (2) the post-accident state of the core, (3) results of the examination of material from the damaged core, and (4) related severe-accident research results. This paper summarizes the TMI-2 Accident Evaluation Program that is being conducted for the USDOE and briefly describes the important results that have been achieved. The Program is divided into four parts: Sample Acquisition and Plant Examination, Accident Scenario, Standard Problem Exercise, and Information and Industry Coordination

  8. Helicopter accident survivability.

    Vyrnwy-Jones, P; Thornton, R

    1984-10-01

    Army Air Corps accident and fatality rates have now reached levels which compare favourably with data from other civilian and military sources. This improvement is the result of enhanced helicopter design and parallel progress in aircrew training. The introduction of new generations of turbine powered rotor craft has largely eliminated mechanical failure as the cause of accident. As a result 75% of Army Air Corps accidents are due to pilot error. This contribution is likely to increase in the future as the pilot's task is made more difficult by the incumberance of personal equipment. Methods whereby occupant protection and aircraft crashworthiness can be improved are reviewed and it is concluded that it would make sound economic sense to implement some of these well proven design features. PMID:6527344

  9. Clinical data from one year follow-up of victims of the radiation accident with 60Co in Bulgaria.

    Djounova, J; Guleva, I; Negoicheva, K; Mileva, I; Panova, D; Rupova, I

    2014-09-01

    A severe radiation accident occurred on 14 June 2011 in an industrial irradiation facility for medical equipment sterilization in Bulgaria. Five people were exposed for 5-10 min to a 60Co source containing 137 TBq. The Emergency Department of the National Centre of Radiobiology and Radiation Protection (NCRRP), Bulgaria, put into practice the plans for providing medical care in radiation accidents and the procedures developed for assessment of injury severity, the decision-making algorithm regarding subsequent treatment, and the therapy for persons affected. The activities performed for initial assessment of the severity of injury of irradiated patients were published in 2012. Based on predictive assessments of the severity of radiation damage, it was decided that the victims required hospitalization at a specialized hematology clinic. Percy Hospital in Paris was chosen for this purpose. The aim of this report is to present the results of 1-y follow-up for three of the victims. Sadly, 1 mo after the accident, Patient 4 died from a heart attack. The medical opinion was that this was not a direct outcome of the irradiation. Patient 5 was only followed up for 4 mo (118 d) because medical follow-up is voluntary, and despite repeated calls, the patient did not respond. Medical examinations by a physician as well as hematology and biochemical tests were performed using standard laboratory methods. The obtained results were compared to the victims' personal reference limits obtained from annual health monitoring. After the accident, the recovery to normal content of peripheral blood cells was observed in all victims. Nevertheless, there were observed cases of thrombocytopenia, granulocytopenia, and leucocytopenia at various times after exposure. During the period of observation, morphological changes in red blood cells such as anisomicrocitosis, macrocytes, megalocytes, and polychromatic erythrocytes were demonstrated. During the 1-y observation period, all victims showed

  10. Tchernobyl accident

    First, R.M.B.K type reactors are described. Then, safety problems are dealt with reactor control, behavior during transients, normal loss of power and behavior of the reactor in case of leak. A possible scenario of the accident of Tchernobyl is proposed: events before the explosion, possible initiators, possible scenario and events subsequent to the core meltdown (corium-concrete interaction, interaction with the groundwater table). An estimation of the source term is proposed first from the installation characteristics and the supposed scenario of the accident, and from the measurements in Europe; radiological consequences are also estimated. Radioactivity measurements (Europe, Scandinavia, Western Europe, France) are given in tables (meteorological maps and fallouts in Europe). Finally, a description of the site is given

  11. Balance of older trekkers: data on alpine accidents and performance as assessed using a video game machine.

    Kimura, Masafumi; Tobe, Masaru; Suto, Takashi; Narahara, Soh; Yamada, Makiko; Aso, Chizu; Takazawa, Tomonori; Baba, Yasuo; Saito, Shigeru

    2012-09-01

    The number of alpine accidents involving older trekkers has increased markedly in developed countries in recent years. More than 76.8% of the trekkers involved in alpine accidents in Japan were older than 40 years, with some experiencing a stroke or myocardial infarction while trekking at altitude. In the present study, we surveyed social trends in trekkers by interview at a popular mountain site, Mt Tanigawa (1963 m in altitude). The total number of trekkers interviewed was 511, and more than 60% of these were older than 40 years. Of trekkers older than 60 years, 42% complained of conditions such as hypertension or diabetes. In 2 volunteer groups (10 younger subjects and 10 older subjects), physical condition was assessed before and after trekking. Significant body weight loss induced by dehydration was observed more often in older subjects than in younger subjects (P problems with regard to overall health and balance. Alpine accidents caused by myocardial infarction, stroke, or hypoglycemia tend to be more common in this population. Alpine rescue teams should be well prepared for this, and older trekkers should be made aware of their increased risk of injury in alpine settings. PMID:22633704

  12. Accident: Reminder

    2003-01-01

    There is no left turn to Point 1 from the customs, direction CERN. A terrible accident happened last week on the Route de Meyrin just outside Entrance B because traffic regulations were not respected. You are reminded that when travelling from the customs, direction CERN, turning left to Point 1 is forbidden. Access to Point 1 from the customs is only via entering CERN, going down to the roundabout and coming back up to the traffic lights at Entrance B

  13. Study on traffic accidents mechanism with automatic recording systems. Part 2. Application of data from ADR and DMR for practical driver education; Jidosha kiroku sochi ni yoru kotsu jiko hassei mechanism no kenkyu. 2. Jiko data kirokukei (ADR) to unko kirokukei (DMR) no untensha kyoiku eno katsuyo

    Ueyama, M.; Ogawa, S. [National Research Inst. of Police Science, Tokyo (Japan); Chikasue, H.; Muramatsu, K. [Yazaki Meter Co. Ltd., Tokyo (Japan)

    1997-10-01

    A field trial are carried out using automatic receding system; ADR (Accident Data Recorder) and DMR (Driving Monitoring Recorder) installed on 20 commercial vehicles, in order to assess the implications for driver behavior and accidents. The data suggest that the accident mechanism can be explained in terms of situation-specific factor and behavior of drivers just before accident that is, their attitude to the handing and control of vehicles. The data might offer a new information for practical driver education. 3 refs., 9 figs., 1 tab.

  14. Expert software for accident identification

    Each type of an accident in a Nuclear Power Plant (NPP) causes immediately after the start of the accident variations of physical parameters that are typical for that type of the accident thus enabling its identification. Examples of these parameter are: decrease of reactor coolant system pressure, increase of radiation level in the containment, increase of pressure in the containment. An expert software enabling a fast preliminary identification of the type of the accident in Krsko NPP has been developed. As input data selected typical parameters from Emergency Response Data System (ERDS) of the Krsko NPP are used. Based on these parameters the expert software identifies the type of the accident and also provides the user with appropriate references (past analyses and other documentation of such an accident). The expert software is to be used as a support tool by an expert team that forms in case of an emergency at Slovenian Nuclear Safety Administration (SNSA) with the task to determine the cause of the accident, its most probable scenario and the source term. The expert software should provide initial identification of the event, while the final one is still to be made after appropriate assessment of the event by the expert group considering possibility of non-typical events, multiple causes, initial conditions, influences of operators' actions etc. The expert software can be also used as an educational/training tool and even as a simple database of available accident analyses. (author)

  15. Shipping container response to severe highway and railway accident conditions: Appendices

    Fischer, L.E.; Chou, C.K.; Gerhard, M.A.; Kimura, C.Y.; Martin, R.W.; Mensing, R.W.; Mount, M.E.; Witte, M.C.

    1987-02-01

    Volume 2 contains the following appendices: Severe accident data; truck accident data; railroad accident data; highway survey data and bridge column properties; structural analysis; thermal analysis; probability estimation techniques; and benchmarking for computer codes used in impact analysis. (LN)

  16. Shipping container response to severe highway and railway accident conditions: Appendices

    Volume 2 contains the following appendices: Severe accident data; truck accident data; railroad accident data; highway survey data and bridge column properties; structural analysis; thermal analysis; probability estimation techniques; and benchmarking for computer codes used in impact analysis. (LN)

  17. Calculating nuclear accident probabilities from empirical frequencies

    Ha-Duong, Minh; Journé, V.

    2014-01-01

    International audience Since there is no authoritative, comprehensive and public historical record of nuclear power plant accidents, we reconstructed a nuclear accident data set from peer-reviewed and other literature. We found that, in a sample of five random years, the worldwide historical frequency of a nuclear major accident, defined as an INES level 7 event, is 14 %. The probability of at least one nuclear accident rated at level ≥4 on the INES scale is 67 %. These numbers are subject...

  18. Trend of Elevator-Related Accidents in Tehran

    Ali Khaji; Syyed Mohammad Ghodsi

    2014-01-01

    Background:   Elevator-related accidents are uncommon, but can cause significant injury. However, little data exist on these types of accidents. To compile and analyze accident data involving elevators in an effort to eliminate or at least significantly reduce such accidents. Methods: In this retrospective study we investigated 1,819 cases of elevator-related accidents during a four-year period (1999-2003) in Tehran. The data were obtained from the Tehran Safety Services & Fire Fighting Organ...

  19. Development of simplified evaluation models for the first power peak during a criticality accident and its verification by the TRACE code simulated results based on CRAC experimental data

    In a reprocessing facility or a part of uranium fuel manufacturing facility where nuclear fuel solution is processed, one could frequently observe a series of power peaks with the first highest right after a criticality accident. The criticality alarm system (CAS) is designed to detect the first power peak and immediately warn workers around the reacting material by any means such as sounding alarms. Consequently, exposure of the workers could be minimized by an immediate and effective evacuation. Therefore in the design and installation of CAS, it is necessary to estimate the magnitude of the first power peak and to set up the threshold point for CAS initiating alarm. Furthermore, it is necessary to estimate the potential level of accidental exposure of workers so as to decide whether or not it is appropriate to install CAS for any compartment. In this report, simplified evaluation models to estimate the minimum scale of the first power peak and the released energy during a criticality accident are derived only by theoretical consideration for use in the design of CAS to set up the threshold point triggering the alarm signal. Other simplified evaluation models are in the same way derived to estimate the maximum scale of the first power peak and the released energy and to predict possible exposure level of workers to be used to judge the appropriateness of CAS installation. These evaluation models are shown to have adequate margin in predicting the minimum and maximum scale of criticality accidents by comparing their results with French CRAC experiment data. Furthermore, comparison of the maximum scale of the first power peak simplified evaluation, has been made with simulated results by the TRACE code based on the extrapolated conditions predicted by the CRAC experiment data to verify the effectiveness of the derived evaluation models

  20. Biological effects of radiation accidents on humans. September 1970-February 1990 (a Bibliography from the NTIS data base). Report for September 1970-February 1990

    This bibliography contains citations concerning the impact of radiation accidents on humans. Radiation exposure assessment for determining appropriate medical treatment is discussed. The effects of ingesting food or inhaling air irradiated by accident fallout are considered. Follow-up studies of the survivors of specific nuclear accidents are included in an attempt to evaluate long and short term health effects of accidents. (This updated bibliography contains 224 citations, 62 of which are new entries to the previous edition.)

  1. Assessment of accident risks in the CRBRP. Volume 2. Appendices

    None

    1977-03-01

    Appendices to Volume I include core-related accident-sequence definition, CRBRP risk-assessment sequence-probability determinations, failure-probability data, accident scenario evaluation, radioactive material release analysis, ex-core accident analysis, safety philosophy and design features, calculation of reactor accident consequences, sensitivity study, and risk from fires.

  2. Bus accident severity and passenger injury: evidence from Denmark

    Prato, Carlo Giacomo; Kaplan, Sigal

    2014-01-01

    principle of sustainable transit and advance the vision “every accident is one too many”. Methods Bus accident data were retrieved from the national accident database for the period 2002–2011. A generalized ordered logit model allows analyzing bus accident severity and a logistic regression enables...

  3. Ship accident studies

    This paper summarizes ship accident studies performed by George G. Sharp, Inc. for the U.S. Maritime Administration in connection with the Nuclear Ship Project. Casualties studied include fires/explosions, groundings and collisions for which a method for calculating probability on a specific route was developed jointly with the Babcock and Wilcox Co. Casualty data source was the Liverpool's Underwriters Association Casualty Returns

  4. Numerical modelling and parametric study of the atmospheric dispersion after radionuclide releases: the Chernobyl accident and the Algeciras incident. Comparison with observation data

    Full text: The attempts of modelling the release following upon the Chernobyl accident and the Algeciras incident are reported. Computing power and observation database are used for sensitivity and parametric studies. The meteorological mesoscale model MM5 is nudged with the ERA-40 reanalysis to simulate the meteorological conditions used by the dispersion model, POLAIR3D. In case of the Chernobyl accident the points of interest are many: the representativity of the meteorological simulations is evaluated using observations with a special focus on precipitation events. The radionuclide dispersion, the dry deposition and scavenging simulated by POLAIR3D are compared with European measurements of activities and depositions. Results of the sensitivity studies are done to evaluate the impact of the deposition parameterizations and source-term characteristics (height of release, quantities). The time dynamic of the contaminated cloud is also investigated with regard to the arrival time on different countries. Similarly, for the Algeciras release, sensitivity to the meteorological fields, source term and depletion processes are analyzed. For the available activity concentrations in the air, data-model comparisons are performed. (author)

  5. Collection, documentation and assessment of data measured in the Federal Republic of Germany after the reactor accident in the nuclear power plant at Chernobyl

    Representative for the Federal Republic of Germany, regions were selected that showed a lesser (Hesse) and higher (Bavaria) contamination. The contamination in individual environmental media (milk, i.a.) was demonstrated by values measured and assessed on a prognostic model and subsequently compared with each other. The intake was then evaluated on the basis of food basket and total body measurement data for determining the dose for various age groups and regions. Against those from food baskets, the doses derived from total body measurements were generally lower by 20-60%. This indicates change in consumption habits, adherence to recommendations and the effect of countermeasures, particularly in the higher contaminated southern region of the Federal Republic of Germany. The intake and dose assessments were compared to those measured during the time of contamination from fallout due to nuclear weapons tests. External radiation exposure and cumulative dose from fallout due to nuclear weapons tests and the Chernobyl accident were calculated. In 1986, the radiation exposure from external sources and from ingestion in consequence of the reactor accident had reached in the region of highest contamination (County of Berchtesgaden) 40%, in the lesser contaminated region (Hesse) about 5% of the average natural radiation exposure. (orig./HP)

  6. Rapid urease test and endoscopic data in dynamic in case of peptic ulcers in former Chernobyl accident clean-up workers

    111 peptic ulcer patients former Chernobyl accident clean-up workers were examined. The patients have been working in the damaged zone during 1986-87 years receiving small radiation dosages. Chronic peptic gastric and duodenal ulcers appeared in them later. The goal of the trial is to investigate the effectiveness of Helicobacter pylori eradication measures in triple-therapy course of medium duration (10 days) include ranitidine, amoxycillinum, and methronidazolum. Upper gastrointestinal endoscopy was accompanied by rapid urease test. The test was repeated after a 1-year period. Analysing the data results we ascertain that the prolonged success of triple-therapy is rather ineffective and have unclear correlation with endoscopic data. This is much evident in case of gastric ulcers. These results testify that clinical course of peptic ulcers in case of post-radiation syndrome differs from the same in population. (authors)

  7. Accidents with biological material in workers

    Cleonice Andréa Alves Cavalcante; Elisângela Franco de Oliveira Cavalcante; Maria Lúcia Azevedo Ferreira de Macêdo; Eliane Cavalcante dos Santos; Soraya Maria de Medeiros

    2013-01-01

    The objective was to describe the accidents with biological material occurred among workers of Rio Grande do Norte, Brazil, between 2007 and 2009. Secondary data were collected in the National Notifiable Diseases Surveillance System by exporting data to Excel using Tabwin. Among the types of occupational accidents reported in the state, the biological accidents (no. = 1,170) accounted for 58.3% with a predominance of cases among nurses (48.6%). The percutaneous exposure was the most frequent ...

  8. Air medical transport of patients from offshore oil and gas facilities. Historical accident data and initial experience.

    Taylor, D H; Casta, R; Walker, V; Collier, F; Fromm, R E

    1993-01-01

    The offshore petroleum exploration and production industry (OSI) is isolated from traditional means of access to emergent health care and may benefit from the unique attributes of helicopter air medical transport. This study was undertaken to review the incidence of OSI-related incidents, injuries and deaths, and report the initial experience of a civilian hospital-based helicopter air transport program in the evacuation of offshore patients. It was learned that the mean annual incidence of major OSI accidents from 1980 to 1986 was 19.1 (+/- 7.0). Mean annual mortality and reported injury were 14.7 (+/- 7.6) and 36.7 (+/- 25.4) patients respectively. Fires and explosions were the most frequently reported events at 62 per year (+/- 11.5/year). Nine OSI patients were evacuated by helicopter during the study's eight-month pilot period (seven for trauma and two for medical illness). One of the nine patients had been exposed to a potentially hazardous substance, requiring changes in the air medical team's operations, aircraft and equipment. The study shows that the offshore petroleum environment is ideally suited for air medical transport, as injuries are common and medical illnesses are to be expected. However, air medical programs operating offshore must deal with additional regulatory requirements and develop operational procedures to ensure safety during these flights. PMID:10127859

  9. Criticality Accident

    At a meeting of electric utility presidents in October, 1999, the Federation Power Companies (FEPCO) officially decided to establish a Japanese version of WANO, following the JCO criticality accident. The Japanese WANO is expected to be launched by the end of the year: initially, with some 30 private sector companies concerned with nuclear fuel. It is said that the private sector had to make efforts to ensure that safety was the most important value in management policy throughout the industry, and that comprehensive inspections would be implemented. In anything related to nuclear energy, sufficient safety checks are required even for the most seemingly trivial matters. Therefore, the All-Japan Council of Local Governments with Atomic Power Stations has already proposed to the Japanese government that it should enact the special law for nuclear emergency, providing that the unified responsibility for nuclear disaster prevention should be shifted to the national government, since the nuclear disaster was quite special from the viewpoint of its safety regulation and technical aspects. (G.K.)

  10. A reactivity accidents simulation of the Fort Saint Vrain HTGR

    A reactivity accidents analysis of the Fort Saint Vrain HTGR was made. The following accidents were analysed 1) A rod pair withdrawal accident during normal operation, 2) A rod pair ejection accident, 3) A rod pair withdrawal accident during startup operations at source levels and 4) Multiple rod pair withdrawal accident. All the simulations were performed by using the BLOOST-6 nuclear code The steady state reactor operation results obtained with the code were consistent with the design reactor data. The numerical analysis showed that all accidents - except the first one - cause particle failure. (author)

  11. Risk and protection factors in fatal accidents.

    Dupont, Emmanuelle; Martensen, Heike; Papadimitriou, Eleonora; Yannis, George

    2010-03-01

    This paper aims at addressing the interest and appropriateness of performing accident severity analyses that are limited to fatal accident data. Two methodological issues are specifically discussed, namely the accident-size factors (the number of vehicles in the accident and their level of occupancy) and the comparability of the baseline risk. It is argued that - although these two issues are generally at play in accident severity analyses - their effects on, e.g., the estimation of survival probability, are exacerbated if the analysis is limited to fatal accident data. As a solution, it is recommended to control for these effects by (1) including accident-size indicators in the model, (2) focusing on different sub-groups of road-users while specifying the type of opponent in the model, so as to ensure that comparable baseline risks are worked with. These recommendations are applied in order to investigate risk and protection factors of car occupants involved in fatal accidents using data from a recently set up European Fatal Accident Investigation database (Reed and Morris, 2009). The results confirm that the estimated survival probability is affected by accident-size factors and by type of opponent. The car occupants' survival chances are negatively associated with their own age and that of their vehicle. The survival chances are also lower when seatbelt is not used. Front damage, as compared to other damaged car areas, appears to be associated with increased survival probability, but mostly in the case in which the accident opponent was another car. The interest of further investigating accident-size factors and opponent effects in fatal accidents is discussed. PMID:20159090

  12. Severe accident phenomena

    Severe accidents are nuclear reactor accidents in which the reactor core is substantially damaged. The report describes severe reactor accident phenomena and their significance for the safety of nuclear power plants. A comprehensive set of phenomena ranging from accident initiation to containment behaviour and containment integrity questions are covered. The report is based on expertise gained in the severe accident assessment projects conducted at the Technical Research Centre of Finland (VTT). (49 refs., 32 figs., 12 tabs.)

  13. Modeling secondary accidents identified by traffic shock waves.

    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. PMID:26687540

  14. Les principaux accidents de déversements pétroliers en mer et la banque de données de l'Institut Français du Pétrole sur les accidents de navires (1955-1979 The Principal Offshore Oil-Spill Accidents and the Tanker Casualties Data-Bank(1955-1979 Compiled by Institut Français du Pétrole

    Bertrand A. R. V.

    2006-11-01

    Full Text Available Après avoir exposé les principaux problèmes posés par le déversement accidentel de pétrole en mer sous ses aspects qualitatifs et quantitatifs, puis rappelé un certain nombre de données tirées d'études antérieures, nous indiquons les résultats de l'activité documentaire de l'Institut Français du Pétrole dans ce domaine : -liste d'accidents ayant donné lieu à un déversement supérieur à 500 t et d'origines diverses (navires, plates-formes, oléoducs, installations côtières; - banque de données sur les accidents de navires. Cette banque concernant plus de 400 accidents survenus de 1955 à 1979 a permis d'établir plusieurs corrélations et de préciser quelques points. En particulier si le nombre d'accidents « principaux » ne semble pas avoir augmenté d'une façon significative au cours de ces dernières années ainsi que le déversement global dû aux accidents, celui-ci nous paraît avoir été sous-estimé dans les évaluations antérieures. II devrait s'élever à 500 000 t/an au lieu de 300 000 t/an, chiffre donné en 1973 par la National Academy of Sciences américaine et constamment repris depuis dans de nombreux rapports et publications. After describing the main problems raised by occidental offshore oil spills from a qualitative and quantitative standpoint and then reviewing various data token from previous reports, this article goes on to describe the results of documentary activity by Institut Français du Pétrole in this field - list of accidents resulting in a spill of more than 500 t and coming from various origins (ships, platforms, pipelines, coastal installations; - data bank on ship accidents. This data bank includes more thon 400 accidents occurring between 1955 and 1979. It reveals various correlations and specific points. In particular, whereas the number of « principal » accidents does not seem to have appreciably increased in the last few years nor has the overall amount thus spilled, these data

  15. Monitoring severe accidents using AI techniques

    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.

  16. CARNSORE: Hypothetical reactor accident study

    Two types of design-basis accident and a series of hypothetical core-melt accidents to a 600 MWe reactor are described and their consequences assessed. The PLUCON 2 model was used to calculate the consequences which are presented in terms of individual and collective doses, as well as early and late health consequences. The site proposed for the nucelar power station is Carnsore Point, County Wexford, south-east Ireland. The release fractions for the accidents described are those given in WASH-1400. The analyses are based on the resident population as given in the 1979 census and on 20 years of data from the meteorological stations at Rosslare Harbour, 8.5 km north of the site. The consequences of one of the hypothetical core-melt accidents are described in detail in a meteorological parametric study. Likewise the consequences of the worst conceivable combination of situations are described. Finally, the release fraction in one accident is varied and the consequences of a proposed, more probable ''Class 9 accident'' are presented. (author)

  17. ACCIDENTS AND UNSCHEDULED EVENTS ASSOCIATED WITH NON-NUCLEAR ENERGY RESOURCES AND TECHNOLOGY

    Accidents and unscheduled events associated with non-nuclear energy resources and technology are identified for each step in the energy cycle. Both natural and anthropogenic causes of accidents or unscheduled events are considered. Data concerning these accidents are summarized. ...

  18. The accident of Chernobyl

    RBMK reactors (reactor control, protection systems, containment) and the nuclear power plant of Chernobyl are first presented. The scenario of the accident is given with a detailed chronology. The actions and consequences on the site are reviewed. This report then give the results of the source term estimation (fision product release, core inventory, trajectories, meteorological data...), the radioactivity measurements obtained in France. Health consequences for the French population are evoked. The medical consequences for the population who have received a high level of doses are reviewed

  19. Accident scenario diagnostics with neural networks

    Nuclear power plants are very complex systems. The diagnoses of transients or accident conditions is very difficult because a large amount of information, which is often noisy, or intermittent, or even incomplete, need to be processed in real time. To demonstrate their potential application to nuclear power plants, neural networks axe used to monitor the accident scenarios simulated by the training simulator of TVA's Watts Bar Nuclear Power Plant. A self-organization network is used to compress original data to reduce the total number of training patterns. Different accident scenarios are closely related to different key parameters which distinguish one accident scenario from another. Therefore, the accident scenarios can be monitored by a set of small size neural networks, called modular networks, each one of which monitors only one assigned accident scenario, to obtain fast training and recall. Sensitivity analysis is applied to select proper input variables for modular networks

  20. Aircraft Loss-of-Control Accident Analysis

    Belcastro, Christine M.; Foster, John V.

    2010-01-01

    Loss of control remains one of the largest contributors to fatal aircraft accidents worldwide. Aircraft loss-of-control accidents are complex in that they can result from numerous causal and contributing factors acting alone or (more often) in combination. Hence, there is no single intervention strategy to prevent these accidents. To gain a better understanding into aircraft loss-of-control events and possible intervention strategies, this paper presents a detailed analysis of loss-of-control accident data (predominantly from Part 121), including worst case combinations of causal and contributing factors and their sequencing. Future potential risks are also considered.

  1. Documentation for Three Wake Vortex Model Data Sets from Simulation of Flight 587 Wake Vortex Encounter Accident Case

    Switzer, George F.

    2008-01-01

    This document contains a general description for data sets of a wake vortex system in a turbulent environment. The turbulence and thermal stratification of the environment are representative of the conditions on November 12, 2001 near John F. Kennedy International Airport. The simulation assumes no ambient winds. The full three dimensional simulation of the wake vortex system from a Boeing 747 predicts vortex circulation levels at 80% of their initial value at the time of the proposed vortex encounter. The linked vortex oval orientation showed no twisting, and the oval elevations at the widest point were about 20 meters higher than where the vortex pair joined. Fred Proctor of NASA?s Langley Research Center presented the results from this work at the NTSB public hearing that started 29 October 2002. This document contains a description of each data set including: variables, coordinate system, data format, and sample plots. Also included are instructions on how to read the data.

  2. SEVERE ACCIDENT MANAGEMENT TRAINING

    The purpose of this paper is (a) to define the International Atomic Energy Agency's role in the area of severe accident management training, (b) to briefly describe the status of representative severe accident analysis tools designed to support development and validation of accident management guidelines, and more recently, simulate the accident with sufficient accuracy to support the training of technical support and reactor operator staff, and (c) provide an overview of representative design-specific accident management guidelines and training. Since accident management and the development of accident management validation and training software is a rapidly evolving area, this paper is also intended to evolve as accident management guidelines and training programs are developed to meet different reactor design requirements and individual national requirements

  3. Traffic Congestion and Accidents

    Schrage, Andrea

    2006-01-01

    Obstructions caused by accidents can trigger or exacerbate traffic congestion. This paper derives the efficient traffic pattern for a rush hour with congestion and accidents and the corresponding road toll. Compared to the model without accidents, where the toll equals external costs imposed on drivers using the road at the same time, a new insight arises: An optimal toll also internalizes the expected increase in future congestion costs. Since accidents affect more drivers if traffic volumes...

  4. Public opinion on atomic energy after JCO accident

    JCO accident happened on September 30, 1999. This book deals with the public opinion of atomic energy after JCO accident in Japan and comparison with that of USA and France. The analysis of public opinion structure is also shown. The important chapter is the eighth chapter an opinion survey after the accident, of which sampling areas consisted of three areas such as JCO accident area, the nuclear power plants and the general cities. The analytical results of data showed that the public opinion in Tokai-mura and Naka-machi, the JCO accident area, indicated moderate opinions. It is the interesting results were obtained that the moderate tendency of opinion was in order JCO accident area, the nuclear power plants and the general cities. People's attitude toward nuclear energy related to their social values. Abstract of JCO accident, JCO structure, the effects of accident on the environment and news stories about the accident are reported. (S.Y.)

  5. Occupational blood exposure accidents in the Netherlands.

    Wijk, P.T.L. van; Schneeberger, P.M.; Heimeriks, K.; Boland, G.J.; Karagiannis, I.; Geraedts, J.; Ruijs, W.L.M.

    2010-01-01

    BACKGROUND: To make proper evaluation of prevention policies possible, data on the incidence and associated medical costs of occupational blood exposure accidents in the Netherlands are needed. METHODS: Descriptive analysis of blood exposure accidents and risk estimates for occupational groups. Cost

  6. Psychology of nuclear accidents

    Tysoe, M.

    1983-03-31

    Incidents involving nuclear weapons are described, as well as the accident to the Three Mile Island-2 reactor. Methods of assessment of risks are discussed, with particular reference to subjective judgements and the possible role of human error in civil nuclear accidents. Accidents or misunderstandings in communication or human actions which might lead to nuclear war are also discussed.

  7. SAMSON: Severe Accident Management System Online Network

    SAMSON, Severe Accident Management System Online Network, is a computational tool used in the event of a nuclear power plant accident by accident managers in the Technical Support Centers (TSC) and Emergency Offsite Facilities (EOF). SAMSON examines over 150 status points monitored by nuclear power plant process computers during a severe accident and makes predictions about when core damage, support plate failure, and reactor vessel failure will occur. These predictions are based on the current state of the plant assuming that all safety equipment not already operating will fail. The status points analyzed include radiation levels, flow rates, pressure levels, temperatures and water levels. SAMSON uses an expert system as well as neural networks trained with the back propagation learning algorithm to make predictions. Previous training on data from accident analysis code allows SAMSON to associate different states in the plant with different times to critical failures. The accidents currently recognized by SAMSON include steam generator tube ruptures (SGTR), with breaks ranging from one tube to eights tubes, and loss of coolant accidents (LOCA), with breaks ranging from 0.001 square feet in size to breaks 3.0 square feet. SAMSON contains several neural networks for each accident type and break size, and chooses the correct network after accident classification by in expert system. SAMSON also provides information concerning the status of plant sensors and recovery strategies

  8. Radioactive materials transport accident analysis

    Over the last 25 years, one of the major issues raised regarding radioactive material transportation has been the risk of severe accidents. While numerous studies have shown that traffic fatalities dominate the risk, modeling the risk of severe accidents has remained one of the most difficult analysis problems. This paper will show how models that were developed for nuclear spent fuel transport accident analysis can be adopted to obtain estimates of release fractions for other types of radioactive material such as vitrified highlevel radioactive waste. The paper will also show how some experimental results from fire experiments involving low level waste packaging can be used in modeling transport accident analysis with this waste form. The results of the analysis enable an analyst to clearly show the differences in the release fractions as a function of accident severity. The paper will also show that by placing the data in a database such as ACCESS trademark, it is possible to obtain risk measures for transporting the waste forms along proposed routes from the generator site to potential final disposal sites

  9. Economic Upturns are good for Your Heart but Watch out for Accidents: A Study on Swedish Regional Data 1976-2005

    Svensson, Mikael

    2010-01-01

    Abstract This paper explores the relationship between the regional unemployment rate and total and cause-specific mortality in Sweden during 1976-2005. Overall mortality is unrelated to changes in the unemployment rate, while the biggest cause of death (heart disease) decreases when the unemployment rate decreases. At the same time other accidents, including job-related accidents, increase when the unemployment rate decreases. Swedish evidence provides no support for the US researc...

  10. Exposure levels for persons involved in recovery operations following the Chernobyl accident in 1986-1987 and dosimetric data verification

    It is considered the organization of individual dosimetric monitoring (IDM) within 30-km zone around Chernobyl nuclear power plant (CNPP) in 1986 for different contingents of recovery workers: the CNPP personnel, Management for Construction 605 (MC-605), military recovery workers, persons assigned to 30-km zone. It is concluded that the quality of IDM had decreased in the following series: the MC-605 personnel, the CNPP personnel, the assigned persons, and military units. The method of dosimetric data verification for recovery workers in 1986 is presented. The results obtained by this method correspond to the results of the experts' estimation. Using the theory of hybrid lognormal distribution it was obtained, in our opinion, real external dose distribution for all the recovery workers. It was estimated that 7% of recovery workers received doses more than 0.25 Gy. Also, the data on values of mean and collective doses for different contingents, as well as for all persons involved in recovery operations is presented. 14 refs., 18 figs

  11. Supervisor's accident investigation handbook

    This pamphlet was prepared by the Environmental Health and Safety Department (EH and S) of Lawrence Berkeley Laboratory (LBL) to provide LBL supervisors with a handy reference to LBL's accident investigation program. The publication supplements the Accident and Emergencies section of LBL's Regulations and Procedures Manual, Pub. 201. The present guide discusses only accidents that are to be investigated by the supervisor. These accidents are classified as Type C by the Department of Energy (DOE) and include most occupational injuries and illnesses, government motor-vehicle accidents, and property damages of less than $50,000

  12. Experimental data report for test TS-3 Reactivity Initiated Accident test in the NSRR with pre-irradiated BWR fuel rod

    This report presents experimental data for Test TS-3 which was the third test in a series of Reactivity Initiated Accident (RIA) tests using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in September, 1990. Test fuel rod used in the Test TS-3 was a short-sized BWR (7 x 7) type rod which was re-fabricated from a commercial rod irradiated in the Tsuruga Unit 1 power reactor of Japan Atomic Power Co. The fuel had an initial enrichment of 2.79 % and a burnup of 26 Gwd/tU. A pulse irradiation of the test fuel rod was performed under a cooling condition of stagnant water at atmospheric pressure and at ambient temperature which simulated a BWR's cold start-up RIA event. The energy deposition of the fuel rod in this test was evaluated to be 94 ± 4 cal/g · fuel (88 ± 4 cal/g · fuel in peak fuel enthalpy) and no fuel failure was observed. Descriptions on test conditions, test procedures, transient behavior of the test rod during the pulse irradiation, and results of pre-pulse and post-pulse irradiation examinations are described in this report. (author)

  13. Experimental data report for test TS-5 Reactivity Initiated Accident test in the NSRR with pre-irradiated BWR fuel rod

    This report presents experimental data for Test TS-5 which was the fifth test in a series of Reactivity Initiated Accident (RIA) tests using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in January, 1993. Test fuel rod used in the Test TS-5 was a short-sized BWR (7x7) type rod which was re-fabricated from a commercial rod irradiated in the Tsuruga Unit 1 power reactor of Japan Atomic Power Co. The fuel had an initial enrichment of 2.79% and a burnup of 26GWd/tU. A pulse irradiation of the test fuel rod was performed under a cooling condition of stagnant water at atmospheric pressure and at ambient temperature which simulated a BWR's cold start-up RIA event. The nominal energy deposition of 117±5cal/g·fuel (98±4cal/g·fuel in peak fuel enthalpy) was subjected to the test fuel rod and no fuel failure was observed in the test. The test fuel was pulse irradiated in a flow shroud which simulates fuel/water ratio in the commercial assembly. Descriptions on test conditions, test procedures, transient behavior of the test rod during the pulse irradiation, and results of pre-pulse and post-pulse irradiation examinations are described in this report. (author)

  14. Framework for accident management

    Accident management is an essential element of the Nuclear Regulatory Commission (NRC) Integration Plan for the closure of severe accident issues. This element will consolidate the results from other key elements; such as the Individual Plant Examination (IPE), the Containment Performance Improvement, and the Severe Accident Research Programs, in a form that can be used to enhance the safety programs for nuclear power plants. The NRC is currently conducting an Accident Management Program that is intended to aid in defining the scope and attributes of an accident management program for nuclear power plants. The accident management plan will ensure that a plant specific program is developed and implemented to promote the most effective use of available utility resources (people and hardware) to prevent and mitigate severe accidents. Hardware changes or other plant modifications to reduce the frequency of severe accidents are not a central aim of this program. To accomplish the outlined objectives, the NRC has developed an accident management framework that is comprised of five elements: (1) accident management strategies, (2) training, (3) guidance and computational aids, (4) instrumentation, and (5) delineation of decision making responsibilities. A process for the development of an accident management program has been identified using these NRC framework elements

  15. Chernobyl accident

    The examination of the radioelements in macromicetae taken in the area of Como's Groane and in other areas near Lakes of Como and Maggiore and a few samples in Pine' di Trento are reported. A number of samples has been collected and analyzed at Joint Research Center, Ispra. A sampling of many pieces has been picked up by the Circolo Micologico Plinio il Vecchio and by the Unita' Sanitarie of Como and Varese. The various samples are subdivided for specie and the denomination for each one of them is given. The foundamental sampling is dated atumn 1986, a second sampling is made in autumn 1987. Gamma spectrometry has revealed the presence of many radiosotopes due to the Chernobyl fall-out. as Cs137, Cs134 and Ag110 (metastable); levels of Potassium 40, a natural radioactive element have been also measured. A discussion of results is presented and the comparison among data of the 1986 season and the 1987 one

  16. Accident proneness, does it exist? A review and meta-analysis

    Visser, Ellen; Pijl, Ysbrand J.; Stolk, Ronald P.; Neeleman, Jan; Rosmalen, Judith G M

    2007-01-01

    Accident related health problems have been suggested to cluster within persons. This phenomenon became known as accident proneness and has been a subject of many discussions. This study provides an overview of accident proneness. Therefore, 79 articles with empirical data on accident rates were identified from databases Embase, Medline, and Psychinfo. First, definitions of accidents varied highly, but most studies focused on accidents resulting in injuries requiring medical attention. Second,...

  17. Assessing economic consequences of radiation accidents

    This project reviewed the literature on the economic consequences of accidents to determine the availability of assessment methods and data and their applicability to the high-level radioactive waste (HLW) disposal system before closure; determined needs for expansion, revision, or adaptation of methods and data for modeling economic consequences of accidents of the scale projected for the disposal system; and gathered data that might be useful for the needed revisions. 8 refs., 1 tab

  18. Characterization of cleaners accidents in the Portuguese service sector

    Cabeças, José Miquel

    2008-01-01

    This paper characterizes work accidents at Portuguese industrial cleaning companies, operating in the service sector, through the application of ESAW methodology. Data was codified based on the analysis of 748 accident claims to insurance companies (number of days lost 1 working day) in 3 large industrial cleaning companies for the period 2001-2003. Slipping and falling in the same level was the main deviation from the normal working process in the moment of the accident (in 25% of the accid...

  19. Framework for accident management

    A program is being conducted to establish those attributes of a severe accident management plan which are necessary to assure effective response to all credible severe accidents and to develop guidance for their incorporation in a plant's Accident Management Plan. This program is one part of the Accident Management Research Program being conducted by the U. S. Nuclear Regulatory Commission (NRC). The approach used in establishing attributes and developing guidance includes three steps. In the first step the general attributes of an accident management plan were identified based on: (1) the objectives established for the NRC accident management program, (2) the elements of an accident management framework identified by the NRC, and (3) a review of the processes used in developing the currently used approach for classifying and analyzing accidents. For the second step, a process was defined that uses the general attributes identified from the first step to develop an accident management plan. The third step applied the process defined in the second step at a nuclear power plant to refine and develop it into a benchmark accident management plan. Step one is completed, step two is underway and step three has not yet begun

  20. Visualization of Traffic Accidents

    Wang, Jie; Shen, Yuzhong; Khattak, Asad

    2010-01-01

    Traffic accidents have tremendous impact on society. Annually approximately 6.4 million vehicle accidents are reported by police in the US and nearly half of them result in catastrophic injuries. Visualizations of traffic accidents using geographic information systems (GIS) greatly facilitate handling and analysis of traffic accidents in many aspects. Environmental Systems Research Institute (ESRI), Inc. is the world leader in GIS research and development. ArcGIS, a software package developed by ESRI, has the capabilities to display events associated with a road network, such as accident locations, and pavement quality. But when event locations related to a road network are processed, the existing algorithm used by ArcGIS does not utilize all the information related to the routes of the road network and produces erroneous visualization results of event locations. This software bug causes serious problems for applications in which accurate location information is critical for emergency responses, such as traffic accidents. This paper aims to address this problem and proposes an improved method that utilizes all relevant information of traffic accidents, namely, route number, direction, and mile post, and extracts correct event locations for accurate traffic accident visualization and analysis. The proposed method generates a new shape file for traffic accidents and displays them on top of the existing road network in ArcGIS. Visualization of traffic accidents along Hampton Roads Bridge Tunnel is included to demonstrate the effectiveness of the proposed method.

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

    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

  2. Road Traffic Accidents in Kazakhstan

    Alma Aubakirova

    2013-03-01

    Full Text Available Background: The article provides the analysis of death rates in road traffic accidents in Kazakhstan from 2004 to 2010 and explores the use of sanitary aviation.Methods: Data of fatalities caused by road traffic accidents were collected and analysed. Descriptive and analytical methods of epidemiology and biomedical statistics were applied.Results: Totaly 27,003 people died as a result of road traffic accidents in this period. The death rate for the total population due to road traffic accidents was 25.0±2.10/0000. The death rate for men was (38.3±3.20/0000, which was higher (P<0.05 than that for women (12.6±1.10/0000. High death rates in the entire male population were identified among men of 30-39 years old, whereas the highest rates for women were attributed to the groups of 50-59 years old and 70-79 years old. In time dynamics, death rates tended to decrease: the total population (Тdec=−2.4%, men (Тdec=−2.3% and women (Тdec=−1.4%. When researching territorial relevance, the rates were established as low (to 18.30/0000, average (between18.3 and24.00/0000 and high (from 24.00/0000 and above. Thus, the regions with high rates included Akmola region (24.30/0000, Mangistau region (25.90/0000, Zhambyl region (27.30/0000, Almaty region (29.30/0000 and South Kazakhstan region (32.40/0000.Conclusion: The identified epidemiological characteristics of the population deaths rates from road traffic accidents should be used in integrated and targeted interventions to enhance prevention of injuries in accidents.

  3. Laser accidents: Being Prepared

    Barat, K

    2003-01-24

    The goal of the Laser Safety Officer and any laser safety program is to prevent a laser accident from occurring, in particular an injury to a person's eyes. Most laser safety courses talk about laser accidents, causes, and types of injury. The purpose of this presentation is to present a plan for safety offices and users to follow in case of accident or injury from laser radiation.

  4. The Chernobyl accident consequences

    Five teen years later, Tchernobyl remains the symbol of the greater industrial nuclear accident. To take stock on this accident, this paper proposes a chronology of the events and presents the opinion of many international and national organizations. It provides also web sites references concerning the environmental and sanitary consequences of the Tchernobyl accident, the economic actions and propositions for the nuclear safety improvement in the East Europe. (A.L.B.)

  5. Communication and industrial accidents

    As, Sicco van

    2001-01-01

    This paper deals with the influence of organizational communication on safety. Accidents are actually caused by individual mistakes. However the underlying causes of accidents are often organizational. As a link between these two levels - the organizational failures and mistakes - I suggest the concept of role distance, which emphasizes the organizational characteristics. The general hypothesis is that communication failures are a main cause of role distance and accident-proneness within orga...

  6. Monitoring data related to the Chernobyl accident as measured in Israel during May-July 1986 and the assessment of the radiation doses to the population

    Environmental monitoring was undertaken on April 30 1986, to follow the effects of the Chernobyl accident on the quality of the environment in Israel. Measurements of air radioactive contamination were continuously taken to the end of July when air radioactive declined to values below 0.01 Bq/m3. Along air measurements, radioactive contamination of ground, rain and drinking water, grass, vegetation and food items such as vegetables, fruits, milk, meat etc. were taken as well. Assessment of the accumulated radiation doses due to the Chernobyl accident was conducted. The effective dose equivalent is estimated to be 46 μSv (4.6 mrem)

  7. Image computing techniques to extrapolate data for dust tracking in case of an experimental accident simulation in a nuclear fusion plant

    Camplani, M.; Malizia, A.; Gelfusa, M.; Barbato, F.; Antonelli, L.; Poggi, L. A.; Ciparisse, J. F.; Salgado, L.; Richetta, M.; Gaudio, P.

    2016-01-01

    In this paper, a preliminary shadowgraph-based analysis of dust particles re-suspension due to loss of vacuum accident (LOVA) in ITER-like nuclear fusion reactors has been presented. Dust particles are produced through different mechanisms in nuclear fusion devices, one of the main issues is that dust particles are capable of being re-suspended in case of events such as LOVA. Shadowgraph is based on an expanded collimated beam of light emitted by a laser or a lamp that emits light transversely compared to the flow field direction. In the STARDUST facility, the dust moves in the flow, and it causes variations of refractive index that can be detected by using a CCD camera. The STARDUST fast camera setup allows to detect and to track dust particles moving in the vessel and then to obtain information about the velocity field of dust mobilized. In particular, the acquired images are processed such that per each frame the moving dust particles are detected by applying a background subtraction technique based on the mixture of Gaussian algorithm. The obtained foreground masks are eventually filtered with morphological operations. Finally, a multi-object tracking algorithm is used to track the detected particles along the experiment. For each particle, a Kalman filter-based tracker is applied; the particles dynamic is described by taking into account position, velocity, and acceleration as state variable. The results demonstrate that it is possible to obtain dust particles' velocity field during LOVA by automatically processing the data obtained with the shadowgraph approach.

  8. Image computing techniques to extrapolate data for dust tracking in case of an experimental accident simulation in a nuclear fusion plant

    In this paper, a preliminary shadowgraph-based analysis of dust particles re-suspension due to loss of vacuum accident (LOVA) in ITER-like nuclear fusion reactors has been presented. Dust particles are produced through different mechanisms in nuclear fusion devices, one of the main issues is that dust particles are capable of being re-suspended in case of events such as LOVA. Shadowgraph is based on an expanded collimated beam of light emitted by a laser or a lamp that emits light transversely compared to the flow field direction. In the STARDUST facility, the dust moves in the flow, and it causes variations of refractive index that can be detected by using a CCD camera. The STARDUST fast camera setup allows to detect and to track dust particles moving in the vessel and then to obtain information about the velocity field of dust mobilized. In particular, the acquired images are processed such that per each frame the moving dust particles are detected by applying a background subtraction technique based on the mixture of Gaussian algorithm. The obtained foreground masks are eventually filtered with morphological operations. Finally, a multi-object tracking algorithm is used to track the detected particles along the experiment. For each particle, a Kalman filter-based tracker is applied; the particles dynamic is described by taking into account position, velocity, and acceleration as state variable. The results demonstrate that it is possible to obtain dust particles’ velocity field during LOVA by automatically processing the data obtained with the shadowgraph approach

  9. Image computing techniques to extrapolate data for dust tracking in case of an experimental accident simulation in a nuclear fusion plant

    Camplani, M. [Visual Information Laboratory, University of Bristol, Bristol (United Kingdom); Grupo de Tratamiento de Imágenes, E.T.S.I de Telecomunicación, Universidad Politécnica de Madrid, Madrid (Spain); Malizia, A.; Gelfusa, M.; Poggi, L. A.; Ciparisse, J. F.; Richetta, M.; Gaudio, P. [Associazione EUROFUSION-ENEA, Department of Industrial Engineering, University of Rome “Tor Vergata,” Via del Politecnico 1, 00133 Rome (Italy); Barbato, F. [Associazione EUROFUSION-ENEA, Department of Industrial Engineering, University of Rome “Tor Vergata,” Via del Politecnico 1, 00133 Rome (Italy); EPMA, Materials Science and Technology, Uberlandstrasse 129, Dubendorf CH-8600 (Switzerland); Antonelli, L. [Associazione EUROFUSION-ENEA, Department of Industrial Engineering, University of Rome “Tor Vergata,” Via del Politecnico 1, 00133 Rome (Italy); Dipartimento di Scienze di base e applicate per l’Ingegneria, Universita degli Studi di Roma La Sapienza, Roma (Italy); Salgado, L. [Grupo de Tratamiento de Imágenes, E.T.S.I de Telecomunicación, Universidad Politécnica de Madrid, Madrid (Spain); Video Processing and Understanding Laboratory, Universidad Autónoma de Madrid, Madrid (Spain)

    2016-01-15

    In this paper, a preliminary shadowgraph-based analysis of dust particles re-suspension due to loss of vacuum accident (LOVA) in ITER-like nuclear fusion reactors has been presented. Dust particles are produced through different mechanisms in nuclear fusion devices, one of the main issues is that dust particles are capable of being re-suspended in case of events such as LOVA. Shadowgraph is based on an expanded collimated beam of light emitted by a laser or a lamp that emits light transversely compared to the flow field direction. In the STARDUST facility, the dust moves in the flow, and it causes variations of refractive index that can be detected by using a CCD camera. The STARDUST fast camera setup allows to detect and to track dust particles moving in the vessel and then to obtain information about the velocity field of dust mobilized. In particular, the acquired images are processed such that per each frame the moving dust particles are detected by applying a background subtraction technique based on the mixture of Gaussian algorithm. The obtained foreground masks are eventually filtered with morphological operations. Finally, a multi-object tracking algorithm is used to track the detected particles along the experiment. For each particle, a Kalman filter-based tracker is applied; the particles dynamic is described by taking into account position, velocity, and acceleration as state variable. The results demonstrate that it is possible to obtain dust particles’ velocity field during LOVA by automatically processing the data obtained with the shadowgraph approach.

  10. Nuclear accidents and epidemiology

    A consultation on epidemiology related to the Chernobyl accident was held in Copenhagen in May 1987 as a basis for concerted action. This was followed by a joint IAEA/WHO workshop in Vienna, which reviewed appropriate methodologies for possible long-term effects of radiation following nuclear accidents. The reports of these two meetings are included in this volume, and cover the subjects: 1) Epidemiology related to the Chernobyl nuclear accident. 2) Appropriate methodologies for studying possible long-term effects of radiation on individuals exposed in a nuclear accident. Figs and tabs

  11. New technology for accident prevention

    Byne, P. [Shiftwork Solutions, Vancouver, BC (Canada)

    2006-07-01

    This power point presentation examined the effects of fatigue in the workplace and presented 3 technologies designed to prevent or monitor fatigue. The relationship between mental fatigue, circadian rhythms and cognitive performance was explored. Details of vigilance related degradations in the workplace were presented, as well as data on fatigue-related accidents and a time-line of meter-reading errors. It was noted that the direct cause of the Exxon Valdez disaster was sleep deprivation. Fatigue related accidents during the Gulf War were reviewed. The effects of fatigue on workplace performance include impaired logical reasoning and decision-making; impaired vigilance and attention; slowed mental operations; loss of situational awareness; slowed reaction time; and short cuts and lapses in optional or self-paced behaviours. New technologies to prevent fatigue-related accidents include (1) the driver fatigue monitor, an infra-red camera and computer that tracks a driver's slow eye-lid closures to prevent fatigue related accidents; (2) a fatigue avoidance scheduling tool (FAST) which collects actigraphs of sleep activity; and (3) SAFTE, a sleep, activity, fatigue and effectiveness model. refs., tabs., figs.

  12. Violent explosion after inadvertent mixing of nitric acid and isopropanol – Review 15 years later finds basic accident data corrupted, no evidence of broad learning

    Hedlund, Frank Huess; Folmer Nielsen, Merete; Hagen Mikkelsen, Sonja;

    2014-01-01

    to produce isopropyl nitrate (nitric acid 1-methylethyl ester, CAS 1712-64-7), a rocket propellant. It is argued that the accident has broad learning potential because of the widespread usage of the two chemicals across industries, the innocent nature of the human error and the severity of the...

  13. Chernobyl nuclear accident: Effects on food. April 1986-November 1989 (Citations from the Food Science and Technology Abstracts data base). Report for April 1986-November 1989

    This bibliography contains citations concerning studies and measurements of the radioactive contamination by the Chernobyl nuclear reactor accident of food and the food chain. The studies cover meat and dairy products, vegetables, fish, food chains, and radioactive contamination of agricultural farms and lands. (This updated bibliography contains 108 citations, 43 of which are new entries to the previous edition.)

  14. Chernobyl nuclear accident: effects on foods. April 1986-October 1988 (Citations from the Food Science and Technology Abstracts data base). Report for April 1986-October 1988

    This bibliography contains citations concerning studies and measurements of the radioactive contamination of the Chernobyl nuclear reactor accident of food and food chains. The studies cover meat and dairy products, vegetables, fish, food chains, and radioactive contamination of agricultural farms and lands. (Contains 65 citations fully indexed and including a title list.)

  15. Criticality accident in Argentina

    A recent criticality type accident, ocurred in Argetina, is commented. Considerations about the nature of the facility where this accident took place, its genesis, type of operation carried out on the day of the event, and the medical aspects involved are done. (Author)

  16. Radiation accidents in hospitals

    Some of the radiation accidents that have occurred in Indian hospitals and causes that led to them are reviewed. Proper organization of radiation safety minimizes such accidents. It has been pointed out that there must be technical competence and mental preparedness to tackle emergencies when they do infrequently occur. (M.G.B.)

  17. Communication and industrial accidents

    As, Sicco van

    2001-01-01

    This paper deals with the influence of organizational communication on safety. Accidents are actually caused by individual mistakes. However the underlying causes of accidents are often organizational. As a link between these two levels - the organizational failures and mistakes - I suggest the conc

  18. Compilation of accident statistics in PSE

    The objective of the investigations on transportation carried out within the framework of the 'Project - Studies on Safety in Waste Management (PSE II)' is the determination of the risk of accidents in the transportation of radioactive materials by rail. The fault tree analysis is used for the determination of risks in the transportation system. This method offers a possibility for the determination of frequency and consequences of accidents which could lead to an unintended release of radionuclides. The study presented compiles all data obtained from the accident statistics of the Federal German Railways. (orig./RB)

  19. Psychological and social aspects verified after the Goiania's radioactive accident

    Psychological and social aspects verified after the radioactive accident occurred in 1987 in Goiania - brazilian city - are discussed. With this goal was going presented a public opinion research in order to retract the Goiania's radioactive accident residual psychological effects. They were going consolidated data obtained in 1.126 interviews. Four involvement different levels groups with the accident are compared with regard to the event. The research allowed to conclude that the accident affected psychologically somehow all Goiania's population. Besides, the research allowed to analyze the professionals performance quality standard in terms of the accident

  20. Accidents with orphan sources

    The International Atomic Energy Agency has specifically defined statutory functions relating to the development of standards of safety and the provision for their application. It also has responsibilities placed on it by virtue of a number of Conventions, two of which are relevant to nuclear accidents or radiological emergencies - the Convention on Early Notification of a Nuclear Accident and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency. An overview of the way in which these functions are being applied to prevent and respond to radiological accidents, particularly those involving orphan sources, is described in this paper. Summaries of a number of such accidents and of the Agency's Action Plan relating to the safety and security of radiation sources are given. (orig.)

  1. Accident proneness, does it exist? A review and meta-analysis

    Visser, Ellen; Pijl, Ysbrand J.; Stolk, Ronald P.; Neeleman, Jan; Rosmalen, Judith G. M.

    2007-01-01

    Accident related health problems have been suggested to cluster within persons. This phenomenon became known as accident proneness and has been a subject of many discussions. This study provides an overview of accident proneness. Therefore, 79 articles with empirical data on accident rates were iden

  2. Fatal motorcycle accidents and alcohol

    Larsen, C F; Hardt-Madsen, M

    1987-01-01

    A series of fatal motorcycle accidents from a 7-year period (1977-1983) has been analyzed. Of the fatalities 30 were operators of the motorcycle, 11 pillion passengers and 8 counterparts. Of 41 operators 37% were sober at the time of accident, 66% had measurable blood alcohol concentration (BAC......); 59% above 0.08%. In all cases where a pillion passenger was killed, the operator of the motorcycle had a BAC greater than 0.08%. Of the killed counterparts 2 were non-intoxicated, 2 had a BAC greater than 0.08%, and 4 were not tested. The results advocate that the law should restrict alcohol...... consumption by pillion passengers as well as by the motorcycle operator. Suggestions made to extend the data base needed for developing appropriate alcohol countermeasures by collecting sociodemographic data on drivers killed or seriously injured should be supported....

  3. Recent trends of severe head injury in Japan Neurotrauma Data Bank with special reference to road traffic accident. Comparison of clinical features and outcome between Project 1998 and Project 2004

    This study was conducted to clarify the recent trends of severe head injury in the Japan Neurotrauma Data Bank (JNTDB) with special reference to traffic accident. In the JNTDB, the number of severely head-injured patients (Glasgow Coma Scale (GCS) score of 8 or less) were 832 in Project 1998 and 797 in Project 2004. Those were divided into 2 groups: traffic accident (TA) group, and non-TA (nTA) group. In addition, the former group was classified into 4 groups: 4 wheel vehicle (4WV) group, motorcycle (MC) group, bicycle (BC) group, and pedestrian (P) group. Analyzed here were cause of injury, age distribution, incidence of alcohol intake, means of transportation, clinical severity (GCS and injury severity score), initial CT findings (Traumatic Coma Data Bank), and outcome at discharge (Glasgow Outcome Scale). In the Project 2004; Traffic accident was less common as the cause of injury. The proportion of younger patients was lower in the TA group, especially in the 4WV and MC groups. Incidence of alcohol intake was lower in the TA group, particularly in the MC groups. Patient transfer by helicopter was more common in both the TA and nTA groups. The proportion of GCS of 3 to 5 was lower in the TA group, especially in the MC group. In the initial CT findings, type 3 of diffuse injury and evacuated mass were less frequent in both groups, and in the 4WV, BC, and P groups. Outcome at discharge: Mortality rate was lower in both groups, and in the 4WV, MC and P groups, but the percentage of good outcomes was unchanged. These results indicated the recent trends of severely head-injured patients who were injured by traffic accident. But there were some problems, such as study protocol and meaningless results, so that further verification is indispensable in the JNTDB study. (author)

  4. Accident report 1975/76

    The statistics previously published on the development of accidents were completed. It is the purpose of this accident report: 1) to present a survey of the development of the number of accidents (no radiation accidents) for the years 1960 - 1976, 2) to break down the accidents by different characteristics in order to be able to recognize the preventive measures to be taken so as to avoid further accidents, 3) to report about accidents experienced and to indicate activities performed with respect to accident prevention and health protection. (orig.)

  5. The reactor accident of Chernobyl

    The contamination, caused by the radioactivity released during the reactor accident of Chernobyl was measured in samples taken in the environment of the Karlsruhe Nuclear Research Center. The radioactivity was determined in air, fodder, milk, vegetables, other plants, foodstuffs, soil, precipitations, drinking water, sludge and other samples. Results of measurements are reported which were received with considerably more than 1000 samples. The evaluation of the data will be presented in KfK 4140. (orig.)

  6. Chernobylsk accident (Causes and Consequences)-Part 1

    Facts, project data, hypothesis, calculations, evaluations, monitoring, standard requirements and several considerations, related to causes, effects and consequences of Chernobylsk-4 accident. (M.C.K.)

  7. Development of integrated accident management assessment technology

    This project aims to develop critical technologies for accident management through securing evaluation frameworks and supporting tools, in order to enhance capabilities coping with severe accidents. For the research goal, firstly under the viewpoint of accident prevention, on-line risk monitoring system and the analysis framework for human error have been developed. Secondly, the training/supporting systems including the training simulator and the off-site risk evaluation system have been developed to enhance capabilities coping with severe accidents. Four kinds of research results have been obtained from this project. Firstly, the framework and taxonomy for human error analysis has been developed for accident management. As the second, the supporting system for accident managements has been developed. Using data that are obtained through the evaluation of off-site risk for Younggwang site, the risk database as well as the methodology for optimizing emergency responses has been constructed. As the third, a training support system, SAMAT, has been developed, which can be used as a training simulator for severe accident management. Finally, on-line risk monitoring system, DynaRM, has been developed for Ulchin 3 and 4 unit

  8. Monitoring Severe Accidents Using AI Techniques

    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

  9. Estimating the frequency of nuclear accidents

    Raju, Suvrat

    2014-01-01

    We used Bayesian methods to compare the predictions of probabilistic risk assessment -- the theoretical tool used by the nuclear industry to predict the frequency of nuclear accidents -- with empirical data. The existing record of accidents with some simplifying assumptions regarding their probability distribution is sufficient to rule out the validity of the industry's analyses at a very high confidence level. We show that this conclusion is robust against any reasonable assumed variation of...

  10. Nuclear Accidents And Associated Environmental Risk

    The paper presents a critical review on the recent view of some safety related issues concerning nuclear accident analysis and its environmental impacts. The philosophy of defence in depth, nuclear accident classification, and quantitative evaluation of environmental risk are among the issues being discussed. The problems of nuclear data harmonization and/or models, building trust and transparence between regulatory guides and public, and alternatives for relocation pathways are also addressed and evaluated

  11. Dosimetric evaluation of radiation accident situation

    The publication contains the classification of neutron spectra from different neutron sources, a chapter on neutron absorption by the human body, a diagram for neutron and photon dose estimation and for classifying persons involved in a radiation accident, the description of detectors and methods used for radiation accident analysis, a chapter on the interpretation of data from an accidental dosimetric system, and annexes. (H.S.)

  12. Persistence of airline accidents.

    Barros, Carlos Pestana; Faria, Joao Ricardo; Gil-Alana, Luis Alberiko

    2010-10-01

    This paper expands on air travel accident research by examining the relationship between air travel accidents and airline traffic or volume in the period from 1927-2006. The theoretical model is based on a representative airline company that aims to maximise its profits, and it utilises a fractional integration approach in order to determine whether there is a persistent pattern over time with respect to air accidents and air traffic. Furthermore, the paper analyses how airline accidents are related to traffic using a fractional cointegration approach. It finds that airline accidents are persistent and that a (non-stationary) fractional cointegration relationship exists between total airline accidents and airline passengers, airline miles and airline revenues, with shocks that affect the long-run equilibrium disappearing in the very long term. Moreover, this relation is negative, which might be due to the fact that air travel is becoming safer and there is greater competition in the airline industry. Policy implications are derived for countering accident events, based on competition and regulation. PMID:20618386

  13. Management of severe accidents

    The definition and the multidimensionality aspects of accident management have been reviewed. The suggested elements in the development of a programme for severe accident management have been identified and discussed. The strategies concentrate on the two tiered approaches. Operative management utilizes the plant's equipment and operators capabilities. The recovery managment concevtrates on preserving the containment, or delaying its failure, inhibiting the release, and on strategies once there has been a release. The inspiration for this paper was an excellent overview report on perspectives on managing severe accidents in commercial nuclear power plants and extending plant operating procedures into the severe accident regime; and by the most recent publication of the International Nuclear Safety Advisory Group (INSAG) considering the question of risk reduction and source term reduction through accident prevention, management and mitigation. The latter document concludes that 'active development of accident management measures by plant personnel can lead to very large reductions in source terms and risk', and goes further in considering and formulating the key issue: 'The most fruitful path to follow in reducing risk even further is through the planning of accident management.' (author)

  14. Accidents, risks and consequences

    Although the accident at Chernobyl can be considered as the worst accident in the world, it could have been worse. Other far worse situations are considered, such as a nuclear weapon hitting a nuclear reactor. Indeed the accident at Chernobyl is compared to a nuclear weapon. The consequences of Chernobyl in terms of radiation levels are discussed. Although it is believed that a similar accident could not occur in the United Kingdom, that possibility is considered. It is suggested that emergency plans should be made for just such an eventuality. Even if Chernobyl could not happen in the UK, the effects of accidents are international. The way in which nuclear reactor accidents happen is explored, taking the 1957 Windscale fire, Three Mile Island and Chernobyl as examples. Reactor designs and accident scenarios are considered. The different reactor designs are listed. As well as the Chernobyl RBMK design it is suggested that the light water reactors also have undesirable features from the point of view of safety. (U.K.)

  15. Accident risks in nuclear facilities. January 1984-April 1988 (Citations from the NTIS data base). Report for January 1984-April 1988

    This bibliography contains citations concerning 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 and the utilzation of computer models in risk analysis are also included. (This updated bibliography contains 368 citations, 104 of which are new entries to the previous edition.)

  16. Accident risks in nuclear facilities. January 1984-April 1988 (Citations from the NTIS data base). Report for January 1984-April 1988

    This bibliography contains citations concerning 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 and the utilzation of computer models in risk analysis are also included. (This updated bibliography contains 368 citations, none of which are new entries to the previous edition.)

  17. Accident risks in nuclear facilities. May 1988-April 1989 (Citations from the NTIS data base). Report for May 1988-April 1989

    This bibliography contains citations concerning 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 and the utilzation of computer models in risk analysis are also included. (This updated bibliography contains 102 citations, all of which are new entries to the previous edition.)

  18. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States); Bunt, R. [Southern Nuclear, Atlanta, GA (United States); Corradini, M. [Univ. of Wisconsin, Madison, WI (United States); Ellison, Paul B. [GE Power and Water, Duluth, GA (United States); Francis, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Gabor, John D. [Erin Engineering, Walnut Creek, CA (United States); Gauntt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Henry, C. [Fauske and Associates, Burr Ridge, IL (United States); Linthicum, R. [Exelon Corp., Chicago, IL (United States); Luangdilok, W. [Fauske and Associates, Burr Ridge, IL (United States); Lutz, R. [PWR Owners Group (PWROG); Paik, C. [Fauske and Associates, Burr Ridge, IL (United States); Plys, M. [Fauske and Associates, Burr Ridge, IL (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rempe, J. [Rempe and Associates LLC, Idaho Falls, ID (United States); Robb, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Wachowiak, R. [Electric Power Research Inst. (EPRI), Knovville, TN (United States)

    2015-01-31

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy’s (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

  19. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy's (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

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

    Yunfeng YE

    2016-02-01

    Full Text Available 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 deaths was declined and several safety concerns persist in some segments. Keywords: Work safety, Major accident, Prevention

  1. Investigation of Key Factors for Accident Severity at Railroad Grade Crossings by Using a Logit Model

    Hu, Shou-Ren; Li, Chin-Shang; Lee, Chi-Kang

    2010-01-01

    Although several studies have used logit or probit models and their variants to fit data of accident severity on roadway segments, few have investigated accident severity at a railroad grade crossing (RGC). Compared to accident risk analysis in terms of accident frequency and severity of a highway system, investigation of the factors contributing to traffic accidents at an RGC may be more complicated because of additional highway–railway interactions. Because the proportional odds assumption ...

  2. Soviet submarine accidents

    Although the Soviet Union has more submarines than the NATO navies combined, and the technological superiority of western submarines is diminishing, there is evidence that there are more accidents with Soviet submarines than with western submarine fleets. Whether this is due to inadequate crews or lower standards of maintenance and overhaul procedures is discussed. In particular, it is suggested that since the introduction of nuclear powered submarines, the Soviet submarine safety record has deteriorated. Information on Soviet submarine accidents is difficult to come by, but a list of some 23 accidents, mostly in nuclear submarines, between 1966 and 1986, has been compiled. The approximate date, class or type of submarine, the nature and location of the accident, the casualties and damage and the source of information are tabulated. (U.K.)

  3. Accident resistant transport container

    Anderson, J.A.; Cole, K.K.

    The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.

  4. Talking about accidents

    It is argued that the public's emotional fear of the hypothetical, very unlikely, gigantic nuclear accident is partly caused by the nuclear industry's incorrect use of language within its own professional discussions. Improved terminology is suggested. (U.K.)

  5. Deepwater Horizon Accident Investigation Report

    NONE

    2010-09-15

    On the evening of April 20, 2010, a well control event allowed hydrocarbons to escape from the Macondo well onto Transocean's Deepwater Horizon, resulting in explosions and fire on the rig. Eleven people lost their lives, and 17 others were injured. The fire, which was fed by hydrocarbons from the well, continued for 36 hours until the rig sank. Hydrocarbons continued to flow from the reservoir through the wellbore and the blowout preventer (BOP) for 87 days, causing a spill of national significance. BP Exploration and Production Inc. was the lease operator of Mississippi Canyon Block 252, which contains the Macondo well. BP formed an investigation team that was charged with gathering the facts surrounding the accident, analyzing available information to identify possible causes and making recommendations to enable prevention of similar accidents in the future. The BP investigation team began its work immediately in the aftermath of the accident, working independently from other BP spill response activities and organizations. The ability to gather information was limited by a scarcity of physical evidence and restricted access to potentially relevant witnesses. The team had access to partial real-time data from the rig, documents from various aspects of the Macondo well's development and construction, witness interviews and testimony from public hearings. The team used the information that was made available by other companies, including Transocean, Halliburton and Cameron. Over the course of the investigation, the team involved over 50 internal and external specialists from a variety of fields: safety, operations, subsea, drilling, well control, cementing, well flow dynamic modeling, BOP systems and process hazard analysis. This report presents an analysis of the events leading up to the accident, eight key findings related to the causal chain of events and recommendations to enable the prevention of a similar accident. The investigation team worked

  6. Deepwater Horizon Accident Investigation Report

    On the evening of April 20, 2010, a well control event allowed hydrocarbons to escape from the Macondo well onto Transocean's Deepwater Horizon, resulting in explosions and fire on the rig. Eleven people lost their lives, and 17 others were injured. The fire, which was fed by hydrocarbons from the well, continued for 36 hours until the rig sank. Hydrocarbons continued to flow from the reservoir through the wellbore and the blowout preventer (BOP) for 87 days, causing a spill of national significance. BP Exploration and Production Inc. was the lease operator of Mississippi Canyon Block 252, which contains the Macondo well. BP formed an investigation team that was charged with gathering the facts surrounding the accident, analyzing available information to identify possible causes and making recommendations to enable prevention of similar accidents in the future. The BP investigation team began its work immediately in the aftermath of the accident, working independently from other BP spill response activities and organizations. The ability to gather information was limited by a scarcity of physical evidence and restricted access to potentially relevant witnesses. The team had access to partial real-time data from the rig, documents from various aspects of the Macondo well's development and construction, witness interviews and testimony from public hearings. The team used the information that was made available by other companies, including Transocean, Halliburton and Cameron. Over the course of the investigation, the team involved over 50 internal and external specialists from a variety of fields: safety, operations, subsea, drilling, well control, cementing, well flow dynamic modeling, BOP systems and process hazard analysis. This report presents an analysis of the events leading up to the accident, eight key findings related to the causal chain of events and recommendations to enable the prevention of a similar accident. The investigation team worked separately

  7. National emergency plan for nuclear accidents

    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

  8. Safety analysis of surface haulage accidents

    Randolph, R.F.; Boldt, C.M.K.

    1996-12-31

    Research on improving haulage truck safety, started by the U.S. Bureau of Mines, is being continued by its successors. This paper reports the orientation of the renewed research efforts, beginning with an update on accident data analysis, the role of multiple causes in these accidents, and the search for practical methods for addressing the most important causes. Fatal haulage accidents most often involve loss of control or collisions caused by a variety of factors. Lost-time injuries most often involve sprains or strains to the back or multiple body areas, which can often be attributed to rough roads and the shocks of loading and unloading. Research to reduce these accidents includes improved warning systems, shock isolation for drivers, encouraging seatbelt usage, and general improvements to system and task design.

  9. The Chernobyl accident

    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

  10. Accident management information needs

    In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate the accident, and monitor the effectiveness of these strategies. This report describes the methodology and presents an application of this methodology to a Pressurized Water Reactor (PWR) with a large dry containment. A risk-important severe accident sequence for a PWR is used to examine the capability of the existing measurements to supply the necessary information. The method includes an assessment of the effects of the sequence on the measurement availability including the effects of environmental conditions. The information needs and capabilities identified using this approach are also intended to form the basis for more comprehensive information needs assessment performed during the analyses and development of specific strategies for use in accident management prevention and mitigation. 3 refs., 16 figs., 7 tabs

  11. Historical aspects of radiation accidents

    Radiation accidents are extremely rare events; however, the last two years have witnessed the largest radiation accidents in both the eastern and western hemispheres. It is the purpose of this chapter to review how radiation accidents are categorized, examine the temporal changes in frequency and severity, give illustrative examples of several types of radiation accidents, and finally, to describe the various registries for radiation accidents

  12. Cyclical Fluctuations in Workplace Accidents

    Boone, J.; van Ours, J.C.

    2002-01-01

    This Paper presents a theory and an empirical investigation on cyclical fluctuations in workplace accidents. The theory is based on the idea that reporting an accident dents the reputation of a worker and raises the probability that he is fired. Therefore a country with a high or an increasing unemployment rate has a low (reported) workplace accident rate. The empirical investigation concerns workplace accidents in OECD countries. The analysis confirms that workplace accident rates are invers...

  13. Accidents on ships in the Danish International Ship register

    Ádám, Balázs; Rasmussen, Hanna Barbara

    our study is to describe trend of accidents and their contributing factors, with special focus on nationality, occurring in ships under Danish flag in the period 2010-2012. The study used two independent data sources, the Danish Maritime Authority and the Danish Radio Medical. It is mandatory to...... report accidents causing at least one day off work beyond the day of accident but the first source contains several accidents not fulfilling this criterion, too. Radio Medical is an independent service where all Danish ships may seek medical advice. The data sets were merged by identification number to...... create a single database that has been studied by descriptive statistics and regression analysis. Findings show a stabilised number of accidents in the analysed period. The occurrence of accidents is influenced by nationality. There is a higher frequency of reported injuries found among Danish and other...

  14. Accidents in nuclear ships

    Oelgaard, P.L. [Risoe National Lab., Roskilde (Denmark)]|[Technical Univ. of Denmark, Lyngby (Denmark)

    1996-12-01

    This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10{sup -3} per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au).

  15. Accidents in nuclear ships

    This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10-3 per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au)

  16. Safety investigation of team performance in accidents

    The paper presents the capacities of the performance evaluation of teamwork (PET) method. Its practicability and efficiency are illustrated by retrospective human reliability analyse of the famous nuclear and maritime accidents. A quantitative assessment of operators' performance on the base of thermo-hydraulic (T/H) calculations and full-scope simulator data for set of NPP design basic accidents with WWER is demonstrated. The last data are obtained on the 'WWER-1000' full-scope simulator of Kozloduy NPP during the regular practical training of the operators' teams. An outlook on the 'evaluation system of main control room (MCR) operators' reliability' project, based on simulator data of operators' training is given

  17. The operational emergency response model at the Swedish Meteorological and Hydrological Institute: validation using data from ETEX and the Chernobyl accident

    The Eulerian atmospheric tracer transport model MATCH (Mesoscale Atmospheric Transport and Chemistry model) has been extended with a Lagrangian particle model treating the initial dispersion of pollutants from point sources. The model has been implemented at SMHI in an emergency response system for nuclear accidents and can be activated on short notice to provide forecast concentration and deposition fields. This information is then forwarded to the Swedish Radiation Protection Agency (SSI) as a basis for further actions. The model has been used to simulate the transport of the inert species released during the first ETEX experiment and the transport and deposition of 137Cs from the Chernobyl accident. Visual inspection of the results as well as statistical analysis shows that the extent, time of arrival and duration of the cloud, is in good agreement with the observations for both cases, with a tendency to overprediction for the first ETEX release. For the Chernobyl case also the simulated deposition pattern over Scandinavia agrees with observations. (author)

  18. Group unified accident reporting database (GUARD)

    Significant advances have been made in recent years in enhancing the standard of safety within Shell Companies, such that safety has now been raised to a status equal to other primary business objectives. It is widely accepted that accident prevention is part of good business practice, and that a safe operation is normally an efficient operation. Safety programmes are being widely implemented which involve all employees from top management right down to the workforce including the contract staff, and the benefits are being realized. The effectiveness of any safety programme, however, must be continuously monitored, and in this respect injury and accident statistics play an important role as a prime indicator of safety performance. Statistics form part of the safety management process indicating the success of the safety programmes being implemented, and highlighting areas of weakness. Statistical information relating to the number and frequency of accidents, significant as it is, tells us little about how the accidents occur, or about how to improve the intrinsic safety of the operations. More detailed information on accident causes and lessons derived from the investigation of non-injurious accidents and near-misses is required for this, and for the setting of appropriate remedial actions. This paper concentrates on the feedback from accidents which have already occurred. This feedback plays a vital role as an indicator of safety performance upon which to judge the effectiveness of safety programmes, and also to provide important information relating to the immediate and underlying causes of accidents. To meet these requirements, however, a system for recording analyzing and communicating safety data is essential

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

    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

  20. First international workshop on severe accidents and their consequences. [Chernobyl Accident

    1989-07-01

    An international workshop on past severe nuclear accidents and their consequences was held in Dagomys region of Sochi, USSR on October 30--November 3, 1989. The plan of this meeting was approved by the USSR Academy of Sciences and by the USSR State Committee of the Utilization of Atomic Energy. The meeting was held under the umbrella of the ANS-SNS agreement of cooperation. Topics covered include analysis of the Chernobyl accident, safety measures for RBMK type reactors and consequences of the Chernobyl accident including analysis of the ecological, genetic and psycho-social factors. Separate reports are processed separately for the data bases. (CBS)

  1. TMI-2 accident: core heat-up analysis

    This report summarizes NSAC study of reactor core thermal conditions during the accident at Three Mile Island, Unit 2. The study focuses primarily on the time period from core uncovery (approximately 113 minutes after turbine trip) through the initiation of sustained high pressure injection (after 202 minutes). The transient analysis is based upon established sequences of events; plant data; post-accident measurements; interpretation or indirect use of instrument responses to accident conditions

  2. Scoping accident(s) for emergency planning

    At the request of the Conference of State Radiation Control Program Director's (CRCPD), in November 1976 the U.S. Nuclear Regulatory Commission formed a joint Task Force with representatives of the U.S. Environmental Protection Agency to answer a number of questions posed by the States regarding emergency planning. This Task Force held monthly meetings through November 1977. In December 1977 a draft report was prepared for limited distribution for review and comment by selected State and local organizations. The NRC/EPA Task Force deliberations centered on the CRCPD request for '... a determination of the most severe accident basis for which radiological emergency response plans should be developed by offsite agencies...' in the vicinity of nuclear power plants. Federal Interagency guidance to the States in this regard has been that the scoping accident should be the most serious conservatively analyzed accident considered for siting purposes, as exemplified in the Commission's Regulations at 10 CFR Part 100 and the NRC staffs Regulatory Guides 1.3 and 1.4, and as presented in license applicant's Safety Analysis Reports and the USNRC Staffs Safety Evaluation Reports. The draft report of the Task Force amplifies on this recommendation: to present a clearer picture of its import and introduces the concept of protective action zones (PAZs) within which detailed emergency plans should be developed; one zone for the plume exposure pathway and a second, larger zone for contamination pathways. The time dependence of potential releases and atmospheric transport, and important radionuclide groups of possible import are also discussed in the draft Task Force report. A status report regarding this effort, as of June 1978, will be presented. (author)

  3. Important severe accident research issues after Fukushima accident

    After the Fukushima accident several investigation committees issued reports with lessons learned from the accident in Japan. Among those lessons, several recommendations have been made on severe accident research. Similar to the EURSAFE efforts under EU Program, review of specific severe accident research items was started before Fukushima accident in working group of Atomic Energy Society of Japan (AESJ) in terms of significance of consequences, uncertainties of phenomena and maturity of assessment methodology. Re-investigation has been started since the Fukushima accident. Additional effects of Fukushima accident, such as core degradation behaviors, sea water injection, containment failure/leakage and re-criticality have been covered. The review results are categorized in ten major fields; core degradation behavior, core melt coolability/retention in containment vessel, function of containment vessel, source term, hydrogen behavior, fuel-coolant interaction, molten core concrete interaction, direct containment heating, recriticality and instrumentation in severe accident conditions. Based on these activities and also author's personal view, the present paper describes the perspective of important severe accident research issues after Fukushima accident. Those are specifically investigation of damaged core and components, advanced severe accident analysis capabilities and associated experimental investigations, development of reliable passive cooling system for core/containment, analysis of hydrogen behavior and investigation of hydrogen measures, enhancement of removal function of radioactive materials of containment venting, advanced instrumentation for the diagnosis of severe accident and assessment of advanced containment design which excludes long-term evacuation in any severe accident situations. (author)

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

    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

  5. Process criticality accident likelihoods, magnitudes and emergency planning. A focus on solution accidents

    This paper presents analyses and applications of data from reactor and critical experiment research on the dynamics of nuclear excursions in solution media. Available criticality accident information is also discussed and shown to provide strong evidence of the overwhelming likelihood of accidents in liquid media over other forms and to support the measured data. These analyses are shown to provide valuable insights into key parameters important to understanding solution excursion dynamics in general and in evaluating practical upper bounds on criticality accident magnitudes. This understanding and these upper bounds are directly applicable to the evaluation of the consequences of postulated criticality accidents. These bounds are also essential in order to comply with national and international consensus standards and regulatory requirements for emergency planning. (author)

  6. Preliminary Assessment of Accident Tolerant Fuel Performance at Normal and Accident Conditions

    The interest for improving the safety of light water reactors (LWRs) fuel designs, which has significantly grown after the Fukushima Daiichi Accident, has driven the U.S. Department of Energy (DOE) to fund three industry-led programs to facilitate the development of accident tolerant fuels (ATF) for LWRs. Westinghouse is leading one of them and engaged in developing a combined accident resistant cladding and high density fuel pellet. It is important to develop and apply fuel performance codes and other computational methods to model the novel fuel forms to better understand the in-core performance and to guide new fuel designs. In this paper, a preliminary assessment on the performance of various ATF concepts during normal and accident conditions is presented. These concepts include various combinations of accident tolerant fuel and cladding materials: UN/SiC, U3Si2/SiC, UN/Coated Zircaloy, and U3Si2/Coated Zircaloy. The properties of the new materials were collected from literature and their irradiation data will be selected from various test reactor experiments. The impact of ATF properties on design basis accidents and beyond design basis accident is also discussed. (author)

  7. Accident progression event tree analysis for postulated severe accidents at N Reactor

    A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied

  8. Information at radiation accidents

    This study was undertaken in order to plan an information strategy for possible future accidents involving radioactivity. Six health visitors and six farmers working in the districts of Norway which received the largest amounts of fallout from the Chernobyl accident, were interviewed. The questions were intended to give an indication of their knowledge about radioactivity and radiation, as well as their needs for information in case of a future accident. The results indicate a relatively low educational background in radiation physics and risk estimation. On the other hand the two groups showed a remarkable skill and interest in doing their own evaluation on the background of information that was linked to their daily life. It is suggested that planning of information in this field is done in close cooperation with the potential users of the information

  9. Radiation accidents and dosimetry

    On September 2nd 1982 one of the employees of the gamma-irradiation facility at Institute for Energy Technology, Kjeller, Norway entered the irradiation cell with a 65.7 kCi *sp60*Co- source in unshielded position. The victim received an unknown radiation dose and died after 13 days. Using electron spin resonance spectroscopy, the radiation dose in this accident was subsequently determined based on the production of longlived free radicals in nitroglycerol tablets borne by the operator during the accident. He used nitroglycerol for heart problems and free radical are easily formed and trapped in sugar which is the main component of the tablets. Calibration experiments were carried out and the dose given to the tablets during the accident was determined to 37.2 +- 0.5 Gy. The general use of free radicals for dose determinations is discussed. (Auth.)

  10. Big nuclear accidents

    Much of the debate on the safety of nuclear power focuses on the large number of fatalities that could, in theory, be caused by extremely unlikely but imaginable reactor accidents. This, along with the nuclear industry's inappropriate use of vocabulary during public debate, has given the general public a distorted impression of the safety of nuclear power. The way in which the probability and consequences of big nuclear accidents have been presented in the past is reviewed and recommendations for the future are made including the presentation of the long-term consequences of such accidents in terms of 'reduction in life expectancy', 'increased chance of fatal cancer' and the equivalent pattern of compulsory cigarette smoking. (author)

  11. Control and interpretation of radiometric survey data for determination of personal doses of internal exposure to the thyroid after the Chernobyl accident

    Following the Chernobyl accident one of the most important studies caused by the necessity of radiation protection and medical care of the population was determination of personal doses to residents of the territories most intensively affected by radioactive contamination. The necessity of determining personal doses demanded that a number of specific problems of measurement and dosimetry nature should be solved. In the given paper two problems are presented: determination of iodine-131 content in the thyroid by the results of radiometry of man in the presence of evenly distributed radionuclides in the body; reconstruction of doses to the thyroid in persons who had not been measured for iodine-131 content in the body or the results of their measurement proved to be unreliable

  12. The management of accidents

    R. B. Ward

    2009-01-01

    Full Text Available Purpose: This author’s experiences in investigating well over a hundred accident occurrences has led to questioning how such events can be managed - - - while immediately recognising that the idea of managing accidents is an oxymoron, we don’t want to manage them, we don’t want not to manage them, what we desire is not to have to manage not-them, that is, manage matters so they don’t happen and then we don’t have to manage the consequences.Design/methodology/approach: The research will begin by defining some common classes of accidents in manufacturing industry, with examples taken from cases investigated, and by working backwards (too late, of course show how those involved could have managed these sample events so they didn’t happen, finishing with the question whether any of that can be applied to other situations.Findings: As shown that the management actions needed to prevent accidents are control of design and application of technology, and control and integration of people.Research limitations/implications: This paper has shown in some of the examples provided, management actions have been know to lead to accidents being committed by others, lower in the organization.Originality/value: Today’s management activities involve, generally, the use of technology in many forms, varying from simple tools (such as knives to the use of heavy equipment, electric power, and explosives. Against these we commit, in control of those items, the comparatively frail human mind and body, which, again generally, does succeed in controlling these resources, with (another generality by appropriate management. However, sometimes the control slips and an accident occurs.

  13. Riverine transport of Cs-137 and Sr-90 into the Black Sea after Chernobyl accident (data analysis and methodological aspects of monitoring)

    Upper part of Dnieper catchment had been heavily contaminated after the Chernobyl accident and serves as a main source of the secondary input of radionuclides to the river. As a result of fast sorption of dissolved radiocesium by suspended sediments and sedimentation of contaminated particles to the bottom, practically all the 137Cs having entered into the upper reaches of the Dnieper river after the Chernobyl accident was retained in the Dnieper reservoirs and the Dnieper-Bug estuary. Taking into account relatively high mobility of 90Sr the extent of it's trapping by Dnieper reservoirs is significantly less comparatively to 137Cs and accounted as some 60-70%. The Danube River catchment is characterized by less radioactive contamination, in comparison with the Dnieper catchment, and more homogeneous spatial distribution of this contamination. Suspended particles play a crucial role in 137Cs transport by Danube to the Black Sea. Regular observations showed, that in average 60-70% of 137Cs transport to the Black Sea is associated with suspended particles. The conditions for water selfpurification are absent on the Danube River due to the high velocity of the currents along the whole it length. Therefore, the significant portion of 137Cs and other contaminants in particulate phase washed out from the upper part of basin can reach the Black Sea. The correct accounting of 137Cs discharge on suspended particles by river strictly depends on representativity of samples used in calculation. Sampling procedure which had been done in uncorrect way could cause in significant underestimation of 137Cs concentration up to 10 times. (author)

  14. The TMI-2 accident

    A critical study about the technical and man-related facts in order to establish what is considered the worst commercial nuclear power accident until 1986. Radiological consequences and stress to the public are considered in contrast to antinuclear groups. This descriptive and technical study has the purpose to document written and oral opinions obtained abroad and then explain to the public in an easy language terminology. Preliminary study describing safety related systems fails and the accident itself with minute to minute description, conduct to the consequences and then, to learned lessons

  15. A framework for the assessment of severe accident management strategies

    Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed

  16. A framework for the assessment of severe accident management strategies

    Kastenberg, W.E. [ed.; Apostolakis, G.; Dhir, V.K. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering] [and others

    1993-09-01

    Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed.

  17. Initial event analysis of the Fukushima Daiichi accident

    The objective of this study is to investigate the initial event of the Fukushima Daiichi accident and to check the validity of the counter measures against the accident. We analyzed the initial event of the Fukushima Daiichi accident for Unit-1, 2 and 3 plants by RELAP5 code and compared with the actual plant data. The parametric study about the operation of the isolation condenser (IC), the reactor core isolation cooling system (RCIC) and the high pressure core injection system (HPCI) was also done to understand the accident progression. (author)

  18. Analysis on relation between safety input and accidents

    YAO Qing-guo; ZHANG Xue-mu; LI Chun-hui

    2007-01-01

    The number of safety input directly determines the level of safety, and there exists dialectical and unified relations between safety input and accidents. Based on the field investigation and reliable data, this paper deeply studied the dialectical relationship between safety input and accidents, and acquired the conclusions. The security situation of the coal enterprises was related to the security input rate, being effected little by the security input scale, and build the relationship model between safety input and accidents on this basis, that is the accident model.

  19. A methodology for the transfer of probabilities between accident severity categories

    Evaluation of the radiological risks of accidents involving vehicles transporting radioactive materials requires consideration of both accident probability and consequences. The probability that an accident will occur may be estimated from historical accident data for the given mode of transport. In addition to an overall accident rate, information regarding accident severity and the resulting package environments across the range of all credible accidents is needed to determine the potential for a release of radioactive material from the package or for an increase in direct radiation from the package caused by damage to packaging shielding. This information is usually obtained from a variety of sources such as historical data, experimental data, analyses of accident and package environments, and expert opinion. The consequences of an accident depend on a number of factors including the type, quantity, and physical form of radioactive material being transported; the response of the package to accident environments; the fraction of material released from the package; and the dispersion of any released material. One approach for the classification and treatment of transportation accidents in risk analysis divides the complete range of critical accident environments resulting from all credible accidents into some number of accident-severity categories. The types of accident environments that a package may be subjected to in transportation are often classified into the following five groups: impact, fire, crush, puncture, and immersion. A open-quotes criticalclose quotes accident environment is one of a type that could present a plausible threat to a package. Each severity category represents a portion of all credible accidents, and the total of all severity categories covers the complete range of critical accident environments. This approach is used in the risk assessment codes RADTRAN (Neuhauser and Kanipe 1992) and INTERTRAN (Ericsson and Elert 1983)

  20. Description of the accident

    The TMI-2 accident occurred in March 1979. The accident started with a simple and fairly common steam power plant failure--loss of feedwater to the steam generators. Because of a combination of design, training, regulatory policies, mechanical failures and human error, the accident progressed to the point where it eventually produced the worst known core damage in large nuclear power reactors. Core temperatures locally reached UO2 fuel liquefaction (metallic solution with Zr) and even fuel melt (3800-51000F). Extensive fission product release and Zircaloy cladding oxidation and embrittlement occurred. At least the upper 1/2 of the core fractured and crumbled upon quenching. The lower central portion of the core apparently had a delayed heatup and then portions of it collapsed into the reactor vessel lower head. The lower outer portion of the core may be relatively undamaged. Outside of the core boundary, only those steel components directly above and adjacent to the core (≤1 foot) are known to have suffered significant damage (localized oxidation and melting). Other portions of the primary system outside of the reactor vessel apparently had little chance of damage or even notable overheating. The demonstrated coolability of the severely damaged TMI-2 core, once adequate water injection began, was one of the most substantial and important results of the TMI-2 accident

  1. Fifteen years after accident

    This book is devoted to 15th anniversary of the Chernobyl accident. Four problems have been reflected in the book: contamination of territories of Western Europe, Belarus, Ukraine and Russian Federation by cesium-137; plutonium, americium and other actinides on territory of Belarus; problems of radioactive wastes management of Chernobyl origin; influence of various factors on oncology morbidity in the Republic of Belarus

  2. Measures against nuclear accidents

    A select committee appointed by the Norwegian Ministry of Social Affairs put forward proposals concerning measures for the improvement of radiation protection preparedness in Norway. On the basis on an assessment of the potential radiation accident threat, the report examines the process of response, and identifies the organizational and management factors that influence that process

  3. The Chernobyl reactor accident

    The documentation abstracted contains a complete survey of the broadcasts transmitted by the Russian wire service of the Deutsche Welle radio station between April 28 and Mai 15, 1986 on the occasion of the Chernobyl reactor accident. Access is given to extracts of the remarkable eastern and western echoes on the broadcasts of the Deutsche Welle. (HP)

  4. DOZIM - evaluation dose code for nuclear accident

    During a nuclear accident an environmentally significant fission products release can happen. In that case it is not possible to determine precisely the air fission products concentration and, consequently, the estimated doses will be affected by certain errors. The stringent requirement to cope with a nuclear accident, even minor, imposes creation of a computation method for emergency dosimetric evaluations needed to compare the measurement data to certain reference levels, previously established. These comparisons will allow a qualified option regarding the necessary actions to diminish the accident effects. DOZIM code estimates the soil contamination and the irradiation doses produced either by radioactive plume or by soil contamination. Irradiations either on whole body or on certain organs, as well as internal contamination doses produced by isotope inhalation during radioactive plume crossing are taken into account. The calculus does not consider neither the internal contamination produced by contaminated food consumption, or that produced by radioactive deposits resuspension. The code is recommended for dose computation on the wind direction, at distances from 102 to 2 x 104 m. The DOZIM code was utilized for three different cases: - In air TRIGA-SSR fuel bundle destruction with different input data for fission products fractions released into the environment; - Chernobyl-like accident doses estimation; - Intervention areas determination for a hypothetical severe accident at Cernavoda Nuclear Power Plant. For the first case input data and results (for a 60 m emission height without iodine retention on active coal filters) are presented. To summarize, the DOZIM code conception allows the dose estimation for any nuclear accident. Fission products inventory, released fractions, emission conditions, atmospherical and geographical parameters are the input data. Dosimetric factors are included in the program. The program is in FORTRAN IV language and was run on a

  5. Lessons learned from accident investigations

    Accidents in three main practices - medical applications, industrial radiography and industrial irradiators - are used to illustrate some common causes of accidents and the main lessons to be learned from them. A brief description of some of these accidents is given. Lessons learned from the accidents described are approached bearing in mind: safety culture, quality assurance, human factors, good engineering practice, defence in depth, security of sources, safety assessment and monitoring and verification compliance. (author)

  6. Lessons learned from accidents investigations

    Accidents from three main practices: medical applications, industrial radiography and industrial irradiators are used to illustrate some common causes of accidents and the main lessons to be learned. A brief description of some of these accidents is given. Lessons learned from the described accidents are approached by subjects covering: safety culture, quality assurance, human factors, good engineering practice, defence in depth, security of sources, safety assessment and monitoring and verification compliance. (author)

  7. The Chernobyl accident

    The accident at Unit 4 of the Chernobyl nuclear power plant was the most severe in the nuclear industry. The accident caused the rapid death of 31 power plant employees and firemen, mainly from acute radiation exposures and burns, and brought about the evacuation of 116,000 people within a few weeks. In addition, about half a million workers and four million members of the public have been exposed, to some extent, to radiation doses resulting from the Chernobyl accident. A large number of radiation measurements have been made since the accident in order to reconstruct the doses received by the most exposed populations. On the basis of currently available information, it appears that: (1) average doses received by clean-up workers from external irradiation decreased with time, being about 300 mGy for the persons who worked in the first three months after the accident, about 170 mGy for the remainder of 1986, 130 mGy in 1987, 30 mGy in 1988, and 15 mGy in 1989; (2) the evacuees received, before evacuation, effective doses averaging 11 mSv for the population of Pripyat, and 18 mSv for the remainder of the population of the 30 km zone, with maximum effective doses ranging up to 380 mSv; and (3) among the populations living in contaminated areas, the highest doses were those delivered to the thyroids of children. Thyroid doses derived from thyroid measurements among Belarussian and Ukrainian children indicate median thyroid doses of about 300 mGy, and more than 1% of the children with thyroid doses in excess of 5000 mGy. A description is provided of the epidemiological studies that the National Cancer Institute has, since 1990, at the request of the Department of Energy, endeavoured to undertake, in cooperation with Belarus and Ukraine, on two possible health effects resulting from the Chernobyl accident: (1, thyroid cancer in children living in contaminated areas during the first few weeks following the accident, and (2) leukaemia among workers involved in clean

  8. Accident Avoidance Skill Training and Performance Testing. Final Report.

    Hatterick, G. Richard; Barthurst, James R.

    A two-phased study was conducted to determine the feasibility of training drivers to acquire skills needed to avoid critical conflict motor vehicle accidents, and to develop the procedures and materials necessary for such training. Basic data were derived from indepth accident investigations and task analyses of driver behavior. Principal…

  9. NASA's Accident Precursor Analysis Process and the International Space Station

    Groen, Frank; Lutomski, Michael

    2010-01-01

    This viewgraph presentation reviews the implementation of Accident Precursor Analysis (APA), as well as the evaluation of In-Flight Investigations (IFI) and Problem Reporting and Corrective Action (PRACA) data for the identification of unrecognized accident potentials on the International Space Station.

  10. ACCIDENT, ILLNESS AND INJURY AND EMPLOYMENT SELF-EXTRACTING FILES

    Files containing information of accidents, illnesses and injuries of miners. These "self-extracting" files are the actual information (raw data) from the accident and injury MSHA Form 7000-2 filed with MSHA by mining operators and contractors as required under the 30 CFR Part 50.

  11. The psychology of nuclear accidents

    Incidents involving nuclear weapons are described, as well as the accident to the Three Mile Island-2 reactor. Methods of assessment of risks are discussed, with particular reference to subjective judgements and the possible role of human error in civil nuclear accidents. Accidents or misunderstandings in communication or human actions which might lead to nuclear war are also discussed. (U.K.)

  12. Agricultural implications of the Fukushima nuclear accident

    Since the Fukushima Daiichi nuclear power plant accident in March 2011, contamination of places and foods has been a matter of concern. Unfortunately, agricultural producers have few sources of information and have had to rely on the lessons from the Chernobyl accident in 1986 or on information obtained from the International Atomic Energy Agency. However, as of this writing, data on the specific consequences of the Fukushima accident on Japanese agriculture remain limited. More than 80% of the land that suffered from the accident was related to agriculture or was in forests and meadows. The in fluence of the accident on agriculture was the most difficult to study because the activity in nature had to be dealt with. For example, when contaminated rice is harvested, scientists working on rice plants and soils and the study of watercourses or mountains have to collaborate to analyze or determine the vehicle by which the radioactivity accumulated and through which it spread in nature. At the request of agriculturists in Fukushima, we at the Graduate School of Agricultural and Life Sciences at The University of Tokyo have been urgently collecting reliable data on the contamination of soil, plants, milk, and crops. Based on our data, we would like to comment on or propose an effective way of resuming agricultural activity. Because obtaining research results based on in situ experiments is time-consuming, we have been periodically holding research report meetings at our university every 3-4 months for lay people, showing them how the contamination situation has changed or what type of effect can be estimated. Although our research is still ongoing, we would like to summarize in this book our observations made during the one and a half years after the accident. (author)

  13. Model based detection and reconstruction of road traffic accidents

    Hiemer, Marcus

    2005-01-01

    This thesis describes the detection and reconstruction of traffic accidents with event data recorders. The underlying idea is to describe the vehicle motion and dynamics up to the stability limit by means of linear and non-linear vehicle models. These models are used to categorize the driving behavior and to freeze the recorded data in a memory if an accident occurs. Based on these data, among others the vehicle trajectory is reconstructed with fuzzy data fusion. The side slip angle whi...

  14. 49 CFR 837.3 - Published reports, material contained in the public accident investigation dockets, and accident...

    2010-10-01

    .... For information regarding the types of documents routinely issued by the Board, see 49 CFR part 801... public accident investigation dockets, and accident database data. 837.3 Section 837.3 Transportation... OF RECORDS IN LEGAL PROCEEDINGS § 837.3 Published reports, material contained in the public...

  15. A Methodology for Evaluating Severe Accident Management Strategies

    Severe accidents are defined as those which entail at least an initial core damage, in many cases specified as the overcoming of the regulatory fuel. After Fukushima accident, the effectiveness of the severe accident management strategy has been attracted worldwide. There is a typical example of severe accident management strategy like Severe Accident Management and Guideline (SAMG). Unfortunately, suitable method for evaluating the accident management strategy is absence until now. In this study, the evaluation methodology which utilizes the decision tree is developed to evaluate the severe accident management strategies. In addition, we applied the developed methodology to ShinKori nuclear power plant Unit 3, 4 and modeled decision tree for evaluation. In this study, we developed a methodology to evaluate the severe accident management strategy by using decision tree. In addition, the evaluation was carried out by selecting the cavity flooding strategy. Shinkori unit 3, 4 which is APR1400 is selected and analyzed for reference plant. In order to evaluation, decision tree for cavity flooding is modeled. With reliability data, quantification will be conducted. The utility of other severe accident management strategies can be evaluated with proposed methodology in this study. Finally, it is expected that this methodology improves the safety of nuclear power plant

  16. The Why and How of Nuclear Accident Dosimetry

    The objective of an effective nuclear accident dosimetry programme is to ensure that a means is provided for estimating the gamma neutron dose from a nuclear accident. In this connection, the limitation of the film badge is discussed, in addition to certain accident experiences which demonstrate the need for an effective accident dosimetry programme at facilities having a potential for nuclear accidents. Certain basic parameters should be considered in the development of an effective nuclear accident dosimetry programme. These are (a) a method for screening personnel involved in nuclear accidents, (b) a fixed system (primary unit) capable of determining first collision dose within some established degree of accuracy at its point of location, (c) the need for ''secondary units'', and (d) the need for a device worn by personnel which would afford spectrum and flux information to assist in dose extrapolation from the fixed unit to the location of man. The neutron component of the system should permit flux and spectral information in order to arrive at appropriate quality factors in the dose estimation. Accuracies should be established based upon the current state of the art. The gamma -ray component of the system should permit measuring gamma radiation within the biological area of interest, i. e. from 10 to 103r. Consideration for the number, placement and ease of recovery of accident units are indeed an integral part of an effective system of accident dosimetry. These considerations should enable reasonable data collection across the entire fission spectrum. (author)

  17. Development of Database for Accident Analysis in Indian Mines

    Tripathy, Debi Prasad; Guru Raghavendra Reddy, K.

    2015-08-01

    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.

  18. Consequences of radioactive releases into the sea resulting from the accident at the Fukushima Dai-ichi nuclear power plant - Evolution of expert investigation according to the data available

    The accident at the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) in March 2011 led to an unprecedented direct input of artificial radioactivity into the marine environment. The Institute for Radioprotection and Nuclear Safety was requested by the French authorities to investigate the radioecological impact of this input, in particular the potential contamination of products of marine origin used for human consumption. This article describes the close link between the responses provided and the availability of the data, as well as their nature and ability to meet the requirements of expert investigation. These responses were needed: (i) to evaluate the inputs of radionuclides into the marine environment, (ii) to understand their dispersion in seawater, and (iii) to estimate their transfer to the biota and sediments. Three phases can be distinguished which characterise these processes during the accident and post-accident periods. The first phase corresponds to an emergency phase during which no measurements were available on samples from the marine environment. It involved the formulation of hypotheses based solely on the expertise of the Institute for Radioprotection and Nuclear Safety. The second phase started when the Japanese authorities provided measurements of the concentrations of radionuclides in seawater. Although these data were not yet adapted to addressing the problems of radioecology, the scenarios could then be refined and the estimates developed in more detail. During the third phase, the accumulation of data over the course of time made it possible to study the phenomena in an appropriate way. The chronology of the events shows that it is essential to have (i) significant measurements of concentration from samples collected in the various matrices of the marine environment, regularly updated and sufficiently well-documented, (ii) samples of seawater collected at the earliest opportunity as close as possible to the damaged site to characterise the

  19. Alternative evacuation strategies for nuclear power accidents

    In the U.S., current protective-action strategies to safeguard the public following a nuclear power accident have remained largely unchanged since their implementation in the early 1980s. In the past thirty years, new technologies have been introduced, allowing faster computations, better modeling of predicted radiological consequences, and improved accident mapping using geographic information systems (GIS). Utilizing these new technologies, we evaluate the efficacy of alternative strategies, called adaptive protective action zones (APAZs), that use site-specific and event-specific data to dynamically determine evacuation boundaries with simple heuristics in order to better inform protective action decisions (rather than relying on pre-event regulatory bright lines). Several candidate APAZs were developed and then compared to the Nuclear Regulatory Commission’s keyhole evacuation strategy (and full evacuation of the emergency planning zone). Two of the APAZs were better on average than existing NRC strategies at reducing either the radiological exposure, the population evacuated, or both. These APAZs are especially effective for larger radioactive plumes and at high population sites; one of them is better at reducing radiation exposure, while the other is better at reducing the size of the population evacuated. - Highlights: • Developed framework to compare nuclear power accident evacuation strategies. • Evacuation strategies were compared on basis of radiological and evacuation risk. • Current strategies are adequate for smaller scale nuclear power accidents. • New strategies reduced radiation exposure and evacuation size for larger accidents

  20. Consequences and problems of the Chernobyl accident

    The data on epidemic situation in connection with the Chernobyl accident, based on the personal medical and dosimetric information on all the persons, subjected to radiation effect, and included in the Russian state medicodosimetric register, are presented. The consequences of the Chernobyl accident become the cause for origination of serious radiation injures by 134 persons (with lethal outcome by 37 patients) and also remote radiation stochastic effects by children (thyroid gland cancer) and by liquidators (thyroid gland leucosis and cancer). The permanent stress and other unfavorable factors conditioned aggravation of chronical and increase in somatic diseases and psychoneurotic disorders

  1. Business cycles and workplace accidents in Iceland 1986- 2011

    Tinna Laufey Ásgeirsdóttir

    2014-12-01

    Full Text Available This study is the first to explore the association between business cycles and workplace accidents using Icelandic data. The relationship is evaluated for the entire labor market, for specific sectors, by gender and by the severity of injuries. Most prior research has found workplace accidents to be pro-cyclical. Hypothesized reasons include increased labor supply and greater work intensity in upswings, and that accidents are more likely to be reported. Aggregate data for workplace accidents from the Administration of Occupational Safety and Health and several macroeconomic indicators from Statistics Iceland and Directorate of Labour were examined. The time series were non-stationary so first differences were used to detrend them. Their relationship was then examined using a linear regression model. Data from the Directorate of Health in Iceland and Statistics Iceland were used to calculate the relative risk of an accident. Pro-cyclical associations between business cycles and work-place accidents were observed, particularly in construction, in commerce and for men. The results of the relative-risk calculations indicated that workers were at considerably greater risk of having an accident in 2007 than in 2004-2006 and 2008-2011. By comparing the different estimations of the study, one can conclude that only a small part of the variability of risk can be explained by changes in labour supply. Increased risk at work, given the labor supply, seems to be a more significant reason for increased prevalence of accidents during periods of economic expansion.

  2. Radiological accidents balance in medicine

    This work deals with the radiological accidents in medicine. In medicine, the radiation accidents on medical personnel and patients can be the result of over dosage and bad focusing of radiotherapy sealed sources. Sometimes, the accidents, if they are unknown during a time enough for the source to be spread and to expose a lot of persons (in the case of source dismantling for instance) can take considerable dimensions. Others accidents can come from bad handling of linear accelerators and from radionuclide kinetics in some therapies. Some examples of accidents are given. (O.L.). 11 refs

  3. Estimating radiation doses from reactor accidents

    In order to plan for emergency response to reactor accidents involving large radiation releases, it is necessary to determine the medical resources, such as diagnostic laboratory tests, hospital facilities and convalescent care, needed to care for a large population exposed to radiation. A determination of the needed medical resources is difficult because of the widely varying sensitivity humans exhibit to radiation exposure and because of the large number of assumptions involved in predicting radiation dispersion. This paper demonstrates a simple method for approximating medical needs in response to a severe reactor accident. The method requires a model for radiation dispersion from the accident and data for population distribution surrounding the reactor. With this information, tables developed in this paper may be used to project medical needs. The needs identified by this methodology may be compared against the actual medical resources of nearby communities to determine the size of the area impacted

  4. Source term formation in CANDU severe accidents

    The paper presents the phenomena involved in the most important CANDU severe accident (LOCA+LOECC, SBO, SGTR, EFF). Fission products are grouped in classes taking into consideration the half time, volatility, chemistry and biological activity. An analysis of the paths on which the release of the fission products to the environment occurs is performed. For each type of CANDU severe accident the process of source term formation, the magnitude and structure of source term and also the timing are presented on the basis of SOPHAEROS, CPA and IODE (modules included in ASTEC code) calculations, completed with literature results. The discussion about the involved sources of uncertainties is also presented taking into account the complexity of phenomena, the great number of parameters and limited availability of experimental data. Some general recommendations are developed in order to use the results in achieving the procedures for protective actions during a reactor accident. (authors)

  5. Sociological and medical aspects of Chernobyl accident

    The sociological survey data, the results of the state of health service in some districts of Gomel and Mogilev regions as well as of the completeness of the fulfillment of state resolutions concerning the liquidation of the Chernobyl accident after effects are given

  6. Chernobyl reactor accident

    On April 26, 1986, an explosion occurred at the newest of four operating nuclear reactors at the Chernobyl site in the USSR. The accident initiated an international technical exchange of almost unprecedented magnitude; this exchange was climaxed with a meeting at the International Atomic Energy Agency in Vienna during the week of August 25, 1986. The meeting was attended by more than 540 official representatives from 51 countries and 20 international organizations. Information gleaned from that technical exchange is presented in this report. A description of the Chernobyl reactor, which differs significantly from commercial US reactors, is presented, the accident scenario advanced by the Russian delegation is discussed, and observations that have been made concerning fission product release are described

  7. The ultimate nuclear accident

    The estimated energy equivalent of Chernobyl explosion was the 1/150 th of the explosive energy equivalent of atomic bomb dropped on Hiroshima; while the devastation that could be caused by the world's stock pile of nuclear weapons, could be equivalent to 160 millions of Chernobyl-like incidents. As known, the number of nuclear weapons is over 50,000 and 2000 nuclear weapons are sufficient to destroy the world. The Three Mile Island and Chernobyl accidents have been blamed on human factors but also the human element, particularly in the form of psychological stresses on those operating the nuclear weapons, could accidentally bring the world to a nuclear catastrophe. This opinion is encouraged by the London's Sunday Times magazine which gave a graphic description of life inside a nuclear submarine. So, to speak of nuclear reactor accidents and not of nuclear weapons is false security. (author)

  8. Nuclear ship accidents

    In this report available information on 28 nuclear ship accident and incidents is considered. Of these 5 deals with U.S. ships and 23 with USSR ships. The ships are in almost all cases nuclear submarines. Only events that involve the nuclear propulsion plants, radiation exposures, fires/explosions and sea water leaks into the submarines are considered. Comments are made on each of the events, and at the end of the report an attempt is made to point out the weaknesses of the submarine designs which have resulted in the accidents. It is emphasized that much of the available information is of a rather dubious nature. consequently some of the assessments made may not be correct. (au)

  9. Reactor accidents in perspective

    In each of the three major reactor accidents which have led to significant releases to the environment, and discussed in outline in this note, the reactor has been essentially destroyed - certainly Windscale and Chernobyl reactors will never operate and the cleanup operation for Three Mile Island is currently estimated to have cost in excess of US Pound 500 000 000. In each of the accidents there has not been any fatality off site in the short term and any long-term health detriment is unlikely to be seen in comparison with the natural cancer incidence rate. At Chernobyl, early fatalities did occur amongst those concerned with fighting the incident on site and late effects are to be expected. The assumption of a linear non-threshold risk, and hence no level of zero risk is the main problem in communication with the public, and the author calls for simplification of the presentation of the concepts of radiological protection. (U.K.)

  10. The Chernobylsk reactor accident

    The construction, the safety philosophy, the major reactor physical parameters of RBMK-1000 type reactor units and the detailed description of the Chernobylsk-4 reactor accident, its causes and conclusions, the efforts to reduce the consequences on the reactor site and in the surroundings are discussed based on different types of Soviet documents including the report presented to the IAEA by the Soviet Atomic Energy Agency in August 1986. (V.N.)

  11. 49 CFR 835.11 - Obtaining Board accident reports, factual accident reports, and supporting information.

    2010-10-01

    ... 49 Transportation 7 2010-10-01 2010-10-01 false Obtaining Board accident reports, factual accident... Board accident reports, factual accident reports, and supporting information. It is the responsibility... obtain Board accident reports, factual accident reports, and accompanying accident docket files....

  12. Accident Monitoring Systems for Nuclear Power Plants

    In the Fukushima Daiichi accident, the instrumentation provided for accident monitoring proved to be ineffective for a combination of reasons. The accident has highlighted the need to re-examine criteria for accident monitoring instrumentation. This publication covers all relevant aspects of accident monitoring in NPPs. The critical issues discussed reflect the lessons learned from the Fukushima Daiichi accident, involve accident management and accident monitoring strategies for nuclear power plants, selection of plant parameters for monitoring plant status, establishment of performance, design, qualification, display, and quality assurance criteria for designated accident monitoring instrumentation, and design and implementation considerations. Technology needs and techniques for accident monitoring instrumentation are also addressed

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

    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. W...

  14. Injury risk prediction for traffic accidents in Porto Alegre/RS, Brazil

    Perone, Christian S.

    2015-01-01

    This study describes the experimental application of Machine Learning techniques to build prediction models that can assess the injury risk associated with traffic accidents. This work uses an freely available data set of traffic accident records that took place in the city of Porto Alegre/RS (Brazil) during the year of 2013. This study also provides an analysis of the most important attributes of a traffic accident that could produce an outcome of injury to the people involved in the accident.

  15. Modelling trends in road accident frequency - Bayesian inference for rates with uncertain exposure

    Lloyd, Louise

    2013-01-01

    Several thousand people die as a result of a road accident each year in Great Britain and the trend in the number of fatal accidents is monitored closely to understand increases and reductions in the number of deaths. Results from analysis of these data directly influence Government road safety policy and ensure theintroduction of effective safety interventions across the country. Overall accident numbers are important, but when disaggregating into various characteristics, accident risk (def...

  16. Accidents and human factors

    When the TMI accident occurred it was 4 a.m., an hour when the error potential of the operators would have been very high. The frequency of car and train accidents in Japan is also highest between 4 a.m. and 6 a.m. The error potential may be classified into five phases corresponding to the electroencephalogramic pattern (EEG). At phase 0, when the delta wave appears, a person is unconscious and in deep sleep; at phase I, when the theta wave appears, he is very tired, sleepy and subnormal; at phase II, when the alpha wave appears, he is normal, relaxed and passive; at phase III, when the beta wave appears, he is normal, clear-minded and active; at phase IV, when the strong beta or epileptic wave appears, he is hypernormal, excited and incapable of normal judgement. Should an accident occur at phase II, the brain condition may jump to phase IV. At this phase the error or accident potential is maximum. The response of the human brain to different types of noises and signals may vary somewhat for different individuals and for different groups of people. Therefore, the possibility that such differences in brain functions may influence the mental structure would be worthy of consideration in human factors and in the design of man-machine systems. Human reliability and performance would be affected by many factors: medical, physiological and psychological, etc. The uncertainty involved in human factors may not necessarily be probabilistic, but fuzzy. Therefore, it would be important to develop a theory by which both non-probabilistic uncertainties, or fuzziness, of human factors and the probabilistic properties of machines can be treated consistently. From the mathematical point of view, probabilistic measure is considered a special case of fuzzy measure. Therefore, fuzzy set theory seems to be an effective tool for analysing man-machine systems. To minimize human error and the possibility of accidents, new safety systems should not only back up man and make up for his

  17. Radiation accident/disaster

    Described are the course of medical measures following Fukushima Daiichi Nuclear Power Plant (FNPP) Accident after the quake and tsunami (Mar. 11, 2011) and the future task for radiation accident/disaster. By the first hydrogen explosion in FNPP (Mar. 12), evacuation of residents within 20 km zone was instructed, and the primary base for measures of nuclear disaster (Off-site Center) 5 km afar from FNPP had to work as a front base because of damage of communicating ways, of saving of injured persons and of elevation of dose. On Mar. 13, the medical arrangement council consisting from stuff of Fukushima Medical University (FMU), National Institute of Radiological Sciences, Nuclear Safety Research Association and Prefectural officers was setup in residents' hall of Fukushima City, and worked for correspondence to persons injured or exposed, where communication about radiation and between related organizations was still poor. The Off-site Center's head section moved to Prefectural Office on Mar. 15 as headquarters. Early in the period, all residents evacuated from the 20 km zone, and in-hospital patients and nursed elderly were transported with vehicles, >50 persons of whom reportedly died mainly by their base diseases. The nation system of medicare for emergent exposure had consisted from the network of the primary to third facilities; there were 5 facilities in the Prefecture, 3 of which were localized at 4-9 km distance from FNPP and closed early after the Accident; and the secondary facility of FMU became responsible to all exposed persons. There was no death of workers of FNPP. Medical stuff also measured the ambient dose at various places near FNPP, having had risk of exposure. At the Accident, the important system of command, control and communication was found fragile and measures hereafter should be planned on assumption of the worst scenario of complete damage of the infrastructure and communication. It is desirable for Disaster Medical Assistance Team which

  18. Systematic register of nuclear accidents

    The Systematic Register of Nuclear Accidents is a consolidation of important accidents occurred in the world during the period 1945-1984. Important accidents can be defined as those involving high radiation doses, which require the exposed individuals to undergo medical treatment. The organization and structuring of this register rests on the necessity for the availability of a database specifically oriented to researchers interested in studying the different nuclear accidents reported. Approximately 150 accidents in that period are presented in a summary form; these accidents had been described or reported in the scientific literature or made known through informal communications of Brazilian and foreign institutions and researchers. This register can be of interest particularly to all professionals who either directly of indirectly work in the area of nuclear or radioactive installations safety. In order to facilitate analysis by the researcher, that casuistic system was divided into 3 groups: criticality accidents (table I), fall-out on Marshall Islands (table II) and external irradiation accidents (table III). It is also included an overview of accidents in that period, indicating the total number of victims, fatal cases, and number of survivors. The author offers to the reader an extensive bibliography on the accidents described. (Author)

  19. Occupational accidents with mowing machines in Austrian agriculture.

    Kogler, Robert; Quendler, Elisabeth; Boxberger, Josef

    2015-01-01

    The number of recognized accidents during agricultural work is still very high in Austria. In the years 2008 to 2009, there occurred 84 approved work accidents with mowing machines. The main causes of accidents were the loss of control of machines, transportations or conveyances, hand tools, objects or animals. In the literature, numerous studies of general agricultural and forestry accident situations are available. Detailed studies on specific types of agricultural machines, which describe concrete circumstances and causes of accidents, are in limited numbers. The accident database from the General Accident Insurance Institution and the Austrian Social Insurance Institution of Farmers, with personal and accidental data information about mowing machine accidents, were analyzed. The results showed that most accidents occurred on mixed agricultural farms (68%). The majority of the injured persons were male (86%), over 40-years-old (86%) with an agricultural or forestry education (91%). The most common accidents occurred in the summer months (69%) and on afternoons during the working week (79%). The majority of accidents were caused by contact with the machine (55%) and the loss of control (73%) during their operation (60%) and harvesting work (63%). The most frequently injuries were wounds, fractures and superficial injuries (81%) to the upper and lower extremities (66%). The results of the chi-square test showed significant correlations between the specific task with the form of contact, the working process, the day and season. Results of the odds ratio determination showed an increased risk of suffering serious injury for men in the first half of the year and half of the day due to loss of control over the machine during agricultural harvesting work. PMID:25780843

  20. Occupational accidents with mowing machines in Austrian agriculture

    Robert Kogler

    2015-02-01

    Full Text Available The number of recognized accidents during agricultural work is still very high in Austria. In the years 2008 to 2009, there occurred 84 approved work accidents with mowing machines. The main causes of accidents were the loss of control of machines, transportations or conveyances, hand tools, objects or animals. In the literature, numerous studies of general agricultural and forestry accident situations are available. Detailed studies on specific types of agricultural machines, which describe concrete circumstances and causes of accidents, are in limited numbers. The accident database from the General Accident Insurance Institution and the Austrian Social Insurance Institution of Farmers, with personal and accidental data information about mowing machine accidents, were analyzed. The results showed that most accidents occurred on mixed agricultural farms (68%. The majority of the injured persons were male (86%, over 40-years-old (86% with an agricultural or forestry education (91%. The most common accidents occurred in the summer months (69% and on afternoons during the working week (79%. The majority of accidents were caused by contact with the machine (55% and the loss of control (73% during their operation (60% and harvesting work (63%. The most frequently injuries were wounds, fractures and superficial injuries (81% to the upper and lower extremities (66%. The results of the chi-square test showed significant correlations between the specific task with the form of contact, the working process, the day and season. Results of the odds ratio determination showed an increased risk of suffering serious injury for men in the first half of the year and half of the day due to loss of control over the machine during agricultural harvesting work.

  1. Severe accident analysis methodology in support of accident management

    The author addresses the implementation at BELGATOM of a generic severe accident analysis methodology, which is intended to support strategic decisions and to provide quantitative information in support of severe accident management. The analysis methodology is based on a combination of severe accident code calculations, generic phenomenological information (experimental evidence from various test facilities regarding issues beyond present code capabilities) and detailed plant-specific technical information

  2. Accident under-reporting among employees: testing the moderating influence of psychological safety climate and supervisor enforcement of safety practices.

    Probst, Tahira M; Estrada, Armando X

    2010-09-01

    We examined accident under-reporting with data from 425 employees employed in 5 industries with above average risk for employee injuries. We expected that rates for unreported accidents would be higher than rates for reported accidents; and that organizational safety climate and perceptions of supervisor enforcement of safety policies would moderate the relationship between unreported accidents and reported accidents. Results showed that the number of unreported accidents was significantly higher than the number of reported accidents. There was an average of 2.48 unreported accidents for every accident reported to the organization. Further, under-reporting was higher in working environments with poorer organizational safety climate or where supervisor safety enforcement was inconsistent. We discuss the implications of these findings for improving accident under-reporting and occupational safety in the workplace. PMID:20538099

  3. Stress in accident and post-accident management at Chernobyl

    The effects of the Chernobyl nuclear accident on the psychology of the affected population have been much discussed. The psychological dimension has been advanced as a factor explaining the emergence, from 1990 onwards, of a post-accident crisis in the main CIS countries affected. This article presents the conclusions of a series of European studies, which focused on the consequences of the Chernobyl accident. These studies show that the psychological and social effects associated with the post-accident situation arise from the interdependency of a number of complex factors exerting a deleterious effect on the population. We shall first attempt to characterise the stress phenomena observed among the population affected by the accident. Secondly, we will be presenting an anlysis of the various factors that have contributed to the emerging psychological and social features of population reaction to the accident and in post-accident phases, while not neglecting the effects of the pre-accident situation on the target population. Thirdly, we shall devote some initial consideration to the conditions that might be conducive to better management of post-accident stress. In conclusion, we shall emphasise the need to restore confidence among the population generally. (Author)

  4. Source term and radiological consequences of the Chernobyl accident

    This report presents the results of a study of the source term and radiological consequences of the Chernobyl accident. The results two parts. The first part was performed during the first 2 months following the accident and dealt with the evaluation of the source term and an estimate of individual doses in the European countries outside the Soviet Union. The second part was performed after August 25-29, 1986 when the Soviets presented in a IAEA Conference in Vienna detailed information about the accident, including source term and radiological consequences in the Soviet Union. The second part of the study reconfirms the source term evaluated in the first part and in addition deals with the radiological consequences in the Soviet Union. Source term and individual doses are calculated from measured post-accident data, reported by the Soviet Union and European countries, microcomputer program PEAR (Public Exposure from Accident Releases). 22 refs

  5. Storybuilder-A tool for the analysis of accident reports

    As part of an ongoing effort by the ministry of Social Affairs and Employment of The Netherlands a research project is being undertaken to construct a causal model for the most commonly occurring scenarios related to occupational risk. This model should provide quantitative insight in the causes and consequences of occupational accidents. The results should be used to help selecting optimal strategies to reduce these risks taking the costs of accidents and of measures into account. The research is undertaken by an international consortium under the name of Workgroup Occupational Risk Model. One of the components of the model is a tool to systematically classify and analyse past accidents. This tool: 'Storybuilder' and its place in the Occupational Risk Model (ORM) are described in the paper. The paper gives some illustrations of the application of the Storybuilder, drawn from the study of ladder accidents, which forms one of the biggest single accident categories in the Dutch data

  6. GPHS-RTG launch accident analysis for Galileo and Ulysses

    This paper presents the safety program conducted to determine the response of the General Purpose Heat Source (GPHS) Radioisotope Thermoelectric Generator (RTG) to potential launch accidents of the Space Shuttle for the Galileo and Ulysses missions. The National Aeronautics and Space Administration (NASA) provided definition of the Shuttle potential accidents and characterized the environments. The Launch Accident Scenario Evaluation Program (LASEP) was developed by GE to analyze the RTG response to these accidents. RTG detailed response to Solid Rocket Booster (SRB) fragment impacts, as well as to other types of impact, was obtained from an extensive series of hydrocode analyses. A comprehensive test program was conducted also to determine RTG response to the accident environments. The hydrocode response analyses coupled with the test data base provided the broad range response capability which was implemented in LASEP

  7. TRAC-PF1/MOD1 calculations and data comparisons for MIST [Multi-Loop Integral System Test] small-break loss-of-coolant accidents with scaled 10 cm2 and 50 cm2 breaks

    Los Alamos National Laboratory is a participant in the Integral System Test (IST) program initiated in June 1983 for the purpose of providing integral system test data on specific issues/phenomena relevant to post-small-break loss-of-coolant accidents (SBLOCAs), loss of feedwater and other transients in Babcock and Wilcox (B and W) plant designs. The Multi-Loop Integral System Test (MIST) facility is the largest single component in the IST program. MIST is a 2 x 4 (2 hot legs and steam generators, 4 cold legs and reactor-coolant pumps) representation of lowered-loop reactor systems of the B and W design. It is a full-height, full-pressure facility with 1/817 power and volume scaling. Two other experimental facilities are included in the IST program: test loops at the University of Maryland, College Park, and at Stanford Research Institute. The objective of the IST tests is to generate high-quality experimental data to be used for assessing thermal-hydraulic safety computer codes. Efforts are underway at Los Alamos to assess TRAC-PF1/MOD1 against data from each of the IST facilities. Calculations and data comparisons for TRAC-PF1/MOD1 assessment have been completed for two transients run in the MIST facility. These are the MIST nominal test. Test 3109AA, a scaled 10 cm2 SBLOCA and Test 320201, a scaled 50 cm2 SBLOCA. Only MIST assessment results are presented in this paper

  8. Accidents with biological material in workers

    Cleonice Andréa Alves Cavalcante

    2013-11-01

    Full Text Available The objective was to describe the accidents with biological material occurred among workers of Rio Grande do Norte, Brazil, between 2007 and 2009. Secondary data were collected in the National Notifiable Diseases Surveillance System by exporting data to Excel using Tabwin. Among the types of occupational accidents reported in the state, the biological accidents (no. = 1,170 accounted for 58.3% with a predominance of cases among nurses (48.6%. The percutaneous exposure was the most frequent occurrence and the circumstances of the accidents were related to the handling of sharps and the most common organic material was blood (63.5%. More than 50% of the workers were vaccinated against hepatitis B, but without information regarding the evaluation of vaccine response. The study revealed the need of improvement in the quality of the information, once the sub-entries and inconsistencies make the National Notifiable Diseases Surveillance System less trustworthy in the characterization of the affected workers.

  9. Accident management insights from IPE's

    In response to the U.S. Nuclear Regulatory Commission's Generic Letter 88-20, each utility in the U.S.A. has undertaken a probabilistic severe accident study of each plant. This paper provides a high level summary of the generic PWR accident management insights that have been obtained from the IPE reports. More importantly, the paper details some of the limitations of the IPE studies with respect to accident management. The IPE studies and the methodology used was designed to provide a best estimate of the potential for a severe accident and/or for severe consequences from a core damage accident. The accepted methodology employs a number of assumptions to make the objective attainable with a reasonable expenditure of resources. However, some of the assumptions represent limitations with respect to developing an accident management program based solely on the IPE and its results. (author)

  10. Correspondence model of occupational accidents

    Juan C. Conte

    2011-09-01

    Full Text Available We present a new generalized model for the diagnosis and prediction of accidents among the Spanish workforce. Based on observational data of the accident rate in all Spanish companies over eleven years (7,519,732 accidents, we classified them in a new risk-injury contingency table (19×19. Through correspondence analysis, we obtained a structure composed of three axes whose combination identifies three separate risk and injury groups, which we used as a general Spanish pattern. The most likely or frequent relationships between the risk and injuries identified in the pattern facilitated the decision-making process in companies at an early stage of risk assessment. Each risk-injury group has its own characteristics, which are understandable within the phenomenological framework of the accident. The main advantages of this model are its potential application to any other country and the feasibility of contrasting different country results. One limiting factor, however, is the need to set a common classification framework for risks and injuries to enhance comparison, a framework that does not exist today. The model aims to manage work-related accidents automatically at any level.Apresentamos aqui um modelo generalizado para o diagnóstico e predição de acidentes na classe de trabalhadores da Espanha. Baseados em dados sobre a frequência de acidentes em todas as companhias da Espanha em 11 anos (7.519.732 acidentes, nós os classificamos em uma nova tabela de contingência risco-injúria (19×19. Através de uma análise por correspondência obtivemos uma estrutura composta por 3 eixos cuja combinação identifica 3 grupos separados de risco e injúria, que nós usamos como um perfil geral na Espanha. As mais prováveis ou frequentes relações entre risco e injúrias identificadas nesse perfil facilitaram o processo de decisão nas companhias em um estágio inicial de apreciação do risco. Cada grupo de risco-injúria tem suas próprias caracter

  11. Design and operation of the data acquisition and reduction system used in the applied mechanics division for mechanical tests and the post accident heat removal experiments

    This paper describes the design and use of a powerful data acquisition system based on a multi-user minicomputer. The system acquires data simultaneously from a number of different types of instruments and front-end microcomputers, performs some signal processing and generates alarm levels to the experimental plant, while running one or more programs (remote consoles) to provide presentations of the collected data in graphical form, or to support assignments of alarm values. A data base has been created and general programs for data manipulation, plotting and mathematical analysis have been written and documented. This work continues to provide more specialized computation for new applications. Essentially no knowledge of computers is required for data acquisition, file management and initiation of programs. This paper is divided into four parts: laboratory environment; system configuration; software potential; and basic criteria for reliable use of the system

  12. Pattern Recognition and Classification of Fatal Traffic Accidents in Israel A Neural Network Approach

    Prato, Carlo Giacomo; Gitelman, Victoria; Bekhor, Shlomo

    2011-01-01

    : (1) single-vehicle accidents of young drivers, (2) multiple-vehicle accidents between young drivers, (3) accidents involving motorcyclists or cyclists, (4) accidents where elderly pedestrians crossed in urban areas, and (5) accidents where children and teenagers cross major roads in small urban areas......This article provides a broad picture of fatal traffic accidents in Israel to answer an increasing need of addressing compelling problems, designing preventive measures, and targeting specific population groups with the objective of reducing the number of traffic fatalities. The analysis focuses on...... 1,793 fatal traffic accidents occurred during the period between 2003 and 2006 and applies Kohonen and feed-forward back-propagation neural networks with the objective of extracting from the data typical patterns and relevant factors. Kohonen neural networks reveal five compelling accident patterns...

  13. Analysis of freight train accident statistics for 1972-1974

    Both train speed and dollar damage have been used in transportation studies as measures of accident severity. Analysis of freight train accident data for the three year period, 1972-74 showed that, in general, as speed increases dollar damage to railroad property also increases. A greater percentage of high speed than low speed accidents result in high dollar damage. Factors, in addition to speed, that can have an important effect on accident severity include the type of accident, the kinds of railcars and other equipment involved, and the geographical environmental of the accident. Threshold levels of accident stresses (e.g., impact and puncture forces and fire temperature and duration) are required to compromise the integrity of shipping containers used for the transport of radioactive materials. Analyses of accident severity using either speed or dollar damage as a basis can provide some insights into the possible risks involved in transport of radioactive materials. however, care must be taken in the strict use of results since there is no direct correlation between either speed or dollar damage and cask failure threshold levels

  14. Real and mythical consequences of Chernobyl accident

    not a most hazardous ones. Such psychological effects of the Chernobyl accident resulted from the lack of public information, the stress of relocation and the fear that any radiation exposures are damaging. Those affected people are believing that illnesses of all kinds are due to radiation. The spreading of such mistaken did influence on general public disapproval of Nuclear Power. This presentation includes also the data of real consequences for the health of concerned population

  15. Accident management insights after the Fukushima Daiichi NPP accident

    The Fukushima Daiichi nuclear power plant (NPP) accident, that took place on 11 March 2011, initiated a significant number of activities at the national and international levels to reassess the safety of existing NPPs, evaluate the sufficiency of technical means and administrative measures available for emergency response, and develop recommendations for increasing the robustness of NPPs to withstand extreme external events and beyond design basis accidents. The OECD Nuclear Energy Agency (NEA) is working closely with its member and partner countries to examine the causes of the accident and to identify lessons learnt with a view to the appropriate follow-up actions to be taken by the nuclear safety community. Accident management is a priority area of work for the NEA to address lessons being learnt from the accident at the Fukushima Daiichi NPP following the recommendations of Committee on Nuclear Regulatory Activities (CNRA), Committee on the Safety of Nuclear Installations (CSNI), and Committee on Radiation Protection and Public Health (CRPPH). Considering the importance of these issues, the CNRA authorised the formation of a task group on accident management (TGAM) in June 2012 to review the regulatory framework for accident management following the Fukushima Daiichi NPP accident. The task group was requested to assess the NEA member countries needs and challenges in light of the accident from a regulatory point of view. The general objectives of the TGAM review were to consider: - enhancements of on-site accident management procedures and guidelines based on lessons learnt from the Fukushima Daiichi NPP accident; - decision-making and guiding principles in emergency situations; - guidance for instrumentation, equipment and supplies for addressing long-term aspects of accident management; - guidance and implementation when taking extreme measures for accident management. The report is built on the existing bases for capabilities to respond to design basis

  16. Accident management approach in Armenia

    In this lecture the accident management approach in Armenian NPP (ANPP) Unit 2 is described. List of BDBAs had been developed by OKB Gydropress in 1994. 13 accident sequences were included in this list. The relevant analyses had been performed in VNIIAES and the 'Guidelines on operator actions for beyond design basis accident (BDBA) management at ANPP Unit 2' had been prepared. These instructions are discussed

  17. Chernobyl reactor accident

    Following the accident at Chernobyl nuclear reactor, WHO organized on 6 May 1986 in Copenhagen a one day consultation of experts with knowledge in the fields of meteorology, radiation protection, biological effects, reactor technology, emergency procedures, public health and psychology in order to analyse the development of events and their consequences and to provide guidance as to the needs for immediate public health action. The present report provides detailed information on the transportation and dispersion of the radioactive material in the atmosphere, especially volatile elements, during the release period 26 April - 5 May. Presented are the calculated directions and locations of the radioactive plume over Europe in the first 5 days after the accident, submitted by the Swedish Meteorological and Hydrological Institute. The calculations have been made for two heights, 1500m and 750m and the plume directions are grouped into five periods, covering five European areas. The consequences of the accident inside the USSR and the radiological consequences outside the USSR are presented including the exposure routes and the biological effects, paying particular attention to iodine-131 effects. Summarized are the first reported measured exposure rates above background, iodine-131 deposition and concentrations in milk and the remedial actions taken in various European countries. Concerning the cesium-137 problem, based on the UNSCEAR assessment of the consequences of the nuclear fallout, one concludes that the cesium contamination outside the USSR is not likely to cause any serious problems. Finally, the conclusions and the recommendations of the meeting, taking into account both the short-term and longer term considerations are presented

  18. Investigation of adolescent accident predictive variables in hilly regions.

    Mohanty, Malaya; Gupta, Ankit

    2016-09-01

    The study aims to determine the significant personal and environmental factors in predicting the adolescent accidents in the hilly regions taking into account two cities Hamirpur and Dharamshala, which lie at an average elevation of 700--1000 metres above the mean sea level (MSL). Detailed comparisons between the results of 2 cities are also studied. The results are analyzed to provide the list of most significant factors responsible for adolescent accidents. Data were collected from different schools and colleges of the city with the help of a questionnaire survey. Around 690 responses from Hamirpur and 460 responses from Dharamshala were taken for study and analysis. Standard deviations (SD) of various factors affecting accidents were calculated and factors with relatively very low SD were discarded and other variables were considered for correlations. Correlation was developed using Kendall's-tau and chi-square tests and factors those were found significant were used for modelling. They were - the victim's age, the character of road, the speed of vehicle, and the use of helmet for Hamirpur and for Dharamshala, the kind of vehicle involved was an added variable found responsible for adolescent accidents. A logistic regression was performed to know the effect of each category present in a variable on the occurrence of accidents. Though the age and the speed of vehicle were considered to be important factors for accident occurrence according to Indian accident data records, even the use of helmet comes out as a major concern. The age group of 15-18 and 18-21 years were found to be more susceptible to accidents than the higher age groups. Due to the presence of hilly area, the character of road becomes a major concern for cause of accidents and the topography of the area makes the kind of vehicle involved as a major variable for determining the severity of accidents. PMID:26077876

  19. Serious accident in Peru

    A peruvian man, victim of an important accidental irradiation arrived on the Saturday twenty ninth of may 1999 to the centre of treatment of serious burns at the Percy military hospital (Clamart -France). The accident spent on the twentieth of February 1999, on the site of a hydroelectric power plant, in construction at 300 km at the East of Lima. The victim has picked up an industrial source of iridium devoted to gamma-graphy operations and put it in his back pocket; of trousers. The workman has serious radiation burns. (N.C.)

  20. Accident prevention programme

    This study by the Steel Industry Safety and Health Commission was made within the context of the application by undertakings of the principles of accident and disease prevention previously adopted by the said Commission. It puts forward recommendations for the effective and gradual implementation of a programme of action on occupational health and safety in the various departments of an undertaking and in the undertaking as a whole. The methods proposed in this study are likely to be of interest to all undertakings in the metallurgical industry and other industrial sectors

  1. Psychological response of accident

    The psychological status of rescuers of consequences of Chernobyl[s accidents, having planned stationary examination and treatment of common somatic diseases, has been examined. THe age of men represented the study group was 35-54 years old. The results of medical-psychological examination showed the development in rescuers of common dysadaptation and stress state, characterized by depressive-hypochondriac state with high anxiety. The course of psychotherapeutic activities made possible to improve essentionally the psychological status of the patients. 12 refs., 3 figs., 1 tab

  2. Reactor accident in Chernobyl

    The bibliography contains 1568 descriptions of papers devoted to Chernobylsk accident and recorded in ''INIS Atomindex'' to 30 June 1990. The descriptions were taken from ''INIS Atomindex'' and are presented in accordance with volumes of this journal (chronology of recording). Therefore all descriptions have numbers showing first the number of volume and then the number of record. The bibliography has at the end the detailed subject index consisting of 465 main headings and a lot of qualifiers. Some of them are descriptors taken from ''INIS Atomindex'' and some are key words taken from natural language. The index is in English as descriptions in the bibliography. (author)

  3. CAMS: Computerized Accident Management Support

    The OECD Halden Reactor Project has initiated a new research programme on computerised accident management support, the so-called CAMS project (CAMS = Computerized Accident Management Support). This work will investigate the possibilities for developing systems which provide more extensive support to the control room staff and technical support centre than the existing SPDS (Safety Parameter Display System) type of systems. The CAMS project will utilize available simulator codes and the capabilities of computerized tools to assist the plant staff during the various accident stages including: identification of the accident state, assessment of the future development of the accident, and planning accident mitigation strategies. This research programme aims at establishing a prototype system which can be used for experimental testing of the concept and serve as a tool for training and education in accident management. The CAMS prototype should provide support to the staff when the plant is in a normal state, in a disturbance sate, and in an accident state. Even though better support in an accident state is the main goal of the project, it is felt to be important that the staff is familiar with the use of the system during normal operation, when they utilize the system during transients

  4. Iodine releases from reactor accidents

    The airborne releases of iodine from water reactor accidents are small fractions of the available iodine and occur only slowly. However, in reactor accidents in which water is absent, the release of iodine to the environment can be large and rapid. These differences in release fraction and rate are related to the chemical states attained by iodine under the accident conditions. It is clear that neither rapid issue of blocking KI nor rapid evacuation of the surrounding population is required to protect the public from the radioiodine released in the event of a major water reactor accident

  5. Guidance on accidents involving radioactivity

    This annex contains advice to Health Authorities on their response to accidents involving radioactivity. The guidance is in six parts:-(1) planning the response required to nuclear accidents overseas, (2) planning the response required to UK nuclear accidents a) emergency plans for nuclear installations b) nuclear powered satellites, (3) the handling of casualties contaminated with radioactive substances, (4) background information for dealing with queries from the public in the event of an accident, (5) the national arrangements for incident involving radioactivity (NAIR), (6) administrative arrangements. (author)

  6. A stochastic approach to accident identification in nuclear power plants

    Identification of the types of accidents and proper actions is required at an early stage of an accident in nuclear power plants. The accident of the plant can be identified by their symptom patterns related to the principal variables and operating status of major equipment. The patterns are identified by the Self-Organizing Feature Map (SOFM), unsupervised artificial neural network, for feature mapping algorithm and the Hidden Markov Model (HMM), a stochastic technique for solving the time series problem. The off-line data from a compact nuclear simulator are vector quantized by SOFM clustering algorithm. The HMM is created for each accident from a set of training data which are the result of vector quantization. The accident identification is decided by calculating which model has the highest probability for given test data. The system uses a left-to-right model including 6 states and 16 input variables to identify 7 types of accidents and the normal state. The HMM is trained by the maximum-likelihood estimation method which uses forward-backward algorithm and Baum-Welch re-estimation algorithm. The optimal path for each model at the given observation is found by Viterbi algorithm, and then the probability of optimal path is calculated. The simulation results show that the proposed system identifies the accident types correctly. It is also shown that the diagnosis is performed well for incomplete input observation caused by sensor fault or malfunction of certain equipment. (author). 13 refs, 4 figs, 2 tabs

  7. Changes in the brain of subjects who participated in liquidation of the Chernobyl power plant accident consequences as shown by the data of radiodiagnosis (emission single-photon computer-aided scintigraphy, X-ray computer -aided and magnetic resonanse tomography)

    Presents the data of X-ray examinations of the brain in liquidators of the consequences of the Chernobyl power plant accident. Findings of X-ray methods of diagnosis permit a conclusion on a complex organic involvement of the brain in subjects who participated in liquidation of the consequences of the Chernobyl power plant accident. The most typical are signs of the hypertensive hydricephalic syndrome with liquorodynamic disturbances and of the vascular encephalic syndrome with development of local postischemic malacia of the brain matter. 7 refs., 5 figs.,

  8. Comparative Assessment Of Natural Gas Accident Risks

    Burgherr, P.; Hirschberg, S

    2005-01-01

    The study utilizes a hierarchical approach including (1) comparative analyses of different energy chains, (2) specific evaluations for the natural gas chain, and (3) a detailed overview of the German situation, based on an extensive data set provided by Deutsche Vereinigung des Gas- und Wasserfaches (DVGW). According to SVGW-expertise DVGW-data can be regarded as fully representative for Swiss conditions due to very similar technologies, management, regulations and safety culture, but has a substantially stronger statistical basis because the German gas grid is about 30 times larger compared to Switzerland. Specifically, the following tasks were carried out by PSI to accomplish the objectives of this project: (1) Consolidation of existing ENSAD data, (2) identification and evaluation of additional sources, (3) comparative assessment of accident risks, and (4) detailed evaluations of specific issues and technical aspects for severe and smaller accidents in the natural gas chain that are relevant under Swiss conditions. (author)

  9. Comparative Assessment Of Natural Gas Accident Risks

    The study utilizes a hierarchical approach including (1) comparative analyses of different energy chains, (2) specific evaluations for the natural gas chain, and (3) a detailed overview of the German situation, based on an extensive data set provided by Deutsche Vereinigung des Gas- und Wasserfaches (DVGW). According to SVGW-expertise DVGW-data can be regarded as fully representative for Swiss conditions due to very similar technologies, management, regulations and safety culture, but has a substantially stronger statistical basis because the German gas grid is about 30 times larger compared to Switzerland. Specifically, the following tasks were carried out by PSI to accomplish the objectives of this project: (1) Consolidation of existing ENSAD data, (2) identification and evaluation of additional sources, (3) comparative assessment of accident risks, and (4) detailed evaluations of specific issues and technical aspects for severe and smaller accidents in the natural gas chain that are relevant under Swiss conditions. (author)

  10. Safety investigation of team performance in accidents.

    Petkov, G; Todorov, V; Takov, T; Petrov, V; Stoychev, K; Vladimirov, V; Chukov, I

    2004-07-26

    The paper presents the capacities of the performance evaluation of teamwork (PET) method. Its practicability and efficiency are illustrated by retrospective human reliability analyse of the famous nuclear and maritime accidents. A quantitative assessment of operators' performance on the base of thermo-hydraulic (T/H) calculations and full-scope simulator data for set of NPP design basic accidents with WWER is demonstrated. The last data are obtained on the 'WWER-1000' full-scope simulator of Kozloduy NPP during the regular practical training of the operators' teams. An outlook on the "evaluation system of main control room (MCR) operators' reliability" project, based on simulator data of operators' training is given. PMID:15231353

  11. Radiation accident grips Goiania

    On 13 September two young scavengers in Goiania, Brazil, removed a stainless steel cylinder from a cancer therapy machine in an abandoned clinic, touching off a radiation accident second only to Chernobyl in its severity. On 18 September they sold the cylinder, the size of a 1-gallon paint can, to a scrap dealer for $25. At the junk yard an employee dismantled the cylinder and pried open the platinum capsule inside to reveal a glowing blue salt-like substance - 1400 curies of cesium-137. Fascinated by the luminescent powder, several people took it home with them. Some children reportedly rubbed in on their bodies like carnival glitter - an eerie image of how wrong things can go when vigilance over radioactive materials lapses. In all, 244 people in Goiania, a city of 1 million in central Brazil, were contaminated. The eventual toll, in terms of cancer or genetic defects, cannot yet be estimated. Parts of the city are cordoned off as radiation teams continue washing down buildings and scooping up radioactive soil. The government is also grappling with the political fallout from the accident

  12. Serious reactor accidents reconsidered

    The chance is determined for damage of the reactor core and that sequel events will cause excursion of radioactive materials into the environment. The gravity of such an accident is expressed by the source term. It appears that the chance for such an accident varies with the source term. In general it is valid that how larger the source term how smaller the chance is for it and vice versa. The chance for excursion is related to two complexes of events: serious damage (meltdown) of the reactor core, and the escape of the liberated radionuclides into the environment. The results are an order of magnitude consideration of the relation between the extent of the source term and the chance for it. From the spectrum of possible source terms three representative ones have been chosen: a large, a medium and a relative small source term. This choice is in accordance with international considerations. The hearth of this study is the estimation of the chance for occurrence of the three chosen source terms for new light-water reactors. refs.; figs.; tabs

  13. Severe accident aerosol research in Finland

    The retention of fission products in the steam generator tubing and in the secondary side is poorly understood at the moment. Most experimental programs have concentrated on the initial stages of deposition. Much less attention has been paid to the situations when deposition-resuspension-revaporisation are important as the deposit layers are getting thicker. The understanding of fission product deposition in realistic steam generator conditions is needed to design efficient accident management procedures. For example if there is large deposition already in the ruptured pipe(s), the accident management procedure is different from the case where most deposition would occur in the secondary side. This is considered very important because steam generator tube rupture sequences are included in the risk dominant sequences. Aerosol deposition has been studied widely in laboratory scale. However, most of the studies have concentrated on situations where the deposit layer is thin and do not significantly affect the process. In severe accident applications the most important deposition studies have been LACE, STORM, TUBA, TRANSAT and AIDA programmes. None of these tests considered steam generator conditions. Thus we can say that there is basic knowledge on aerosol deposition and removal from gas streams in water pools, but it can not be applied directly to steam generator tube rupture cases. At the moment the effectiveness of such accident management procedures as secondary side flooding can not be verified as there is no experimental data and the models in severe accident codes are poor or non-existing. As a results of this work we will get data on deposition in the tubing, in the break location and in the secondary side. Experiments will be performed in horizontal steam generators (VVER reactors). (orig.)

  14. Severe Accident Test Station Activity Report

    Pint, Bruce A [ORNL; Terrani, Kurt A [ORNL

    2015-06-01

    Enhancing safety margins in light water reactor (LWR) severe accidents is currently the focus of a number of international R&D programs. The current UO2/Zr-based alloy fuel system is particularly susceptible since the Zr-based cladding experiences rapid oxidation kinetics in steam at elevated temperatures. Therefore, alternative cladding materials that offer slower oxidation kinetics and a smaller enthalpy of oxidation can significantly reduce the rate of heat and hydrogen generation in the core during a coolant-limited severe accident. In the U.S. program, the high temperature steam oxidation performance of accident tolerant fuel (ATF) cladding solutions has been evaluated in the Severe Accident Test Station (SATS) at Oak Ridge National Laboratory (ORNL) since 2012. This report summarizes the capabilities of the SATS and provides an overview of the oxidation kinetics of several candidate cladding materials. A suggested baseline for evaluating ATF candidates is a two order of magnitude reduction in the steam oxidation resistance above 1000ºC compared to Zr-based alloys. The ATF candidates are categorized based on the protective external oxide or scale that forms during exposure to steam at high temperature: chromia, alumina, and silica. Comparisons are made to literature and SATS data for Zr-based alloys and other less-protective materials.

  15. The expert assistant in accident management

    In the event of a nuclear accident in proximity to an urban area, the consequences resulting from the complex processes of environmental transport of radioactivity would require complex countermeasures. Emphasis has been placed on either modelling the potential effects of such an event on the population, or on attempting to predict the geographical evolution of the release. Less emphasis has been placed on the development of accident management aids with a in-built data acquisition capability. Given the problems of predicting the evolution of an accidental release of activity, more emphasis should be placed on the development of small regional systems specifically engineered to acquire and display environmental data in the most efficaceous form possible. A wealth of information can be obtained from appropriately-sited outstations which can aid those responsible for countermeasures in their decision making processes. The substantial volume of data which would arrive within the duration and during the aftermath of an accident requires skilled interpretation under conditions of considerable stress. It is necessary that a management aid notonly presents these data in a rapidly assimilable form, but is capable of making intelligent decisions of its own, on such matters as information display priority and the polling frequency of outstations. The requirement is for an expert assistant. The XERSES accident management aid has been designed with the foregoing features in mind. Intended for covering regions up to approximately 100 kms square, it links with between 1 and 64 outstations supplying a variety of environmental data. Under quiescent conditions the system will operate unattended, raising alarms remotely only when detecting abnormal conditions. Under emergency conditions, the system automatically adjusts such operating parameters as data acquisition rate

  16. An Epidemiological Study of Accidents among Construction Workers in Kerman

    Hasan Khaje

    2011-01-01

    Full Text Available Introduction: Accidents are known among the leading causes of deaths and disabilities in developing and industrialized countries. Among the various occupations and activities, construction industry is among the most hazardous industries in the world, the risk of which and its following harms are still somehow unknown. This study aimed at investigating the epidemiology of accidents in construction, for the first time in Kerman. Methods: In this descriptive, analytical study, all construction workers (n=153 who had been hurt at work during 2006-2008 were investigated. The data were collected through questionnaire and were analyzed by chi-square and regression logistic test, SPSS statistical software. Results: The mean age of the injured workers was 32 years (the lowest age was 16 and the highest was 70 years and the highest rate of accidents occurred among the 16-36 years-old age group. Generally, 16.3 % (n=25 of the accidents led to death and 77.8% of the accidents occurred to people with junior high school and lower levels of education. There were significant relationships between the three variables of year, season and the shift in which the accident occurred and the result (death or survival of the accident. However, no significant relationships were observed between the insurance status of the injured and the results of the accidents. Conclusion: In Iran, there are strong relationships between reasons and results of accidents, so this study recommends more studies with the aim of changing the current trend to prevent the accidents in future.

  17. The Fukushima Daiichi Accident. Technical Volume 1/5. Description and Context of the Accident. Annexes

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  18. The Fukushima Daiichi Accident. Technical Volume 5/5. Post-accident Recovery. Annexes

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  19. Accidents caused by electric currents; Unfaelle durch elektrischen Strom

    Juehling, J. [Berufsgenossenschaft der Feinmechanik und Elektrotechnik, Koeln (Germany). Inst. zur Erforschung Elektrischer Unfaelle

    1998-12-31

    The present evaluation only refers to accidents caused by electric currents in member companies of the employees` industrial compensation society of the fine mechanics and electrical engineering professions (BGFE). In some cases the institute also publishes statistics on the frequency time course of electrical accidents which deviate from those the relevant annual report. This is mainly due to the fact that these statistics also contain non-notifiable accidents communicated via medical reports and the supplementary report on electrical accidents. They further contain keyed data on electrical accidents reported by other employees` industrial compensation societies. Inquiries made to the institute may therefore be answered on the basis of all the above-mentioned data on electrical accidents as well as on the overall accident statistics of the BGFE. [Deutsch] Die nachfolgenden Auswertungen beziehen sich nur auf Unfaelle in Mitgliedsbetrieben der BG F und E, verursacht durch den elektrischen Strom. Zum Teil veroeffentlicht aber das Institut Zahlen ueber die zeitliche Entwicklung von Stromunfaellen, die nicht immer mit den Angaben der jeweiligen Jahresberichte uebereinstimmen muessen. Das liegt vor allem daran, dass auch nicht-meldepflichtige Unfaelle ueber den D-Arztbericht und ueber den Ergaenzungsbericht bei Unfaellen durch elektrischen Strom - also ueber aerztliche Erhebungsformulare - erfasst werden. Ausserdem werden auch von anderen Berufsgenossenschaften eingehende Stromunfaelle verschluesselt. Zur Beantwortung von Anfragen an das Institut koennen also all die vorgenannten Daten zu elektrischen Unfaellen und natuerlich auch die Zahlen zum Gesamtunfallgeschehen der BG F und E herangezogen werden. (orig.)

  20. Health Problems in Radiation Accidents

    The authors define a radiation accident as a situation which has led or could have led to the unexpected irradiation of persons or contamination of the environment over and above the levels accepted as safe. Several categories of accidents are distinguished as a function of the consequences to be expected. The suggested system of classifying accidents makes it possible to plan post-accident measures within a single system of 'concentric circles', taking into account at the same time whether it will be possible to carry out the post-accident measures unaided or whether it will be necessary to bring in additional manpower and resources from outside. The authors consider the possibility of countering the effects of accidents as a function of their nature, with reference to the biological, economic and psychological aspects. They evaluate the part played by the health service in planning and carrying out accident prevention measures, and consider the function of radiological units attached to epidemiological health stations ; these units are essentially centres providing for precautionary measures to avert accidents and action to counter their effects. (author)

  1. Containment severe accident thermohydraulic phenomena

    This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phenomenological knowledge, including an account of relevant experimental investigations and to discuss, to some extent, the modelling approach used in the MAAP 3.0 computer code. The MAAP code has been used in Sweden as the main tool in the analysis of severe accidents. The dependence of the containment accident progression and containment phenomena on the initial conditions, which in turn are heavily dependent on the in-vessel accident progression and phenomena as well as associated uncertainties, is emphasized. The report is in three parts dealing with: * Swedish reactor containments, the severe accident mitigation programme in Sweden and containment accident progression in Swedish PWRs and BWRs as predicted by the MAAP 3.0 code. * Key non-energetic ex-vessel phenomena (melt fragmentation in water, melt quenching and coolability, core-concrete interaction and high temperature in containment). * Early containment threats due to energetic events (hydrogen combustion, high pressure melt ejection and direct containment heating, and ex-vessel steam explosions). The report concludes that our understanding of the containment severe accident progression and phenomena has improved very significantly over the parts ten years and, thereby, our ability to assess containment threats, to quantify uncertainties, and to interpret the results of experiments and computer code calculations have also increased. (au)

  2. First Responders and Criticality Accidents

    Valerie L. Putman; Douglas M. Minnema

    2005-11-01

    Nuclear criticality accident descriptions typically include, but do not focus on, information useful to first responders. We studied these accidents, noting characteristics to help (1) first responders prepare for such an event and (2) emergency drill planners develop appropriate simulations for training. We also provide recommendations to help people prepare for such events in the future.

  3. Severe accident recriticality analyses (SARA)

    Frid, W.; Højerup, C.F.; Lindholm, I.;

    2001-01-01

    Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies, the ...

  4. The Chernobyl accident. Appendix B

    In appendix B, the models introduced in chapter 6 are applied to the study of the Chernobyl accident. This event is very important in the teaching of nuclear engineering, and I have included in this Appendix a relatively detailed description of the accident. However, the analysis is limited to the physics of the relevant phenomena. (author)

  5. Preventing accidents at intake towers

    Villegas, F. (INTEGRAL S.A., Medellin, CO (United States))

    1994-03-01

    Strong air blow-outs occurring in the intake tower of Guatape Hydroelectric Power Plant in Colombia have caused two serious accidents recently. The causes of the accidents were investigated and recommendations are made here to prevent future repetitions of these dangerous events. (UK)

  6. Occupational accidents aboard merchant ships

    Hansen, H; Nielsen, D; Frydenberg, M

    2002-01-01

    Objectives: To investigate the frequency, circumstances, and causes of occupational accidents aboard merchant ships in international trade, and to identify risk factors for the occurrence of occupational accidents as well as dangerous working situations where possible preventive measures may be initiated.

  7. Probability of spent fuel transportation accidents

    McClure, J. D.

    1981-07-01

    The transported volume of spent fuel, incident/accident experience and accident environment probabilities were reviewed in order to provide an estimate of spent fuel accident probabilities. In particular, the accident review assessed the accident experience for large casks of the type that could transport spent (irradiated) nuclear fuel. This review determined that since 1971, the beginning of official US Department of Transportation record keeping for accidents/incidents, there has been one spent fuel transportation accident. This information, coupled with estimated annual shipping volumes for spent fuel, indicated an estimated annual probability of a spent fuel transport accident of 5 x 10/sup -7/ spent fuel accidents per mile. This is consistent with ordinary truck accident rates. A comparison of accident environments and regulatory test environments suggests that the probability of truck accidents exceeding regulatory test for impact is approximately 10/sup -9//mile.

  8. Analysis of the TMI-2 accident using ATHLET-CD

    One analyzed the simulation of the TMI-2 NPP accident making use of the ATHLET-CD code. One describes the accident sequence, the code structure and performs the comparative analysis of the calculated and the measured data. Simulation of thermohydraulic characteristics was a special success. Application of the codes promotes the NPP optimization, the reactor safety improvement and the risk reduction. The ATHLET-CD system ( the thermohydraulic analysis of leaks and transient processes at the reactor core disruption) will allow to evaluate the adequacy of the models included in the available codes to calculate severe accidents

  9. Grey-Markov Model for Road Accidents Forecasting

    李相勇; 严余松; 蒋葛夫

    2003-01-01

    In order to improve the forecasting precision of road accidents, by introducing Markov chains forecasting method, a grey-Markov model for forecasting road accidents is established based on grey forecasting method. The model combines the advantages of both grey forecasting method and Markov chains forecasting method, overcomes the influence of random fluctuation data on forecasting precision and widens the application scope of the grey forecasting. An application example is conducted to evaluate the grey-Markov model, which shows that the precision of the grey-Markov model is better than that of grey model in forecasting road accidents.

  10. Radioecological and dosimetric consequences of Chernobyl accident in France

    After ten years and the taking in account of numerous data, it can be affirmed that the dosimetric consequences of Chernobyl accident will have been limited in France. for the period 1986-2046, the individual middle efficient dose commitment, for the area the most reached by depositing is inferior to 1500 μSv, that represents about 1% of middle natural exposure in the same time. but mountains and forests can have more important surface activities than in plain. Everywhere else, it can be considered that the effects of Chernobyl accident are disappearing. the levels of cesium 137 are now often inferior to what they were before the accident. (N.C.)

  11. Accident Occurrence and Functional Health Patterns. A Pilot Study of Relationships in a Graduate Population.

    Vries, Jan; CURTIS, ELIZABETH; SHEERIN, FINTAN

    2012-01-01

    PURPOSE: This pilot study sought to examine the relationship between functional health patterns and accident proneness. METHODS: A quantitative-descriptive design was employed assessing accident proneness by collecting data on the occurrence of accidents among a sample of university graduates, and examining this in relation to biographical data and information collated using the Functional Health Pattern Assessment Screening Tool (FHPAST). Data were analyzed using descriptive and i...

  12. Corporate Cost of Occupational Accidents

    Rikhardsson, Pall M.; Impgaard, M.

    2004-01-01

    The systematic accident cost analysis (SACA) project was carried out during 2001 by The Aarhus School of Business and PricewaterhouseCoopers Denmark with financial support from The Danish National Working Environment Authority. Its focused on developing and testing a method for evaluating...... occupational costs of companies for use by occupational health and safety professionals. The method was tested in nine Danish companies within three different industry sectors and the costs of 27 selected occupational accidents in these companies were calculated. One of the main conclusions is that the SACA...... method could be used in all of the companies without revisions. The evaluation of accident cost showed that 2/3 of the costs of occupational accidents are visible in the Danish corporate accounting systems reviewed while 1/3 is hidden from management view. The highest cost of occupational accidents...

  13. Severe accidents, a US approach

    The attitude of the American nuclear industry and the regulatory authorities in the United States toward severe accidents has often seemed ambivalent. It was common a few years ago to assume the position that severe accidents should not be included in the design basis of the plant. This view was associated with the concept of the maximum credible accident. A severe accident that would lead to a large release of fission products from the reactor core was simply regarded as having so low a likelihood as not to be credible. That does not mean that it had a zero probability of occurring. Because of the way the plant was designed, built, and operated, severe accidents were regarded as having a low enough probability that no further special measures were necessary regarding them. (author)

  14. Severe accident management. Prevention and Mitigation

    Effective planning for the management of severe accidents at nuclear power plants can produce both a reduction in the frequency of such accidents as well as the ability to mitigate their consequences if and when they should occur. This report provides an overview of accident management activities in OECD countries. It also presents the conclusions of a group of international experts regarding the development of accident management methods, the integration of accident management planning into reactor operations, and the benefits of accident management

  15. Severe Accident Test Station Design Document

    Snead, Mary A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yan, Yong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howell, Michael [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Keiser, James R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrani, Kurt A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-09-01

    The purpose of the ORNL severe accident test station (SATS) is to provide a platform for evaluation of advanced fuels under projected beyond design basis accident (BDBA) conditions. The SATS delivers the capability to map the behavior of advanced fuels concepts under accident scenarios across various temperature and pressure profiles, steam and steam-hydrogen gas mixtures, and thermal shock. The overall facility will include parallel capabilities for examination of fuels and irradiated materials (in-cell) and non-irradiated materials (out-of-cell) at BDBA conditions as well as design basis accident (DBA) or loss of coolant accident (LOCA) conditions. Also, a supporting analytical infrastructure to provide the data-needs for the fuel-modeling components of the Fuel Cycle Research and Development (FCRD) program will be put in place in a parallel manner. This design report contains the information for the first, second and third phases of design and construction of the SATS. The first phase consisted of the design and construction of an out-of-cell BDBA module intended for examination of non-irradiated materials. The second phase of this work was to construct the BDBA in-cell module to test irradiated fuels and materials as well as the module for DBA (i.e. LOCA) testing out-of-cell, The third phase was to build the in-cell DBA module. The details of the design constraints and requirements for the in-cell facility have been closely captured during the deployment of the out-of-cell SATS modules to ensure effective future implementation of the in-cell modules.

  16. Explaining the road accident risk: weather effects.

    Bergel-Hayat, Ruth; Debbarh, Mohammed; Antoniou, Constantinos; Yannis, George

    2013-11-01

    This research aims to highlight the link between weather conditions and road accident risk at an aggregate level and on a monthly basis, in order to improve road safety monitoring at a national level. It is based on some case studies carried out in Work Package 7 on "Data analysis and synthesis" of the EU-FP6 project "SafetyNet-Building the European Road Safety Observatory", which illustrate the use of weather variables for analysing changes in the number of road injury accidents. Time series analysis models with explanatory variables that measure the weather quantitatively were used and applied to aggregate datasets of injury accidents for France, the Netherlands and the Athens region, over periods of more than 20 years. The main results reveal significant correlations on a monthly basis between weather variables and the aggregate number of injury accidents, but the magnitude and even the sign of these correlations vary according to the type of road (motorways, rural roads or urban roads). Moreover, in the case of the interurban network in France, it appears that the rainfall effect is mainly direct on motorways--exposure being unchanged, and partly indirect on main roads--as a result of changes in exposure. Additional results obtained on a daily basis for the Athens region indicate that capturing the within-the-month variability of the weather variables and including it in a monthly model highlights the effects of extreme weather. Such findings are consistent with previous results obtained for France using a similar approach, with the exception of the negative correlation between precipitation and the number of injury accidents found for the Athens region, which is further investigated. The outlook for the approach and its added value are discussed in the conclusion. PMID:23928504

  17. Pseuchoneurotic disorders associated with the Chernobyl accident

    This survey relied largely on random selection. As a rule, the attention of the specialists was directed to people with certain specific complaints. Psychogenic disorders observed in the area of the accident at the Chernobyl plant were followed and studied by a team of specialists from the USSR Ministry of Health, beginning on 29 April 1986. According to the nature of the observed stress effects and of the resultant psychic disorders, it was possible to delineate three periods: first the acute period of the disaster from the time of the accident, lasting about 10 days until completion of the evacuation of the population from the danger zone (5 May); second the intermediate delayed period, the period of comparatively early consequences (from 6 May to October 1986); and third, the period of remote consequences. In the course of the year, 1,572 people were examined. The data available indicate that the psychogenic disorders observed after the Chernobyl accident can be regarded as the consequence of a single process, the dynamics of which are determined on the one hand by the characteristics of the emergency situation and on the other by the traits and the degree of preparedness of the people involved. The special nature of the stress situation in all three periods - the threat to health - gave rise to certain characteristic clinical observations, primarily a high degree of somatization and hypochondria. An understanding of the psychological disorders affecting those who lived through the Chernobyl accident, and of their effects on the work capability and pattern of life of people at various stages after the accident, has made it possible to develop and implement a complex and refined system of prophylactic and medical measures. (author)

  18. Artificial intelligence applications in accident management

    For nuclear power plant accident management, there are some addition concerns: linking AI systems to live data streams must be mastered; techniques for processing sensor inputs with varying data quality need to be provided; systems responsiveness to changing plant conditions and multiple user requests should, in general, be improved; there is a need for porting applications from specialized AI machines onto conventional computer hardware without incurring unacceptable performance penalties; human factors guidelines are required for new user interfaces in AI applications; methods for verification and validation of AI-based systems must be developed; and, finally, there is a need for proven methods to evaluate use effectiveness and firmly establish the benefits of AI-based accident management systems. (orig./GL)

  19. Estimating the frequency of nuclear accidents

    Raju, Suvrat

    2016-01-01

    We used Bayesian methods to compare the predictions of probabilistic risk assessment -- the theoretical tool used by the nuclear industry to predict the frequency of nuclear accidents -- with empirical data. The existing record of accidents with some simplifying assumptions regarding their probability distribution is sufficient to rule out the validity of the industry's analyses at a very high confidence level. We show that this conclusion is robust against any reasonable assumed variation of safety standards over time, and across regions. The debate on nuclear liability indicates that the industry has independently arrived at this conclusion. We pay special attention to the Indian situation, where we show that the existing operating experience provides insufficient data to make any reliable claims about the safety of future reactors. We briefly discuss some policy implications.

  20. Global impact of the Chernobyl reactor accident

    Radioactive material was deposited throughout the Northern Hemisphere as a result of the accident at the Chernobyl Nuclear Power Station on 26 April 1986. On the basis of a large amount of environmental data and new integrated dose assessment and risk models, the collective dose commitment to the approximately 3 billion inhabitants is calculated to be 930,000 person-gray, with 97% in the western Soviet Union and Europe. The best estimates for the lifetime expectation of fatal radiogenic cancer would increase the risk from 0 to 0.02% in Europe and 0 to 0.003% in the Northern Hemisphere. By means of an integration of the environmental data, it is estimated that approximately 100 petabecquerels of cesium-137 (1 PBq = 10(15) Bq) were released during and subsequent to the accident

  1. Accidents, probabilities and consequences

    Following brief discussion of the safety of wind-driven power plants and solar power plants, some aspects of the safety of fast breeder and thermonuclear power plants are presented. It is pointed out that no safety evaluation of breeders comparable to the Rasmussen investigation has been carried out and that discussion of the safety aspects of thermonuclear power is only just begun. Finally, as an illustration of the varying interpretations of risk and safety analyses, four examples are given of predicted probabilities and consequences in Copenhagen of the maximum credible accident at the Barsebaeck plant, under the most unfavourable meterological conditions. These are made by the Environment Commission, Risoe Research Establishment, REO (a pro-nuclear group) and OOA (an anti-nuclear group), and vary by a factor of over 1000. (JIW)

  2. The Fukushima accident

    The accident happened on March 11, 2011 in the nuclear reactors at the Fukushima plant, Japan, is described. The reactors of the Fukushima plant have been power reactors. The electrical energy is produced by use of the heat released in the fission. Nuclear reactors were affected after of the power outage as a result of the earthquake and the tsunami, and this has kept in operation the refrigeration systems. The japanese reactors have been fission reactors and have used uranium 235 or plutonium 239 as fissionable material. The nuclear reactions of fission are explained. The control of the nuclear reactions at Fukushima was complicated by the decreased of the neutrons absorption and has produced more reactions, generating great amounts of heat. The steam contaminated with the products of fission is produced by to cool the reactor with water. The fissionable material released is dragged until the atmosphere. Radioactive contamination at sites near the reactor was covered in a zone of exclusion with a radius of 30 km. The effects of radioactive contamination in the zone of exclusion are mentioned. The radioactive material from Japan has traveled with the wind in direction toward the north pole. The radioactive cloud has continued until to reach the north Africa and south of Europe. The cloud has approximated to Costa Rica, but the activity of the material found has been less of 0,01 Bq/m3. The Centro de Investigacion en Ciencias Atomicas, Nucleares y Moleculares (Cicanum) has initiated the collection of soil samples, water and earth products to detect part of the radioactive material from the cloud. The Cicanum has had modern equipments to quantify the specific concentrations of radioactive isotope, alpha emitters, beta and gamma, in food, water and milk. The Cicanum has maintained the radiological surveillance of foods after the Chernobyl accident

  3. The Chernobyl accident — an epidemiological perspective

    Cardis, E; Hatch, M.

    2011-01-01

    Twenty-five years have passed since radioactive releases from the Chernobyl nuclear accident led to exposure of millions of people in Europe. Studies of affected populations have provided important new data on the links between radiation and cancer – particularly the risk of thyroid tumours from exposure to iodine isotopes - that are important not only for a fuller scientific understanding of radiation effects, but also for radiation protection.

  4. Direction Committee for the management of the post-accident phase of a nuclear accident or of a radiological event (CODIRPA). Work group 'Hypotheses'. Contextual data and hypotheses to perform predictive assessments of radiological and dose consequences at the beginning of a post-accidental transition phase. 2007-2009 work report

    This report first describes how to examine the various exposure ways of a person present on a contaminated territory and formulates hypotheses for the calculation of radioactive doses received by ingestion of contaminated food products, by external irradiation, or by involuntary inhalation of radioactive particles. It identifies factors which may influence the contamination of food products, and gives recommendations for the predictive calculation of their contamination during the first month following the accident. It indicates available methods for the predictive assessment of radioactive deposits at the beginning of the transition phase. It proposes an expertise method to assess the post-accident consequences

  5. Severe Accident Management System On-line Network SAMSON

    SAMSON is a computational tool used by accident managers in the Technical Support Centers (TSC) and Emergency Operations Facilities (EOF) in the event of a nuclear power plant accident. SAMSON examines over 150 status points monitored by nuclear power plant process computers during a severe accident and makes predictions about when core damage, support plate failure, and reactor vessel failure will occur. These predictions are based on the current state of the plant assuming that all safety equipment not already operating will fail. SAMSON uses expert systems, as well as neural networks trained with the back propagation learning algorithms to make predictions. Training on data from an accident analysis code (MAAP - Modular Accident Analysis Program) allows SAMSON to associate different states in the plant with different times to critical failures. The accidents currently recognized by SAMSON include steam generator tube ruptures (SGTRs), with breaks ranging from one tube to eight tubes, and loss of coolant accidents (LOCAs), with breaks ranging from 0.0014 square feet (1.30 cm2) in size to breaks 3.0 square feet in size (2800 cm2). (author)

  6. ROAD TRANSPORT ACCIDENTS IN NIGERIA AND THE ROLE

    Olasunkanmi Oriola AKINYEMI

    2016-06-01

    Full Text Available Analysis of road traffic accidents revealed that most accidents are as a result of drivers’ errors. Over the years, active safety systems (ASS were devised in vehicle to reduce the high level of road accidents, caused by human errors, leading to death and injuries.This study however evaluated the impacts of ASS inclusions into vehicles in Nigeria road transportation network. The objectives was to measure how ASS contributed to making driving safer and enhanced transport safety. Road accident data were collected, for a period of eleven years, from Lagos State Ministry of Economic Planning and Budget, Central Office of Statistics. Quantitative analysis of the retrospective accident was conducted by computing the proportion of yearly number of vehicles involved in road accident to the total number of vehicles for each year. Results of the analysis showed that the proportion of vehicles involved in road accidents decreased from 16 in 1996 to 0.89 in 2006, the injured persons reduced from 15.58 in 1998 to 0.3 in 2006 and the death rate diminished from 4.45 in 1998 to 0.1 in 2006. These represented 94.4%, 95% and 95% improvement respectively on road traffic safety. It can therefore be concluded that the inclusions of ASS into design of modern vehicles had improved road safety in Nigeria automotive industry.

  7. Unconventional sources of plant information for accident management

    Oehlberg, R.; Machiels, A.; Chao, J.; Weiss, J. (Electric Power Research Inst., Palo Alto, CA (United States)); True, D.; James, R. (ERIN Engineering and Research, Walnut Creek, CA (United States))

    1992-01-01

    One phase of accident management covers the actions taken during the course of an accident by the plant operating and technical staff to prevent or minimize off-site radiation releases, gain control, and return the plant to a safe state. Inherent in accomplishing these goals is obtaining a clear picture of the nature of the accident and plant status. Development of a consistent and coherent understanding of the accident and plant status requires plant staff to evaluate and interpret data from a wide range of sources. Plant information during an accident can be obtained from the following sources: (1) plant instrumentation, including Regulatory Guide 1.97 instrumentation; and (2) information sources identified in abnormal operations or emergency operations procedures. Probabilistic risk analyses have shown that events involving the loss of key electrical support systems can be significant contributors to core damage. Such events could jeopardize or degrade instrument availability. Plant-specific accident procedures and interpretation of instruments intended for design-basis events may not be applicable in severe accidents. Information sources such as other nuclear steam supply systems (NSSSs) and balance-of-plant (BOP) instrumentation may be available.

  8. Imperfect conformation of experimental and epidemiological data for frequency of RET/РТС gene rearrangements in papillary thyroid carcinoma for the Chernobyl accident

    Ushenkova L.N.

    2013-12-01

    Full Text Available In an overview and analytical study of the epidemiological data on the frequency of RET/РТС gene rearrangements in sporadic and radiogenic (patients after radiotherapy, residents of contaminated after the Chernobyl disaster areas, victims after the atomic bombings, etc. carcinomas of the thyroid gland were examined. In general, the observed epidemiological laws were confirmed in radiobiology experiments by irradiation of different cultures of thyroid cells and ex vivo with the exception of Chernobyl cohorts. Induction of RET/РТС gene rearrangements by 131l exposure in children carcinomas of Chernobyl residents in mice did not observe too. It is concluded that the situation with the frequency of RET/РТС rearrangements in thyroid carcinoma in Chernobyl cohorts once again confirms the multifactorial nature of the induction and development of these tumors with a contribution of radiation and non-radiation factors (iodine deficiency and different stresses.

  9. Nuclear accidents on policy: Notes on public perception

    Richter, Felix; Steenbeck, Malte; Wilhelm, Markus

    2012-01-01

    Nuclear energy is controversially discussed in many countries. Major nuclear accidents as recently in Fukushima set nuclear power plant security on top of the public agenda and increase pressure on policy makers to provide adequate reactions. Using data of the German Socio-economic Panel we analyze the effects of the accident in Fukushima and the following resolution on a nuclear phase-out plan by the German federal government on subjective perceptions using ordinary least squares and ordered...

  10. Nuclear Accidents and Policy: Notes on Public Perception

    Richter, Felix; Steenbeck, Malte; Wilhelm, Markus

    2013-01-01

    Major nuclear accidents as recently in Fukushima set nuclear power plant security at the top of the public agenda. Using data of the German Socio-Economic Panel we analyze the effects of the Fukushima accident and a subsequent government decision on nuclear power phase-out on several measures of subjective perception in Germany. In the light of current political debates about the strategic orientation of this energy turnaround, such an analysis is of particular interest since non-pecuniary ga...

  11. Measuring the Impacts of Nuclear Accidents on Energy Policy

    Zsuzsanna Csereklyei

    2013-01-01

    This paper examines the history of nuclear energy, safety developments of reactors and nuclear energy policy from the 1950s on. I investigate the effects of nuclear accidents on energy policy with the help of a panel dataset of 31 countries from 1965-2009, using annual data about the capacity of reactors under construction, primary energy consumption, as well as three nuclear accidents scaled INES five or higher by the International Atomic Energy Agency. After determining the extent of the ac...

  12. Epidemiological profile of patients with cerebral vascular accident

    Carolline Paulo Neto da Cunha Lima, Marta Miriam Lopes Costa, Maria Julia Guimarães Oliveira Soares

    2009-01-01

    Objectives: to show the profile epidemiological of patients with cerebral vascular accident in a public hospital from João Pessoa city, Paraíba, Brazil; to investigate the social demographic profile; to identify the risk factors, symptoms and sequels of the cerebral vascular accident. Methods: this is about a descriptive and exploratory study, from quantitative approach; the population was configured by sixty handbooks. Data collect was performed with a form from March to April 2007, and then...

  13. Researching Effects of Drivers Features on Traffic Accidents: Kocaeli Model

    UÇKUN, Ceylan Gazi; ÇELİKKOL, Ethem Soner; TEKİN, Vasfı Nadir; ÇELİKKOL, Şimal

    2013-01-01

    In addition to environmental conditions, weather conditions and density, situations related to drivers are more effective on traffic accidents, according to available data. Regarding occurrence of traffic accidents, it is observed that point of view of drivers towards traffic rules and drivers’ compliance with these rules is not parallel. It is important to research the reasons that cause this situation. A normal person’s mental state does not change without any reason at traffic. It is clear...

  14. RESEARCHING EFFECTS OF DRIVERS FEATURES ON TRAFFIC ACCIDENTS: KOCAELİ MODEL

    CEYLAN GAZI UÇKUN; ETHEM SONER ÇELİKKOL; VASFI NADIR TEKİN; ŞIMAL ÇELİKKOL

    2013-01-01

    In addition to environmental conditions, weather conditions and density, situations related to drivers are more effective on traffic accidents, according to available data.Regarding occurrence of traffic accidents, it is observed that point of view of drivers towards traffic rules and drivers’ compliance with these rules is not parallel. It is important to research the reasons that cause this situation. A normal person’s mental state does not change without any reason at traffic. It is clear ...

  15. Risk and resilience factors of persons exposed to accidents

    HERTA, DANA – CRISTINA; BRÎNDAS, PAULA; TRIFU, RALUCA; COZMAN, DOINA

    2016-01-01

    Background and aims Resilience encompasses factors promoting effective functioning in the context of adversity. Data regarding resilience in the wake of accidental trauma is still scarce. The aim of the current study is to comparatively assess adaptive, life – promoting factors in persons exposed to motor vehicle accidents (MVA) vs. persons exposed to other types of accidents, and to identify psychological factors of resilience and vulnerability in this context of trauma exposure. Methods We ...

  16. Industrial accidents triggered by lightning

    Research highlights: → Lightning impact caused relevant industrial accidents. → Atmospheric storage tanks are the equipment item more susceptible to lightning damage. → Specific damage and release modes may be identified for lightning damage. Specific event trees should be adopted for the identification of post-release final scenarios characterizing lightning-induced major accidents. - Abstract: 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.

  17. International aspects of nuclear accidents

    The accident at Chernobyl revealed that there were shortcomings and gaps in the existing international mechanisms and brought home to governments the need for stronger measures to provide better protection against the risks of severe accidents. The main thrust of international co-operation with regard to nuclear safety issues is aimed at achieving a uniformly high level of safety in nuclear power plants through continuous exchanges of research findings and feedback from reactor operating experience. The second type of problem posed in the event of an accident resulting in radioactive contamination of several countries relates to the obligation to notify details of the circumstances and nature of the accident speedily so that the countries affected can take appropriate protective measures and, if necessary, organize mutual assistance. Giving the public accurate information is also an important aspect of managing an emergency situation arising from a severe accident. Finally, the confusion resulting from the unwarranted variety of protective measures implemented after the Chernobyl accident has highlighted the need for international harmonization of the principles and scientific criteria applicable to the protection of the public in the event of an accident and for a more consistent approach to emergency plans. The international conventions on third party liability in the nuclear energy sector (Paris/Brussels Conventions and the Vienna Convention) provide for compensation for damage caused by nuclear accidents in accordance with the rules and jurisdiction that they lay down. These provisions impose obligations on the operator responsible for an accident, and the State where the nuclear facility is located, towards the victims of damage caused in another country

  18. Severe accident research and management in Nordic Countries - A status report

    The report describes the status of severe accident research and accident management development in Finland, Sweden, Norway and Denmark. The emphasis is on severe accident phenomena and issues of special importance for the severe accident management strategies implemented in Sweden and in Finland. The main objective of the research has been to verify the protection provided by the accident mitigation measures and to reduce the uncertainties in risk dominant accident phenomena. Another objective has been to support validation and improvements of accident management strategies and procedures as well as to contribute to the development of level 2 PSA, computerised operator aids for accident management and certain aspects of emergency preparedness. Severe accident research addresses both the in-vessel and the ex-vessel accident progression phenomena and issues. Even though there are differences between Sweden and Finland as to the scope and content of the research programs, the focus of the research in both countries is on in-vessel coolability, integrity of the reactor vessel lower head and core melt behaviour in the containment, in particular the issues of core debris coolability and steam explosions. Notwithstanding that our understanding of these issues has significantly improved, and that experimental data base has been largely expanded, there are still important uncertainties which motivate continued research. Other important areas are thermal-hydraulic phenomena during reflooding of an overheated partially degraded core, fission product chemistry, in particular formation of organic iodine, and hydrogen transport and combustion phenomena. The development of severe accident management has embraced, among other things, improvements of accident mitigating procedures and strategies, further work at IFE Halden on Computerised Accident Management Support (CAMS) system, as well as plant modifications, including new instrumentation. Recent efforts in Sweden in this area

  19. Severe accident research and management in Nordic Countries - A status report

    Frid, W. [Swedish Nuclear Power Inspectorate, SKI (Sweden)] (ed.)

    2002-01-01

    The report describes the status of severe accident research and accident management development in Finland, Sweden, Norway and Denmark. The emphasis is on severe accident phenomena and issues of special importance for the severe accident management strategies implemented in Sweden and in Finland. The main objective of the research has been to verify the protection provided by the accident mitigation measures and to reduce the uncertainties in risk dominant accident phenomena. Another objective has been to support validation and improvements of accident management strategies and procedures as well as to contribute to the development of level 2 PSA, computerised operator aids for accident management and certain aspects of emergency preparedness. Severe accident research addresses both the in-vessel and the ex-vessel accident progression phenomena and issues. Even though there are differences between Sweden and Finland as to the scope and content of the research programs, the focus of the research in both countries is on in-vessel coolability, integrity of the reactor vessel lower head and core melt behaviour in the containment, in particular the issues of core debris coolability and steam explosions. Notwithstanding that our understanding of these issues has significantly improved, and that experimental data base has been largely expanded, there are still important uncertainties which motivate continued research. Other important areas are thermal-hydraulic phenomena during reflooding of an overheated partially degraded core, fission product chemistry, in particular formation of organic iodine, and hydrogen transport and combustion phenomena. The development of severe accident management has embraced, among other things, improvements of accident mitigating procedures and strategies, further work at IFE Halden on Computerised Accident Management Support (CAMS) system, as well as plant modifications, including new instrumentation. Recent efforts in Sweden in this area

  20. A study on the late core melt progression in pressurized water reactor severe accidents

    Park, Jae Hong; Jeun Gyoo Dong; Bang, Kwang Hyun; Park, Seh In; Lim, Jae Hyuck; Park, Seong Yong [Hanyang Univ., Seoul (Korea, Republic of); Back, Hyung Hmm [Korea Maritime Univ., Busan (Korea, Republic of)

    1998-03-15

    After TMI-2 accidents, it has been paid much attention to severe accidents beyond the design basis accidents and the research on the progress of severe accidents and mitigation and the closure of severe accidents has been actively performed. In particular, a great deal of uncertainties yet exist in the phase of late core melt progression and thus the research on this phase of severe accident progress has a key role in obtaining in severe accident mitigation and nuclear reactor safety. In the present study, physics of late core melt progression, experimental data and the major phenomenological models of computer codes are reviewed and a direction of reducing the uncertainties in the late core melt progression os proposed.

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

    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.

  2. [Prevention of bicycle accidents].

    Zwipp, H; Barthel, P; Bönninger, J; Bürkle, H; Hagemeister, C; Hannawald, L; Huhn, R; Kühn, M; Liers, H; Maier, R; Otte, D; Prokop, G; Seeck, A; Sturm, J; Unger, T

    2015-04-01

    For a very precise analysis of all injured bicyclists in Germany it would be important to have definitions for "severely injured", "seriously injured" and "critically injured". By this, e.g., two-thirds of surgically treated bicyclists who are not registered by the police could become available for a general analysis. Elderly bicyclists (> 60 years) are a minority (10 %) but represent a majority (50 %) of all fatalities. They profit most by wearing a helmet and would be less injured by using special bicycle bags, switching on their hearing aids and following all traffic rules. E-bikes are used more and more (145 % more in 2012 vs. 2011) with 600,000 at the end of 2011 and are increasingly involved in accidents but still have a lack of legislation. So even for pedelecs 45 with 500 W and a possible speed of 45 km/h there is still no legislative demand for the use of a protecting helmet. 96 % of all injured cyclists in Germany had more than 0.5 ‰ alcohol in their blood, 86 % more than 1.1 ‰ and 59 % more than 1.7 ‰. Fatalities are seen in 24.2 % of cases without any collision partner. Therefore the ADFC calls for a limit of 1.1 ‰. Some virtual studies conclude that integrated sensors in bicycle helmets which would interact with sensors in cars could prevent collisions or reduce the severity of injury by stopping the cars automatically. Integrated sensors in cars with opening angles of 180° enable about 93 % of all bicyclists to be detected leading to a high rate of injury avoidance and/or mitigation. Hanging lamps reduce with 35 % significantly bicycle accidents for children, traffic education for children and special trainings for elderly bicyclists are also recommended as prevention tools. As long as helmet use for bicyclists in Germany rates only 9 % on average and legislative orders for using a helmet will not be in force in the near future, coming up campaigns seem to be necessary to be promoted by the Deutscher

  3. Third IAEA nuclear accident intercomparison experiment

    The purpose of this report is to present the results of the International Atomic Energy Agency intercomparison experiments held at the 'Boris Kidric' Institute, Vinca, in May 1973. The experiments are parts of a multilaboratory intercomparison programme sponsored by the IAEA for the evaluation of nuclear accident dosimetry systems and eventually recommendation of dosimetry systems that will provide adequate informations in the event of a criticality accident. The previous two studies were held at the Valduc Centre near Dijon (France) in June 1970 and at the ORNL in Oak Ridge (USA), in May 1971. Parts of the intercomparison studies were coordination meetings. The topics and conclusions of the Third coordination meeting are given in the Chairman's Report of F.F. Haywood. This paper will deal, therefore, only with data concerning the Third intercomparison experiments in which the RB reactor at Vinca was used as a source of mixed radiation. (author)

  4. Method for consequence calculations for severe accidents

    This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Ringhals reactor No 3/4. The accident sequence chosen for the calcualtions was a release caused by total power failure. The calculations were made by means of the PLUCON4 code. A decontamination factor of 500 is used to account for the scrubber effect. Meteorological data for two years from the Ringhals meteorological tower were analysed to find representative weather situations. As typical weather, Pasquill D, was chosen with a wind speed of 10 m/s, and as extreme weather, Pasquill E, with a wind speed of 2 m/s. 19 refs. (author)

  5. Characterization of a nuclear accident dosimeter

    The 23rd nuclear accident dosimetry intercomparison was held during the week of June 12--16, 1995 at Los Alamos National Laboratory. This report presents the results of this event, referred to as NAD 23, as related to the performance of Sandia National Laboratories (SNL) personal nuclear accident dosimeter (PNAD). Two separate critical assemblies, SHEBA and Godiva, were used to generate seven separate neutron spectra for use in dose comparisons. SNL's PNAD measured absorbed doses that were within +16 to +26% of the reference doses. In addition, a preliminary investigation was undertaken to determine the feasibility of using the data obtained from an irradiated PNAD to correct for body orientation. This portion of the experiment was performed with a TRIGA reactor at the Nuclear Science Center at Texas A and M University

  6. Information from water ingress accident on AVR

    An ingress of water occurred in the AVR reactor in May 1978. The reactor had been shut down and cooled by forced circulation; liquid water entered the primary circuit from a leak in the superheater, evaporated in passing through the core and condensed in the lower part of the primary circuit and in the ball handling region. Various fission product activities were measured in the water by the AVR scientists and a study was started to identify the sources of these activities and to derive information which could be used in the analyses of water ingress accidents in general. The first part of this study is reported in this note. The possible source terms are considered separately and estimates of their contributions are made, supported by data from previous laboratory experiments where possible. The main conclusion is that valuable information has been derived concerning the desorption of iodine, cesium and strontium from dust and primary circuit surfaces. A minimum programme of measurements and analytical work necessary to increase this information has been identified. An example of the application of the data to a particular accident to a power reactor is given to indicate how the information can affect the calculation of consequences. For the second part of the study, better estimates of the fission product concentrations in the primary circuit prior to the accident and various measurements when the reactor is operating again are required. (orig.)

  7. Chemical Stockpile Disposal Program rapid accident assessment

    Chester, C.V.

    1990-08-01

    This report develops a scheme for the rapid assessment of a release of toxic chemicals resulting from an accident in one of the most chemical weapon demilitarization plants or storage areas. The system uses such inputs as chemical and pressure sensors monitoring the plant and reports of accidents radioed to the Emergency Operations Center by work parties or monitoring personnel. A size of release can be estimated from previous calculations done in the risk analysis, from back calculation from an open-air chemical sensor measurement, or from an estimated percentage of the inventory of agent at the location of the release. Potential consequences of the estimated release are calculated from real-time meteorological data, surrounding population data, and properties of the agent. In addition to the estimated casualties, area coverage and no-death contours vs time would be calculated. Accidents are assigned to one of four categories: community emergencies, which are involve a threat to off-site personnel; on-post emergencies, which involve a threat only to on-site personnel; advisory, which involves a potential for threat to on-site personnel; and chemical occurrence, which can produce an abnormal operating condition for the plant but no immediate threat to on-site personnel. 9 refs., 20 tabs.

  8. Accident response in France

    French PWR power plant design relies basically on a deterministic approach. A probabilistic approach was introduced in France in the early seventies to define safety provisions against external impacts. In 1977 an overall safety objective was issued by the safety authority in terms of an upper probability limit for having unacceptable consequences. Additional measures were taken (the ''H'' operating procedures) to complement the automatic systems normally provided by the initial design, so as to safisfy the safety objective. The TMI-2 accident enhanced the interest in confused situations in which possible multiple equipment failure and/or unappropriate previous actions of the operators impede the implementation of any of the existing event-oriented procedures. In such situations, the objective becomes to avoid core-melt by any means available: this is the goal of the Ul symptom-oriented procedure. Whenever a core-melt occurs, the radioactive releases into the environment must be compatible with the feasibility of the off-site emergency plans; that means that for some hypothetical, but still conceivable scenarios, provisions have to be made to delay and limit the consequences of the loss of the containment: the U2, U4 and U5 ultimate procedures have been elaborated for that purpose. For the case of an emergency, a nationwide organization has been set up to provide the plant operator with a redundant technical expertise, to help him save his plant or mitigate the radiological consequences of a core-melt

  9. A general approach to transform a lake model for one radionuclide (radiocesium) to another (radiostrontium) and critical model tests using data for four Ural lakes contaminated by the fallout from the Kyshtym accident in 1957

    This paper presents results of a model test carried out within the framework of the COMETES project (EU). The aim of the work was to change the structure of the MOIRA lake model for radiocesium so that it can be applied more generally for, in principle, all types of radionuclides and heavy metals. This general lake model is used within the MOIRA decision support system (DSS; MOIRA and COMETES are acronyms for EU-projects). The model is based on a set of differential equations and a specific modelling structure. It incorporates all important fluxes to, from and within lakes in a general manner. Yet the model is driven by a minimum of variables accessible from standard maps and monitoring programs. The model can be separated into two parts, a general part with equations applicable for all types of water pollutants and a substance-specific part. This model has previously been validated for 137Cs from many lakes covering a wide domain and yielded excellent predictive power. The alterations discussed in this work are meant to be general and radiostrontium is used as a typical element. Radiostrontium is known to be more mobile than radiocesium and all abiotic parts of the model handling fixation and mobility have been altered. The new model for 90Sr has been critically tested using data from four lakes heavily contaminated with 90Sr from the Kyshtym accident in the Southern Urals, Russia, using empirical data from a period from 1958 to 1995 for 90Sr in fish (here goldfish), water and sediments

  10. Preparedness against nuclear power accidents

    This booklet contains information about the organization against nuclear power accidents, which exist in the four Swedish counties with nuclear power plants. It is aimed at classes 7-9 of the Swedish schools. (L.E.)

  11. Trauma in the elderly caused by traffic accident: integrative review

    Ana Maria Ribeiro dos Santos

    2015-02-01

    Full Text Available OBJECTIVE To describe the scientific knowledge produced about trauma in the elderly caused by traffic accidents in healthcare area studies. METHODS Integrative review of studies from 2003 to 2013 searched in LILACS, SciELO, PubMed and CINHAL databases. We used combination of the descriptors injuries, wounds and accidents, in English, Portuguese and Spanish languages. RESULTS 32 studies were selected. In the thematic analysis, three categories emerged: epidemiological data from traffic accidents involving elderly; traffic accidents with elderly pedestrians; and trauma care in the elderly. We observed increased incidence of trauma in most countries and pedestrians represented a large part of the victims. Among these, the elderly are the most vulnerable group. CONCLUSION Studies showed that trauma care in the elderly need protocols and professionals with training in gerontology specialized in trauma care services.

  12. Fatal motorcycle accidents in the county of Funen (Denmark)

    Larsen, C F; Hardt-Madsen, M

    1988-01-01

    A study of motorcycle fatalities in the period 1977-1983 in the county of Funen, Denmark was compared with an analysis of data obtained from the Accident Register at the Odense University Hospital. Among the operators killed one fifth were illegally operating the motorcycle. A remarkable...... statistical difference in distribution of accidents involved motorcycles and the total distribution of motorcycles in the county was reported, thus finding an over-representation of heavy motorcycles in the present study. No important differences were found in the distribution of type of accidents compared to...... other studies. In the present study all but one victim were tested for blood-alcohol concentration (BAC). The results differ from previous studies in as much as 50% of the killed operators of an accident involving motorcycles had a BAC above 0.08%. The reported distribution by age, licensing experience...

  13. Structural evaluation of electrosleeved tubes under severe accident transients

    A flow stress model was developed for predicting failure of Electrosleeved PWR steam generator tubing under severe accident transients. The Electrosleeve, which is nanocrystalline pure nickel, loses its strength at temperatures greater than 400 C during severe accidents because of grain growth. A grain growth model and the Hall-Petch relationship were used to calculate the loss of flow stress as a function of time and temperature during the accident. Available tensile test data as well as high temperature failure tests on notched Electrosleeved tube specimens were used to derive the basic parameters of the failure model. The model was used to predict the failure temperatures of Electrosleeved tubes with axial cracks in the parent tube during postulated severe accident transients

  14. Sensitivity analysis in severe accidents semi-mechanistic modeling

    A sensitivity analysis to determine the most influent phenomena in the core melt progression to be considered in a semi-mechanistic modeling have been performed in the present work. The semi-mechanistic program MARCH3 and the TMI-2 plant parameters were used in the TMI-2 severe accident. The sensitivity analysis was performed with the comparison of the results obtained by the program with the plant data recorded during the accident. The results enabled us to verify that although many phenomena are present in the accident, the modelling of the most important ones was enough to reproduce, at least in a qualitative way, the accident progression. This fact reflects the importance of the sensitivity analysis to select the most influent phenomena in a core melting process. (author). 48 refs., 28 figs., 6 tabs

  15. Psychic pathology of anthropogenic accidents at risk enterprises

    The literary data on the clinic and pathogenesis distinctions of traumatic and posttraumatic stress following the accidents are analyzed. The inner contradictory character of the Chernobyl NPP operators reaction to psychodraumatic situation is revealed. A number of concepts liable to discussion is given: inner contradiction of the reactions to traumatic stress on account of accidents at risk cuterprises puts forward the way for psychology evolution in process, besides, posttraumatic stress may be considered as one of the stages of such evolution; the misuse of spirits by the persons with traumatic stress appeared on account of accidents at risk enterprises puts forward the way for the subsequent evolution towards psychic degeneration; the prevailing effect of the reality denial among the personnel of the risk enterprises may form a muthcreative attitude to technical sphere and play a certain role in the emergence of anthropogenic accidents at these enterprises. 22 refs

  16. The management of radioactive waste from accidents

    Two accident case histories are reviewed - the Three Mile Island (TMI-2) reactor accident in 1979 and the Seveso accident in 1976. The status of the decontamination and radioactive waste management operations at TMI-2 as at 1986 is presented. 1986 estimates of reactor accident and recovery costs are given. 12 refs., 8 tabs

  17. 29 CFR 1960.29 - Accident investigation.

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Accident investigation. 1960.29 Section 1960.29 Labor... MATTERS Inspection and Abatement § 1960.29 Accident investigation. (a) While all accidents should be investigated, including accidents involving property damage only, the extent of such investigation shall...

  18. 49 CFR 195.54 - Accident reports.

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Accident reports. 195.54 Section 195.54... PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.54 Accident reports. (a) Each operator that experiences an accident that is required to be reported under § 195.50 shall as soon...

  19. 49 CFR 801.32 - Accident reports.

    2010-10-01

    ... 49 Transportation 7 2010-10-01 2010-10-01 false Accident reports. 801.32 Section 801.32... PUBLIC AVAILABILITY OF INFORMATION Accident Investigation Records § 801.32 Accident reports. (a) The NTSB....S. civil transportation accidents, in accordance with 49 U.S.C. 1131(e). (b) These reports may...

  20. The measurement of accident-proneness

    As, Sicco van

    2001-01-01

    This paper deals with the measurement of accident-proneness. Accidents seem easy to observe, however accident-proneness is difficult to measure. In this paper I first define the concept of accident-proneness, and I develop an instrument to measure it. The research is mainly executed within chemical

  1. 49 CFR 230.22 - Accident reports.

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Accident reports. 230.22 Section 230.22... Requirements § 230.22 Accident reports. In the case of an accident due to failure, from any cause, of a steam... persons, the railroad on whose line the accident occurred shall immediately make a telephone report of...

  2. 49 CFR 845.40 - Accident report.

    2010-10-01

    ... 49 Transportation 7 2010-10-01 2010-10-01 false Accident report. 845.40 Section 845.40... RULES OF PRACTICE IN TRANSPORTATION; ACCIDENT/INCIDENT HEARINGS AND REPORTS Board Reports § 845.40 Accident report. (a) The Board will issue a detailed narrative accident report in connection with...

  3. Evaluation Metrics Applied to Accident Tolerant Fuels

    Shannon M. Bragg-Sitton; Jon Carmack; Frank Goldner

    2014-10-01

    The safe, reliable, and economic operation of the nation’s nuclear power reactor fleet has always been a top priority for the United States’ nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry’s success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. One of the current missions of the U.S. Department of Energy’s (DOE) Office of Nuclear Energy (NE) is to develop nuclear fuels and claddings with enhanced accident tolerance for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+). Accident tolerance became a focus within advanced LWR research upon direction from Congress following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex. The overall goal of ATF development is to identify alternative fuel system technologies to further enhance the safety, competitiveness and economics of commercial nuclear power. Enhanced accident tolerant fuels would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The U.S. DOE is supporting multiple teams to investigate a number of technologies that may improve fuel system response and behavior in accident conditions, with team leadership provided by DOE national laboratories, universities, and the nuclear industry. Concepts under consideration offer both evolutionary and revolutionary changes to the current nuclear fuel system. Mature concepts will be tested in the Advanced Test Reactor at Idaho National Laboratory beginning in Summer 2014 with additional concepts being

  4. Evaluation Metrics Applied to Accident Tolerant Fuels

    The safe, reliable, and economic operation of the nation’s nuclear power reactor fleet has always been a top priority for the United States’ nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry’s success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. One of the current missions of the US. Department of Energy’s (DOE) Office of Nuclear Energy (NE) is to develop nuclear fuels and claddings with enhanced accident tolerance characteristics for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+). LWR fuel with accident tolerant characteristics became a focus within advanced LWR research following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex, and upon receiving direction from Congress. The overall goal of ATF development is to identify alternative fuel system technologies to further enhance the safety, competitiveness and economics of commercial nuclear power. Enhanced accident tolerant fuels would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The US. DOE is supporting multiple teams to investigate a number of technologies that may improve fuel system response and behaviour in accident conditions, with team leadership provided by DOE national laboratories, universities, and the nuclear industry. Concepts under consideration offer both evolutionary and revolutionary changes to the current nuclear fuel system. Mature concepts will be tested in the Advanced Test Reactor at Idaho National

  5. Nuclear laws and radiologic accidents

    Some aspects of the nuclear activities in Brazil, specially concerning the Goiania s accident are demonstrated using concepts from environmental and nuclear law. Nuclear and environmental competence, the impossibility of the states of making regional laws, as the lack of regulation about the nuclear waste, are discussed. The situation of Goiania when the accident happened, the present situation of the victims and the nuclear waste provisionally stored in Abadia de Goias is reported

  6. Iodine prophylaxis following nuclear accidents

    These proceedings of the Joint WHO/CEC workshop on iodine prophylaxis following nuclear accidents are presented under the following headings: normal thyroid function and the response to iodine, theoretical basis for stable iodine prophylaxis, risks and benefits of stable iodine prophylaxis, indications for the use of stable iodine, recommendations and rationale for the use of stable iodine prophylaxis in event of future accidents. (UK)

  7. Nuclear accident countermeasures: iodine prophylaxis

    In January 1989 the Department of Health convened a working group to consider and advise on the indications for the use of stable iodine, in the United Kingdom, in the event of nuclear accident. In formulating its advice the working group was to consider the International Guidelines for Iodine Prophylaxis following Nuclear Accidents, drawn by the World Health Organisation, and their applicability to the UK. This report summarises the findings of the working group and gives its conclusions and recommendations. (author)

  8. Traffic accidents involving fatigue driving and their extent of casualties.

    Zhang, Guangnan; Yau, Kelvin K W; Zhang, Xun; Li, Yanyan

    2016-02-01

    The rapid progress of motorization has increased the number of traffic-related casualties. Although fatigue driving is a major cause of traffic accidents, the public remains not rather aware of its potential harmfulness. Fatigue driving has been termed as a "silent killer." Thus, a thorough study of traffic accidents and the risk factors associated with fatigue-related casualties is of utmost importance. In this study, we analyze traffic accident data for the period 2006-2010 in Guangdong Province, China. The study data were extracted from the traffic accident database of China's Public Security Department. A logistic regression model is used to assess the effect of driver characteristics, type of vehicles, road conditions, and environmental factors on fatigue-related traffic accident occurrence and severity. On the one hand, male drivers, trucks, driving during midnight to dawn, and morning rush hours are identified as risk factors of fatigue-related crashes but do not necessarily result in severe casualties. Driving at night without street-lights contributes to fatigue-related crashes and severe casualties. On the other hand, while factors such as less experienced drivers, unsafe vehicle status, slippery roads, driving at night with street-lights, and weekends do not have significant effect on fatigue-related crashes, yet accidents associated with these factors are likely to have severe casualties. The empirical results of the present study have important policy implications on the reduction of fatigue-related crashes as well as their severity. PMID:26625173

  9. Nuclear fuel cycle facility accident analysis handbook

    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

  10. The vver severe accident management

    The basic approach to the VVER safety management is based on the defence-in-depth principle the main idea of which is the multiplicity of physical barriers on the way of dangerous propagation on the one hand and the diversity of measures to protect each of them on the other hand. The main events of severe accident with loss of core cooling at NPP with WWER can be represented as a sequence of NPP states, in which each subsequent state is more severe than the previous one. The following sequence of states of the accident progression is supposed to be realistic and the most probable: -) loss of efficient core cooling; -) core melting, relocation of the molten core to the lower head and molten pool formation, -) reactor vessel damage, and -) containment damage and fission products release. The objectives of accident management at the design basis stage, the determining factors and appropriate determining parameters of processes are formulated in this paper. The same approach is used for the estimation of processes parameters at beyond design basis accident progression. The accident management goals and the determining factors and parameters are also listed in that case which is characterized by the loss of integrity of the fuel cladding. The accident management goal at the stage of core melt relocation implies the need for an efficient core-catcher

  11. JAERI's activities in JCO accident

    The Japan Atomic Energy Research Institute (JAERI) was actively involved in a variety of technical supports and cooperative activities, such as advice on terminating the criticality condition, contamination checks of the residents and consultation services for the residents, as emergency response actions to the criticality accident at the uranium processing facility operated by the JCO Co. Ltd., which occurred on September 30, 1999. These activities were carried out in collaborative ways by the JAERI staff from the Tokai Research Establishment, Naka Fusion Research Establishment, Oarai Research Establishment, and Headquarter Office in Tokyo. As well, the JAERI was engaged in the post-accident activities such as identification of accident causes, analyses of the criticality accident, and dose assessment of exposed residents, to support the Headquarter for Accident Countermeasures of the Science and Technology Agency (STA), the Accident Investigation Committee and the Health Control Committee of the Nuclear Safety Commission of Japan (NSC). This report compiles the activities, that the JAERI has conducted to date, including the discussions on measures for terminating the criticality condition, evaluation of the fission number, radiation monitoring in the environment, dose assessment, analyses of criticality dynamics. (author)

  12. An analysis of accidents involving towboat-barge combination on selected inland waterways of the United States.

    Gamble, William John

    1980-01-01

    Approved for public release; distribution is unlimited This study uses a statistical analysis approach on a computerized data base to analyze accidents involving towboat-barge combinations on the inland waterways of the United States. The main areas explored are the factors affecting the severity and the frequency of accidents. In addition, multiple regression models are used to predict the severity of towboat accidents from a set of independent accident variables. Conclusions and recom...

  13. Accidents involving motorcyclists and cyclists in the municipality of São Paulo: characterization and trends☆☆☆

    Cintia Leci Rodrigues; Jane de Eston Armond; Carlos Gorios; Patricia Colombo Souza

    2014-01-01

    Objective:To describe the characteristics of motorcycle and bicycle accident victims, according to notifications of suspected and confirmed accidents that have occurred in the municipality of São Paulo.Method:This was a descriptive epidemiological study. It covered all accidents (12,924) that occurred involving motorcycles (11,366) and bicycles (1558) between January 2011 and October 2013. Data in the Health Department's information system for surveillance of violence and accidents (SIVVA) wa...

  14. Radiological accidents: education for prevention and confrontation

    The purpose of this work is to train and inform on radiological accidents as a preventive measure to improve the people life quality. Radiological accidents are part of the events of technological origin which are composed of nuclear and radiological accidents. As a notable figure is determined that there have been 423 radiological accidents from 1944 to 2005 and among the causes prevail industrial accidents, by irradiations, medical accidents and of laboratories, among others. Latin American countries such as Argentina, Brazil, Mexico and Peru are some where most accidents have occurred by radioactivity. The radiological accidents can have sociological, environmental, economic, social and political consequences. In addition, there are scenarios of potential nuclear accidents and in them the potential human consequences. Also, the importance of the organization and planning in a nuclear emergency is highlighted. Finally, the experience that Cuba has lived on the subject of radiological accidents is described

  15. Severe accident analysis using dynamic accident progression event trees

    Hakobyan, Aram P.

    In present, the development and analysis of Accident Progression Event Trees (APETs) are performed in a manner that is computationally time consuming, difficult to reproduce and also can be phenomenologically inconsistent. One of the principal deficiencies lies in the static nature of conventional APETs. In the conventional event tree techniques, the sequence of events is pre-determined in a fixed order based on the expert judgments. The main objective of this PhD dissertation was to develop a software tool (ADAPT) for automated APET generation using the concept of dynamic event trees. As implied by the name, in dynamic event trees the order and timing of events are determined by the progression of the accident. The tool determines the branching times from a severe accident analysis code based on user specified criteria for branching. It assigns user specified probabilities to every branch, tracks the total branch probability, and truncates branches based on the given pruning/truncation rules to avoid an unmanageable number of scenarios. The function of a dynamic APET developed includes prediction of the conditions, timing, and location of containment failure or bypass leading to the release of radioactive material, and calculation of probabilities of those failures. Thus, scenarios that can potentially lead to early containment failure or bypass, such as through accident induced failure of steam generator tubes, are of particular interest. Also, the work is focused on treatment of uncertainties in severe accident phenomena such as creep rupture of major RCS components, hydrogen burn, containment failure, timing of power recovery, etc. Although the ADAPT methodology (Analysis of Dynamic Accident Progression Trees) could be applied to any severe accident analysis code, in this dissertation the approach is demonstrated by applying it to the MELCOR code [1]. A case study is presented involving station blackout with the loss of auxiliary feedwater system for a

  16. Accident Tolerant Fuel Analysis

    Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and

  17. Accident tolerant fuel analysis

    Smith, Curtis [Idaho National Laboratory; Chichester, Heather [Idaho National Laboratory; Johns, Jesse [Texas A& M University; Teague, Melissa [Idaho National Laboratory; Tonks, Michael Idaho National Laboratory; Youngblood, Robert [Idaho National Laboratory

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant

  18. Containment in-situ post accident sampling and emission monitoring for design basis and severe accidents

    In order to reduce the residual risk in case of severe accident the German Reactor Safety Commission imposed additional recommendations that provision are made for: Post Accident Sampling System (PASS ) for the confinement atmosphere for obtaining of information on the condition of the core and potential hazards to the environment; Emission monitoring for containment venting. In-situ PASS provides the following information: activity concentration of radioactive aerosols, gaseous iodine and noble gases and composition of gases present in the containment atmosphere (CO, CO2, O2 etc.).The emission monitoring system has the task of monitoring radioactive materials discharged during DBA or severe accident if filtered confinement venting will be performed. The data obtained from the monitoring serves as a base for the implementing of the emergency response actions. The system is designed for the maximum activity concentration at the time of early containment venting, commenced in the event of a core melt accident - 1011 Bq/m3 aerosol bound radionuclides; 5.1011 Bq/m3 gaseous iodine isotopes and 2.1015 Bq/m3 radioactive noble gases

  19. Organizational culture during the accident response process

    A large volume of literature hypothesizes a direct relationship between organizational culture and organizational effectiveness. Culture data have been collected by the authors and others at nuclear power plants (NPPs) and other organizations that demand high reliability. In this paper, the literature and data are used to explore a critical dimension of the accident response process in an NPP: the transition from an anticipatory strategy to an ad hoc strategy. In particular, the effect of organizational culture on the implementation of each of these strategies is examined

  20. Nuclear power plant Severe Accident Research Plan

    The Severe Accident Research Plan (SARP) will provide technical information necessary to support regulatory decisions in the severe accident area for existing or planned nuclear power plants, and covers research for the time period of January 1982 through January 1986. SARP will develop generic bases to determine how safe the plants are and where and how their level of safety ought to be improved. The analysis to address these issues will be performed using improved probabilistic risk assessment methodology, as benchmarked to more exact data and analysis. There are thirteen program elements in the plan and the work is phased in two parts, with the first phase being completed in early 1984, at which time an assessment will be made whether or not any major changes will be recommended to the Commission for operating plants to handle severe accidents. Additionally at this time, all of the thirteen program elements in Chapter 5 will be reviewed and assessed in terms of how much additional work is necessary and where major impacts in probabilistic risk assessment might be achieved. Confirmatory research will be carried out in phase II to provide additional assurance on the appropriateness of phase I decisions. Most of this work will be concluded by early 1986

  1. Factors Associated with Infant Feeding Methods after the Nuclear Power Plant Accident in Fukushima: Data from the Pregnancy and Birth Survey for the Fiscal Year 2011 Fukushima Health Management Survey.

    Ishii, Kayoko; Goto, Aya; Ota, Misao; Yasumura, Seiji; Abe, Masafumi; Fujimori, Keiya

    2016-08-01

    Objectives The objective of this study was to assess the frequency of and factors associated with infant feeding methods after the Fukushima nuclear power plant accident using data from the Fukushima Health Management Survey. Methods We conducted an anonymous self-administered questionnaire survey of 16,001 women who gave birth around the time of the Great East Japan Earthquake and registered their pregnancies at Fukushima Prefecture municipal offices between August 1, 2010 and July 31, 2011. The responses of 8366 women were analyzed. Chi square tests and multiple logistic regression analysis were used to compare various factors between women who had formula-fed their children because of concern regarding radioactive contamination or other reasons and those who had breastfed exclusively. Results The percentage of women who had breastfed exclusively was 30.9 %. The percentage of women who had both breastfed and formula-fed or formula-fed exclusively was 69.1 %, of which 20.3 % formula-fed because of concern regarding radioactive contamination of breast milk. The use of formula feeding because of concern about radioactive contamination was significantly higher in women who had resided within the evacuation area and those whose regular antenatal care had been interrupted. The use of formula feeding for other reasons was significantly higher in women who had resided within the evacuation area and lower for those who had willingly switched to another medical institution. Conclusions for Practice Our results suggest the importance of providing breastfeeding support to women who are forced to evacuate or whose antenatal care is interrupted after a disaster. PMID:27028325

  2. Occupational accidents with piercing and cutting instruments in hospital nurses

    Maria Helena Palucci Marziale

    2004-02-01

    Full Text Available Goals: To identify factors associated with occupational accidents caused by piercing and cutting instruments and to identify the consequences of these accidents.Methods: Descriptive field research. Data were obtained through semi-structured interviews with nurses who suffered accidents during one year in four hospitals at São Paulo State - Brazil. Results: factors associated with accidents were: work overload, poor quality material, inadequate disposal materials, professional negligence, clients’ aggressiveness, lack of attention and use of unsheathed needles. The accidents caused financial damages to the institutions as well as emotional and physical impairments to workers. Conclusions: There are several factors associated with accidents with piercing and cutting instruments. Therefore, preventive measures must be implemented according to the peculiarities of each work environment. Better care should be taken with the preparation of the professionals as well as with the information on risks from exposure to body/blood fluids they are given. A specific legislation is needed in our country in order to minimize this problem.

  3. An approach to accidents modeling based on compounds road environments.

    Fernandes, Ana; Neves, Jose

    2013-04-01

    The most common approach to study the influence of certain road features on accidents has been the consideration of uniform road segments characterized by a unique feature. However, when an accident is related to the road infrastructure, its cause is usually not a single characteristic but rather a complex combination of several characteristics. The main objective of this paper is to describe a methodology developed in order to consider the road as a complete environment by using compound road environments, overcoming the limitations inherented in considering only uniform road segments. The methodology consists of: dividing a sample of roads into segments; grouping them into quite homogeneous road environments using cluster analysis; and identifying the influence of skid resistance and texture depth on road accidents in each environment by using generalized linear models. The application of this methodology is demonstrated for eight roads. Based on real data from accidents and road characteristics, three compound road environments were established where the pavement surface properties significantly influence the occurrence of accidents. Results have showed clearly that road environments where braking maneuvers are more common or those with small radii of curvature and high speeds require higher skid resistance and texture depth as an important contribution to the accident prevention. PMID:23376544

  4. Reconstruction of the Chernobyl emergency and accident management

    Full text of publication follows: on April 26, 1986 the most serious civil technological accident in the history of mankind occurred of the Chernobyl Nuclear Power Plant (ChNPP) in the former Soviet Union. As a direct result of the accident, the reactor was severely destroyed and large quantities of radionuclides were released. Some 800000 persons, also called 'liquidators' - including plant operators, fire-fighters, scientists, technicians, construction workers, emergency managers, volunteers, as well as medical and military personnel - were part of emergency measurements and accident management efforts. Activities included measures to prevent the escalation of the accident, mitigation actions, help for victims as well as activities in order to provide a basic infrastructure for this unprecedented and overwhelming task. The overall goal of the 'Project Chernobyl' of the Institute of Risk Research of the University of Vienna was to preserve for mankind the experience and knowledge of the experts among the 'liquidators' before it is lost forever. One method used to reconstruct the emergency measures of Chernobyl was the direct cooperation with liquidators. Simple questionnaires were distributed among liquidators and a database of leading accident managers, engineers, medical experts etc. was established. During an initial struggle with a number of difficulties, the response was sparse. However, after an official permit had been issued, the questionnaires delivered a wealth of data. Furthermore a documentary archive was established, which provided additional information. The multidimensional problem in connection with the severe accident of Chernobyl, the clarification of the causes of the accident, as well as failures and successes and lessons to be learned from the Chernobyl emergency measures and accident management are discussed. (authors)

  5. Study of evacuation times based on general accident history

    The RADTRAN 4 computer code, which calculates estimates of accident dose-risk corresponding to specified transportation scenarios, ascribes doses to potentially exposed members of the public. These persons are modeled as not being evacuated from the affected area for 24 hours following a release of radioactive material. Anecdotal evidence has suggested that this value may be unnecessarily conservative; consequently risk estimates are unnecessarily high. An initial survey of recent trucking accidents, reported in newspapers and other periodicals (1988 through 1994), that involved evacuation of the general population in the affected areas was undertaken to establish the actual time required for such evacuations. Accidents involving hazardous materials other than those which are radioactive (e.g., gasoline, insecticides, other chemicals) but also requiring evacuations of nearby residents were included in the survey. However, the resultant set of sufficiently documented trucking incidents yielded rather sparse data [1]. When the probability density distribution of the truck accident data was compared with that resulting from addition of four other (rail and fixed site) incidents, there was no statistically significant difference between them. Therefore, in order to improve the statistical significance of the data set, i.e., maximize the number of pertinent samples, a search for evacuations resulting from all types of accidents was performed. This resulted in many more references; a set of 48 incidents which could be adequately verified was compiled and merged with the original two data sets for a total of 66 evacuation accounts

  6. RETRAC, Reactor Core Accident Simulation

    1 - Description of program or function: The RETRAC code uses a set of coupled neutron point-kinetics equations and thermal-hydraulic conservation laws to simulate nuclear reactor core behaviour under transient or accident conditions. The reactor core is represented by single equivalent unit cells composed of three regions: fuel, clad, and moderator (coolant). 2 - Method of solution: At each time step, core thermal power is calculated by solving a set of six delayed neutron group kinetics equations with adjusted reactivity feedbacks. The numerical resolution is performed by using the Runge-Kutta-Gill method. The externally inserted reactivity is specified in the input data file, whereas Doppler, fuel, clad, and water temperature reactivity feedbacks are calculated by the code itself. Core cooling is treated as a homogeneous one-dimensional fluid flow through a representative unit cell composed of three successive regions: fuel, clad, and coolant. Several flow regime models are considered for both single- and two-phase states of the coolant. The conservation laws are solved by the method of characteristics coupled with an implicit finite difference scheme to ensure stability and convergence of the numerical algorithm. Validation tests of the RETRAC code were performed by using the International Atomic Energy Agency 10-MW benchmark cores, for protected transients. Further assessment studies are in progress using experimental data. 3 - Restrictions on the complexity of the problem: The RETRAC code uses steady-state thermal-hydraulic correlations. Their use is not always justified, but it seems to be quite useful in quasi-steady cases such as as loss-of-flow transients

  7. Development of the MIDAS GUI environment for severe accident management and analyses

    MIDAS is being developed at KAERI as an integrated severe accident analysis code with existing model modification and new model addition. Also restructuring of the data transfer scheme is going on to improve user's convenience. In this paper, various MIDAS GUI systems which are input management system IEDIT, variable plotting system IPLOT, severe accident training simulator SATS, and online guidance module HyperKAMG, are introduced. In addition, detail functions and usage of these systems for severe accident management and analyses are described

  8. A RESEARCH ON WORKING CONDITIONS AND OCCUPATIONAL ACCIDENTS AT THE FOREST HARVESTING ACTIVITIES

    MENEMENCİOĞLU, Kayhan

    2009-01-01

    This study was condcuted to have some information about the occupational accident ratio and some habits of forest harvesting workers, and the reasons of the accidents. The data obtained from a total of 250 forest workers responded to a self-administered questionnaire working at the harvesting practises at Directorates of Forest Enterprises Adana, Oltu, Ilgaz, Pazar and Sındırgı were discussed. According to findings; 47 % of forestry workers had at least an occupational accident and the cause...

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

    Jan Christian Kaiser

    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...

  10. The Fukushima Accident and Policy Implications: Notes on Public Perception in Germany

    Felix Richter; Malte Steenbeck; Markus Wilhelm

    2015-01-01

    Major nuclear accidents as recently in Fukushima set nuclear power plant security at the top of the public agenda. Using data of the German Socio-Economic Panel we analyze the effects of the Fukushima accident and a subsequent government decision on nuclear power phase-out on several measures of subjective perception in Germany. We find that the Fukushima accident increases the probability to report greater worries about the environment. Furthermore, we find evidence for a decrease in the pro...

  11. Social representations about the causes of accidents with needlestick materials by nursing technicians

    Juliana Almeida Marques Lubenow; Maria Eliete Batista Moura

    2013-01-01

    The accidents with needlestick materials are serious due to the diseases that can be caused. This is a descriptive study with qualitative approach and it was developed at a private hospital in Piauí, Brazil, between March and June 2011. The objective is analyzing the causes attributed by nursing technicians to their own accidents with needlestick, using the Social Representations Theory. Deep interviews were applied to 16 professionals who suffered this kind of accident. Data were processed i...

  12. Development and application of traffic accident density estimation models using kernel density estimation

    Seiji Hashimoto; Syuji Yoshiki; Ryoko Saeki; Yasuhiro Mimura; Ryosuke Ando; Shutaro Nanba

    2016-01-01

    Traffic accident frequency has been decreasing in Japan in recent years. Nevertheless, many accidents still occur on residential roads. Area-wide traffic calming measures including Zone 30, which discourages traffic by setting a speed limit of 30 km/h in residential areas, have been implemented. However, no objective implementation method has been established. Development of a model for traffic accident density estimation explained by GIS data can enable the determination of dangerous areas o...

  13. Preliminary dose assessment of the Chernobyl accident

    From the major accident at Unit 4 of the Chernobyl nuclear power station, a plume of airborne radioactive fission products was initially carried northwesterly toward Poland, thence toward Scandinavia and into Central Europe. Reports of the levels of radioactivity in a variety of media and of external radiation levels were collected in the Department of Energy's Emergency Operations Center and compiled into a data bank. Portions of these and other data which were obtained directly from published and official reports were utilized to make a preliminary assessment of the extent and magnitude of the external dose to individuals downwind from Chernobyl. Radioactive 131I was the predominant fission product. The time of arrival of the plume and the maximum concentrations of 131I in air, vegetation and milk and the maximum reported depositions and external radiation levels have been tabulated country by country. A large amount of the total activity in the release was apparently carried to a significant elevation. The data suggest that in areas where rainfall occurred, deposition levels were from ten to one-hundred times those observed in nearby ''dry'' locations. Sufficient spectral data were obtained to establish average release fractions and to establish a reference spectra of the other nuclides in the release. Preliminary calculations indicated that the collective dose equivalent to the population in Scandinavia and Central Europe during the first year after the Chernobyl accident would be about 8 x 106 person-rem. From the Soviet report, it appears that a first year population dose of about 2 x 107 person-rem (2 x 105 Sv) will be received by the population who were downwind of Chernobyl within the U.S.S.R. during the accident and its subsequent releases over the following week. 32 refs., 14 figs., 20 tabs

  14. Nuclear accident dosimetry intercomparison studies.

    Sims, C S

    1989-09-01

    Twenty-two nuclear accident dosimetry intercomparison studies utilizing the fast-pulse Health Physics Research Reactor at the Oak Ridge National Laboratory have been conducted since 1965. These studies have provided a total of 62 different organizations a forum for discussion of criticality accident dosimetry, an opportunity to test their neutron and gamma-ray dosimetry systems under a variety of simulated criticality accident conditions, and the experience of comparing results with reference dose values as well as with the measured results obtained by others making measurements under identical conditions. Sixty-nine nuclear accidents (27 with unmoderated neutron energy spectra and 42 with eight different shielded spectra) have been simulated in the studies. Neutron doses were in the 0.2-8.5 Gy range and gamma doses in the 0.1-2.0 Gy range. A total of 2,289 dose measurements (1,311 neutron, 978 gamma) were made during the intercomparisons. The primary methods of neutron dosimetry were activation foils, thermoluminescent dosimeters, and blood sodium activation. The main methods of gamma dose measurement were thermoluminescent dosimeters, radiophotoluminescent glass, and film. About 68% of the neutron measurements met the accuracy guidelines (+/- 25%) and about 52% of the gamma measurements met the accuracy criterion (+/- 20%) for accident dosimetry. PMID:2777549

  15. The radiological accident in Gilan

    The use of radioactive materials continues to offer a wide range of benefits throughout the world in medicine, research and industry. Precautions are, however, necessary in order to protect people from the detrimental effects of the radiation. Where the amount of radioactive material is substantial, e.g. with sources used in radiotherapy or industrial radiography, extreme care is necessary to prevent accidents that may have severe consequences for the individuals affected. Nevertheless, in spite of all precautions, accidents with radiation sources continue to occur. As part of its activities dealing with the safety of radiation sources, the IAEA follows up severe accidents in order to provide an account of their circumstances and medical aspects from which those organizations with responsibilities for radiation protection and the safety of radiation sources may learn. On 24 July 1996 a serious accident occurred at the Gilan combined cycle fossil fuel power plant in the Islamic Republic of Iran, when a worker who was moving thermal insulation materials around the plant noticed a shiny, pencil sized metal object lying in a trench and put it in his pocket. He was unaware that the metal object was an unshielded 185 GBq 192Ir source used for industrial radiography. This report compiles information about the medical and other aspects of the accident. As a result of exposure to the iridium source, the worker suffered from severe haematopoietic syndrome (bone marrow depression) and an unusually extended localized radiation injury requiring plastic surgery

  16. The radiological accident in Cochabamba

    In April 2002 an accident involving an industrial radiography source containing 192Ir occurred in Cochabamba, Bolivia, some 400 km from the capital, La Paz. A faulty radiography source container had been sent back to the headquarters of the company concerned in La Paz together with other equipment as cargo on a passenger bus. This gave rise to a potential for serious exposure for the bus passengers as well as for the company employees who were using and transporting the source. The Government of Bolivia requested the assistance of the IAEA under the terms of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency. The IAEA in response assembled and sent to Bolivia a team composed of senior radiation safety experts and radiation pathology experts from Brazil, the United Kingdom and the IAEA to investigate the accident. The IAEA is grateful to the Government of Bolivia for the opportunity to report on this accident in order to disseminate the valuable lessons learned and help prevent similar accidents in the future

  17. Accident knowledge and emergency management

    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.

  18. Accident knowledge and emergency management

    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

  19. Traffic Accidents on Slippery Roads

    Fonnesbech, J. K.; Bolet, Lars

    2014-01-01

    Police registrations from 65 accidents on slippery roads in normally Danish winters have been studied. The study showed: • 1 accident per 100 km when using brine spread with nozzles • 2 accidents per 100 km when using pre wetted salt • 3 accidents per 100 km when using kombi spreaders The results...... of accidents in normally Danish winter seasons are remarkable alike the amount of salt used in praxis in the winter 2011/2012. • 2.7 ton NaCl/km when using brine spread with nozzles • 5 ton NaCl/km when using pre wetted salt. • 5.7 ton NaCl/km when using kombi spreaders The explanation is that spreading...... of brine with nozzles is precision spreading, while spreading of salt with rotation plate are very imprecise; you can measure 80% residual salt when using brine and only 40% when using pre wetted salt. Of course the result would be worse if dry (solid) salt were used on dry roads. A winter route in Denmark...

  20. [Venomous animal accidents in childhood

    Oliveira, J S; Campos, J A; Costa, D M

    1999-11-01

    OBJECTIVE: To highlight the importance of venomous animal accidents in childhood. The conducts are based on the proposals of the Ministério da Saúde do Brasil [Ministry of Health of Brazil] to standardize medical care in this kind of accident. This article shows the importance of early clinical diagnosis and assistance.METHODS: Review of international and national literature that includes original articles, official standards and books.RESULTS: Pediatricians may always feel insecure when they have to attend children who had venomous animal accidents because this kind of pathology is not very common. This article tries to offer easy guidelines and describes the main steps to be followed. Besides, peculiar or unusual aspects of these accidents are to be found in the literature referred to in the end of this article. Venomous animal accidents are always more severe in children, therefore resulting in higher mortality and sequelae. We assert that the early antivenom sera is extremely helpful.CONCLUSIONS: The systematization of the assistance may guarantee that the essential steps are followed thus making the assistance itself more effective. This is the purpose of the guidelines presented in this article. PMID:14685472

  1. Development of the severe accident risk information database management system SARD

    The main purpose of this report is to introduce essential features and functions of a severe accident risk information management system, SARD (Severe Accident Risk Database Management System) version 1.0, which has been developed in Korea Atomic Energy Research Institute, and database management and data retrieval procedures through the system. The present database management system has powerful capabilities that can store automatically and manage systematically the plant-specific severe accident analysis results for core damage sequences leading to severe accidents, and search intelligently the related severe accident risk information. For that purpose, the present database system mainly takes into account the plant-specific severe accident sequences obtained from the Level 2 Probabilistic Safety Assessments (PSAs), base case analysis results for various severe accident sequences (such as code responses and summary for key-event timings), and related sensitivity analysis results for key input parameters/models employed in the severe accident codes. Accordingly, the present database system can be effectively applied in supporting the Level 2 PSA of similar plants, for fast prediction and intelligent retrieval of the required severe accident risk information for the specific plant whose information was previously stored in the database system, and development of plant-specific severe accident management strategies

  2. Development of the severe accident risk information database management system SARD

    Ahn, Kwang Il; Kim, Dong Ha

    2003-01-01

    The main purpose of this report is to introduce essential features and functions of a severe accident risk information management system, SARD (Severe Accident Risk Database Management System) version 1.0, which has been developed in Korea Atomic Energy Research Institute, and database management and data retrieval procedures through the system. The present database management system has powerful capabilities that can store automatically and manage systematically the plant-specific severe accident analysis results for core damage sequences leading to severe accidents, and search intelligently the related severe accident risk information. For that purpose, the present database system mainly takes into account the plant-specific severe accident sequences obtained from the Level 2 Probabilistic Safety Assessments (PSAs), base case analysis results for various severe accident sequences (such as code responses and summary for key-event timings), and related sensitivity analysis results for key input parameters/models employed in the severe accident codes. Accordingly, the present database system can be effectively applied in supporting the Level 2 PSA of similar plants, for fast prediction and intelligent retrieval of the required severe accident risk information for the specific plant whose information was previously stored in the database system, and development of plant-specific severe accident management strategies.

  3. A database system for the management of severe accident risk information, SARD

    Ahn, K. I.; Kim, D. H. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    The purpose of this paper is to introduce main features and functions of a PC Windows-based database management system, SARD, which has been developed at Korea Atomic Energy Research Institute for automatic management and search of the severe accident risk information. Main functions of the present database system are implemented by three closely related, but distinctive modules: (1) fixing of an initial environment for data storage and retrieval, (2) automatic loading and management of accident information, and (3) automatic search and retrieval of accident information. For this, the present database system manipulates various form of the plant-specific severe accident risk information, such as dominant severe accident sequences identified from the plant-specific Level 2 Probabilistic Safety Assessment (PSA) and accident sequence-specific information obtained from the representative severe accident codes (e.g., base case and sensitivity analysis results, and summary for key plant responses). The present database system makes it possible to implement fast prediction and intelligent retrieval of the required severe accident risk information for various accident sequences, and in turn it can be used for the support of the Level 2 PSA of similar plants and for the development of plant-specific severe accident management strategies.

  4. State of health of the population Belarus on the data of the Belarussian state register of the persons who have undergone to effect of radiation owing to Chernobyl accident

    The purpose - to estimate a state of health of the population of Belarus, injured of Chernobyl accident. In 2006 in comparison with 1995 among the population of Belarus, injured of Chernobyl accident, on 25,5 % the incidence rate by neoplasms, including on 65,6 % by malignant tumors and on 12,2 % - benign has grown. Among malignant tumor the greatest rate of increase characterized a case rate by malignant tumor of urinary paths, lymphatic and hemopoietic tissue, organs of digestion. The body height of incidence by the acquired hypothyrosis, autoimmune thyroiditis, diabetes mellitus, cataract, glaucoma, illnesses described by boosted bloody pressure, acute myocardial infarction, subarachnoidal hemorrhage was prolonged. From a total number of diseases registered among the population of Belarus, injured of Chernobyl accident, 66,5 % were necessary on the persons who were taking part in liquidation of Chernobyl accident, 29,6 % on the persons living or living in territories with density of contamination Cs137 more 555 kBq/m2. The relation of a prevalence and incidence rate has made in 1995 year - 1,7, in 2006 year - 4,2, that testifies to essential accumulation of a chronic pathology. During 1995-2006 years the dynamics of a mortality from all reasons among the population of Belarus, injured of Chernobyl accident had the expressed tendency to body height. In 2006 among the persons recognized by the invalids, 71,3 % were necessary on liquidators, 24,0 % - on territories with density of contamination 137Cs more 555 kBq/m2. For period 1995 - 2006 years the tendency to lowering gravity of invalidism was planned. Since 1998, the invalidism has no the tendency to body height. In frame of reasons of invalidism the diseases of the system of a circulation, neoplasm both illness of the osteomuscular system and connective tissue predominated. (author)

  5. Epidemiological profile of patients with cerebral vascular accident

    Carolline Paulo Neto da Cunha Lima, Marta Miriam Lopes Costa, Maria Julia Guimarães Oliveira Soares

    2009-10-01

    Full Text Available Objectives: to show the profile epidemiological of patients with cerebral vascular accident in a public hospital from João Pessoa city, Paraíba, Brazil; to investigate the social demographic profile; to identify the risk factors, symptoms and sequels of the cerebral vascular accident. Methods: this is about a descriptive and exploratory study, from quantitative approach; the population was configured by sixty handbooks. Data collect was performed with a form from March to April 2007, and then data were analyzed and presented in tables and figures. This study was approval by the Ethics Committee under protocol number 58/2007. Results: data has been demonstrated that most of the handbooks belonged to patients from 46 to 85 years old; from female; they came from Mata Paraibana region; they were patients with hypertension; they had cerebral vascular accident of the type hemorrhagic. Conclusion: this study was very important for nurses, since it allowed them to have knowledge to help reduce the number of deaths and sequelae of cerebral vascular accident, also contributed to the basics to change like this, as knowledge of the disease and fitness treatment methods (among them, stand out studies of risk factors and relevance of applying an early prevention of cerebral vascular accident. Thus, the role of nursing is to prevent and detect early complications, educating the population about the disease.

  6. Nuclear law and radiological accidents

    Nuclear activities in Brazil, and particularly the radiological accident of Goiania, are examined in the light of the environmental and nuclear laws of Brazil and the issue of responsibility. The absence of legislation covering radioactive wastes as well as the restrictions on Brazilian States to issue regulations covering nuclear activities are reviewed. The radiological accident and its consequences, including the protection and compensation of the victims, the responsibility of the shareholders of the Instituto Goiano de Radioterapia, operator of the radioactive source, the provisional storage and the final disposal at Abadia de Goias of the radioactive waste generated by the accident are reviewed. Finally, nuclear responsibility, the inapplicability of the Law 6453/77 which deals with nuclear damages, and the state liability regime are analysed in accordance with the principles of the Brazilian Federal Constitution. (author)

  7. Fukushima accident study using MELCOR

    Randall O Gauntt

    2013-01-01

    The accidents at the Fukushima Daiichi nuclear power station stunned the world as the sequences played out over severals days and videos of hydrogen explosions were televised as they took place.The accidents all resulted in severe damage to the reactor cores and releases of radioactivity to the environment despite heroic measures had taken by the operating personnel.The following paper provides some background into the development of these accidents and their root causes,chief among them,the prolonged station blackout conditions that isolated the reactors from their ultimate heat sink — the ocean.The interpretations given in this paper are summarized from a recently completed report funded by the United States Department of Energy (USDOE).

  8. Air cleaning in accident situations

    The Organization for Economic Co-Operation and Development (OECD) through its subsidiaries the Nuclear Energy Agency (NEA) and the Committee on the Safety of Nuclear Installations (CSNI) established in 1979 a Group of Experts or Air Cleaning in Accident Situations. This group met seven times to establish a draft report based on its Terms of Reference which were to: 1) review the performance of off-gas cleaning systems in accident conditions; 2) collect information about operating experience with these systems; 3) seek to establish common principles for the design of off-gas systems; 4) review methods used in the different countries for testing filters from the standpoint of accident conditions; and 5) suggest specific mechanisms for improving cooperation, with regard, for example, to filter testing. The conclusions and recommendations of the Group are summarized

  9. Nuclear accidents - Liabilities and guarantees

    The 1992 Symposium on Nuclear Accidents - Liabilities and guarantees, organized by the OECD NUCLEAR Energy Agency in collaboration with the international Atomic Energy Agency, discussed the nuclear third party liability regime established by the Paris and Vienna Conventions, its advantages and shortcomings, and assessed the teachings of the Chernobyl accident in the context of that regime. The topics included the geographical scope of the Conventions, the definition of nuclear damage, in particular environmental damage, insurance cover and capacity, supplementary compensation by means of a collective contribution from the nuclear industry or governments, and finally, the international liability of States in case of a nuclear accident. This proceeding contains 26 papers which have been selected

  10. Severe accident simulation at Olkiuoto

    Tirkkonen, H.; Saarenpaeae, T. [Teollisuuden Voima Oy (TVO), Olkiluoto (Finland); Cliff Po, L.C. [Micro-Simulation Technology, Montville, NJ (United States)

    1995-09-01

    A personal computer-based simulator was developed for the Olkiluoto nuclear plant in Finland for training in severe accident management. The generic software PCTRAN was expanded to model the plant-specific features of the ABB Atom designed BWR including its containment over-pressure protection and filtered vent systems. Scenarios including core heat-up, hydrogen generation, core melt and vessel penetration were developed in this work. Radiation leakage paths and dose rate distribution are presented graphically for operator use in diagnosis and mitigation of accidents. Operating on an graphically for operator use in diagnosis and mitigation of accidents. Operating on an 486 DX2-66, PCTRAN-TVO achieves a speed about 15 times faster than real-time. A convenient and user-friendly graphic interface allows full interactive control. In this paper a review of the component models and verification runs are presented.

  11. Severe accident management guidelines tool

    Severe Accident is addressed by means of a great number of documents such as guidelines, calculation aids and diagnostic trees. The response methodology often requires the use of several documents at the same time while Technical Support Centre members need to assess the appropriate set of equipment within the adequate mitigation strategies. In order to facilitate the response, TECNATOM has developed SAMG TOOL, initially named GGAS TOOL, which is an easy to use computer program that clearly improves and accelerates the severe accident management. The software is designed with powerful features that allow the users to focus on the decision-making process. Consequently, SAMG TOOL significantly improves the severe accident training, ensuring a better response under a real situation. The software is already installed in several Spanish Nuclear Power Plants and trainees claim that the methodology can be followed easier with it, especially because guidelines, calculation aids, equipment information and strategies availability can be accessed immediately (authors)

  12. Internal Accident Report on EDH

    SC Department

    2006-01-01

    The A2 Safety Code requires that, the Internal Accident Report form must be filled in by the person concerned or any witness to ensure that all the relevant services are informed. Please note that an electronic version of this form has been elaborated in collaboration with SC-IE, HR-OPS-OP and IT-AIS. Whenever possible, the electronic form shall be used. The relative icon is available on the EDH Desktop, Other tasks page, under the Safety heading, or directly here: https://edh.cern.ch/Document/Accident/. If you have any questions, please contact the SC Secretariat, tel. 75097 Please notice that the Internal Accident Report is an integral part of the Safety Code A2 and does not replace the HS50.

  13. Hindsight Bias in Cause Analysis of Accident

    Atsuo Murata; Yasunari Matsushita

    2014-01-01

    It is suggested that hindsight becomes an obstacle to the objective investigation of an accident, and that the proper countermeasures for the prevention of such an accident is impossible if we view the accident with hindsight. Therefore, it is important for organizational managers to prevent hindsight from occurring so that hindsight does not hinder objective and proper measures to be taken and this does not lead to a serious accident. In this study, a basic phenomenon potentially related to accidents, that is, hindsight was taken up, and an attempt was made to explore the phenomenon in order to get basically insights into the prevention of accidents caused by such a cognitive bias.

  14. JCO criticality accident termination operation

    In 2001, we summarized the circumstances surrounding termination of the JCO criticality accident based on testimony in the Mito District Court on December 17, 2001. JCO was the company for uranium fuels production in Japan. That document was assembled based on actual testimony in the belief that a description of the work involved in termination of the accident would be useful in some way for preventing nuclear disasters in the future. The description focuses on the witness' own behavior, and what he saw and heard, and thus is written from the perspective of action by one individual. This was done simply because it was easier for the witness to write down his memories as he remembers them. Description of the activities of other organizations and people is provided only as necessary, to ensure that consistency in the descriptive approach is not lost. The essentials of this report were rewritten as a third-person objective description in the summary of the report by the Atomic Energy Society of Japan (AESJ). Since then, comments have been received from sources such as former members of the Nuclear Safety Commission (Dr. Kenji Sumita and Dr. Akira Kanagawa), concerned parties from the former Science and Technology Agency, and reports from the JCO Criticality Accident Investigation Committee of the AESJ, and thus this report was rewritten to correct incorrect information, and add material where that was felt to be necessary. This year is the tenth year of the JCO criticality accident. To mark this occasion we have decided to translate the record of what occurred at the accident site into English so that more people can draw lessons from this accident. This report is an English version of JAEA-Technology 2009-073. (author)

  15. Human factors review for Severe Accident Sequence Analysis (SASA)

    The paper will discuss work being conducted during this human factors review including: (1) support of the Severe Accident Sequence Analysis (SASA) Program based on an assessment of operator actions, and (2) development of a descriptive model of operator severe accident management. Research by SASA analysts on the Browns Ferry Unit One (BF1) anticipated transient without scram (ATWS) was supported through a concurrent assessment of operator performance to demonstrate contributions to SASA analyses from human factors data and methods. A descriptive model was developed called the Function Oriented Accident Management (FOAM) model, which serves as a structure for bridging human factors, operations, and engineering expertise and which is useful for identifying needs/deficiencies in the area of accident management. The assessment of human factors issues related to ATWS required extensive coordination with SASA analysts. The analysis was consolidated primarily to six operator actions identified in the Emergency Procedure Guidelines (EPGs) as being the most critical to the accident sequence. These actions were assessed through simulator exercises, qualitative reviews, and quantitative human reliability analyses. The FOAM descriptive model assumes as a starting point that multiple operator/system failures exceed the scope of procedures and necessitates a knowledge-based emergency response by the operators. The FOAM model provides a functionally-oriented structure for assembling human factors, operations, and engineering data and expertise into operator guidance for unconventional emergency responses to mitigate severe accident progression and avoid/minimize core degradation. Operators must also respond to potential radiological release beyond plant protective barriers. Research needs in accident management and potential uses of the FOAM model are described. 11 references, 1 figure

  16. Consequences of the Chernobyl accident

    The techniques currently used in off-site consequence modelling are applied to the Chernobyl accident. Firstly, the time dependent spread of radioactive material across the European continent is considered, followed by a preliminary assessment of the dosimetric impact (in terms of collective and mean individual doses) on the various countries of Eastern and Western Europe. The consequences of the accident in the USSR are also discussed. Finally, the likely implications of the Chernobyl event on research in the field of environmental consequence assessment are outlined. (author)

  17. Severe accident source term reassessment

    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)

  18. The nature of reactor accidents

    Reactor accidents are events which result in the release of radioactive material from a nuclear power plant due to the failure of one or more critical components of that plant. The failures, depending on their number and type, can result in releases whose consequences range from negligible to catastrophic. By way of examples, this paper describes four specific accidents which cover this range of consequence: failure of a reactor control system, loss of coolant, loss of coolant with impaired containment, and reactor core meltdown. For each a possible sequence of events and an estimate of the expected frequency are presented

  19. Civil liability concerning nuclear accidents

    France and the USA wish to cooperate in order to promote an international regime of civil liability in order to give a fair compensation to victims of nuclear accidents as it is recommended by IAEA. On the other hand the European Commission has launched a consultation to see the necessity or not to harmonize all the civil liability regimes valid throughout Europe. According to the Commission the potential victims of nuclear accidents would not receive equal treatment at the European scale in terms of insurance cover and compensation which might distort competition in the nuclear sector. (A.C.)

  20. Chemistry of fission products for accident analysis

    Current knowledge concerning the chemical state of the fission product elements during the development of accidents in water reactor systems is reviewed in this paper. The fission product elements which have been considered are Cs, I, Te, Sr and Ba but aspects of the behavior of Mo, Ru and the lanthanides are also discussed. Some features of the reactions of the various species of these elements with other components of the reactor systems are described. The importance of having an adequate knowledge of thermodynamic data and phase equilibria of relatively simple systems in order to interpret experimental observations on complex multi-component systems is stressed

  1. Children thyroid carcinoma and Chernobyl accident

    In Nuclear medicine diagnostic department of Kaunas Medical University Clinics 22 children (6-16 years of age), ill with thyroid carcinoma were examined. Bas ing on the data of Kaunas Medical University Clinic the incidence of children thyroid carcinoma did not increase after Chernobyl accident. Ratio of boys and girls was 4.5:1. Differentiated thyroid carcinoma was detected in 15 (68.2%)children, mixed carcinoma - 4 (18.2%), nondiferenciated -3 (13.6%) children. First stage of cancer was detected only in one patient (4.5%), second -16 (72.7%), third - 3 (13.6%), fourth stage - 2 (9.1%) patients. (author)

  2. Transport and machinery accidents in South African underground mines

    Gouws, M.J.; Owen-Thomas, D.; Stewart, J.M. [Chamber of Mines of South Africa, Johannesburg (South Africa)

    1997-09-01

    A significant proportion of the total injuries and fatalities in underground coal mines in South African are related to transport and machinery. Data are presented to show that, over the past decade, the injury rate has not declined significantly and that 29% of injuries and 17% of fatalities occurred in the area of transport and machinery. An analysis of transport and machinery accident data is provided, in which accidents are classified by equipment and tasks. A new strategy to improve health and safety in mines is described. 8 refs., 3 figs., 2 tabs., 1 app.

  3. Impact of Fukushima nuclear accident to China's mainland environment

    Terrestrial Environment Radiation monitoring results by environmental protection agencies of China after Fukushima Nuclear Accident were collected. Combined with the atmospheric circulation and monitoring results from IMS and CTBTO, and also through comparison with data from USA, France, Canada and etc, the monitoring data in China were analyzed and evaluated. With the approaches introduced from the Source and Effects of Ionizing Radiation-UNSCEAR 2000 Report to the General Assembly (with scientific annexes) and the Generic procedures for Assessment and Response during a Radiological Emergency, the radiation dose of Chinese population impacted from this accident was initially estimated. (authors)

  4. Differences in Characteristics of Aviation Accidents during 1993-2012 Based on Flight Purpose

    Evans, Joni K.

    2016-01-01

    Usually aviation accidents are categorized and analyzed within flight conduct rules (Part 121, Part 135, Part 91) because differences in accident rates within flight rules have been demonstrated. Even within a particular flight rule the flights have different purposes. For many, Part 121 flights are synonymous with scheduled passenger transport, and indeed this is the largest group of Part 121 accidents. But there are also non-scheduled (charter) passenger transport and cargo flights. The primary purpose of the analysis reported here is to examine the differences in aviation accidents based on the purpose of the flight. Some of the factors examined are the accident severity, aircraft characteristics and accident occurrence categories. Twenty consecutive years of data were available and utilized to complete this analysis.

  5. Modeling of pipe break accident in a district heating system using RELAP5 computer code

    Reliability of a district heat supply system is a very important factor. However, accidents are inevitable and they occur due to various reasons, therefore it is necessary to have possibility to evaluate the consequences of possible accidents. This paper demonstrated the capabilities of developed district heating network model (for RELAP5 code) to analyze dynamic processes taking place in the network. A pipe break in a water supply line accident scenario in Kaunas city (Lithuania) heating network is presented in this paper. The results of this case study were used to demonstrate a possibility of the break location identification by pressure decrease propagation in the network. -- Highlights: ► Nuclear reactor accident analysis code RELAP5 was applied for accident analysis in a district heating network. ► Pipe break accident scenario in Kaunas city (Lithuania) district heating network has been analyzed. ► An innovative method of pipe break location identification by pressure-time data is proposed.

  6. Using modular neural networks to monitor accident conditions in nuclear power plants

    Nuclear power plants are very complex systems. The diagnoses of transients or accident conditions is very difficult because a large amount of information, which is often noisy, or intermittent, or even incomplete, need to be processed in real time. To demonstrate their potential application to nuclear power plants, neural networks axe used to monitor the accident scenarios simulated by the training simulator of TVA's Watts Bar Nuclear Power Plant. A self-organization network is used to compress original data to reduce the total number of training patterns. Different accident scenarios are closely related to different key parameters which distinguish one accident scenario from another. Therefore, the accident scenarios can be monitored by a set of small size neural networks, called modular networks, each one of which monitors only one assigned accident scenario, to obtain fast training and recall. Sensitivity analysis is applied to select proper input variables for modular networks

  7. Ignalina accident localisation system response to maximum design basis accident

    In this paper the study of the accident localisation system (ALS) of the Ignalina nuclear power plant (NPP) with RBMK-1500 reactors (large-power channel-type water-cooled graphite-moderated reactor) with regard to a maximum design basis accident (MDBA) is presented. The MDBA for Ignalina NPP constitutes a guillotine rupture of the maximum diameter pipe. The thermal-hydraulic and structural analyses were performed using the RELAP5, CONTAIN and ALGOR codes. The coolant mass and energy discharge source terms to the accident compartment were established using the RELAP5 code. This was then used as a source term for the long-term accident thermal-hydraulic analysis of ALS compartments employing the CONTAIN code. Results obtained by the CONTAIN calculations establish a basis for the structural analysis. A finite-element method has been used for ALS structural analysis using the ALGOR code, the results of which show that the structures of the ALS would not be breached by the pressure attained in the event of an MDBA. (author)

  8. Lessons learned and evaluation of the impact from the Chernobyl accident

    The impact on society of the Chernobyl accident is assessed. The situation prior to Chernobyl with respect to regulations of radiation protection against the consequences of a major accident is considered. The development of the recommendations and regulations issued by the CEC for the Maximum Permitted Levels of different reactions to the accident are examined and some data on the average individual effective dose equivalents estimated in a number of countries are reported. Finally some main problems concerning the information of the public and the preparedness for possible future accidents are also summarized. (author)

  9. China's coal mine accident statistics analysis and one million tons mortality prediction

    Qiao Tong

    2016-01-01

    In order to study the general rule of coal mine accidents in China in recent years, the data of coal mine accident in 2011-2015 is analyzed. The mathematical statistics method is used to analyze the occurrence year, type, season and area of the accident. The results of analysis shows that the coal mine accident has been reduced year by year, and the frequency of gas explosion is the highest. The frequency and the number of deaths in the second quarter of the year are the highest; Guizhou p...

  10. Problems of dosimetric evaluation of radiation accident situations with external irradiation in neutron and gamma field

    The problems are discussed of the dosimetric evaluation of radiation accident situations in a mixed gamma and neutron field. The methods and means of accident dosimetry should allow evaluation basically in three stages: (1) within 6 hours following an accident to classify persons according to radiation exposure; (2) to obtain data on the maximum absorbed dose with accuracy better than +-50% within 48 hours; (3) to establish depth dose values with accuracy better than +-20 to 25% within 3 to 6 days. Recommendations are shown related to safeguarding dosimetric systems for radiation accident situations in nuclear facilities. (B.S.)

  11. On the graphic simulation of severe accidents using IBM PC

    In this paper some methods of developing a graphical simulation system using IBM PC and MELCOR code were discussed. Most TH codes, which can calculate the severe accident phenomena parameters, are now running on workstations or supercomputers, to meet the complicated calculations. But the recent progress in computer engineering including personal computers make it possible to run TH codes in small microprocessor environments. Therefore we have surveyed some technical aspects in developing a severe accident graphical simulation system using IBM PC and MELCOR code. Especially noticing the complicated calculation results and the difficulties in obtaining continuous data due to the large data size, which are main defects of TH codes, we also surveyed the graphical methods to overcome these problems. The proposed methods are expected to play important roles in developing our graphic simulation system of severe accidents

  12. Simple estimate of fission rate during JCO criticality accident

    Oyamatsu, Kazuhiro [Faculty of Studies on Contemporary Society, Aichi Shukutoku Univ., Nagakute, Aichi (Japan)

    2000-03-01

    The fission rate during JCO criticality accident is estimated from fission-product (FP) radioactivities in a uranium solution sample taken from the preparation basin 20 days after the accident. The FP radioactivity data are taken from a report by JAERI released in the Accident Investigation Committee. The total fission number is found quite dependent on the FP radioactivities and estimated to be about 4x10{sup 16} per liter, or 2x10{sup 18} per 16 kgU (assuming uranium concentration 278.9 g/liter). On the contrary, the time dependence of the fission rate is rather insensitive to the FP radioactivities. Hence, it is difficult to determine the fission number in the initial burst from the radioactivity data. (author)

  13. A MELCOR model of Fukushima Daiichi Unit 3 accident

    Highlights: • A MELCOR model of the Fukushima Unit 3 accident was developed. • The MELCOR input file is published as electronic supplementary data with this paper. • Reactor pressure vessel lower head failed about 53 h after the earthquake. • 70% of fuel was discharged from reactor to containment. • 0.95% of cesium inventory was released to the environment. - Abstract: A MELCOR model of the Fukushima Daiichi Unit 3 accident was developed. The model is based on publicly available information, and the MELCOR input file is published as electronic supplementary data with this paper. According to the calculation, the reactor pressure vessel lower head failed about 53 h after the earthquake. At the end of the calculation, 30% of the fuel was still inside the reactor and 70% had been discharged to the containment. Almost all of the radioactive noble gases and 0.95% of the cesium inventory were released to the environment during the accident

  14. A MELCOR model of Fukushima Daiichi Unit 3 accident

    Sevón, Tuomo, E-mail: tuomo.sevon@vtt.fi

    2015-04-01

    Highlights: • A MELCOR model of the Fukushima Unit 3 accident was developed. • The MELCOR input file is published as electronic supplementary data with this paper. • Reactor pressure vessel lower head failed about 53 h after the earthquake. • 70% of fuel was discharged from reactor to containment. • 0.95% of cesium inventory was released to the environment. - Abstract: A MELCOR model of the Fukushima Daiichi Unit 3 accident was developed. The model is based on publicly available information, and the MELCOR input file is published as electronic supplementary data with this paper. According to the calculation, the reactor pressure vessel lower head failed about 53 h after the earthquake. At the end of the calculation, 30% of the fuel was still inside the reactor and 70% had been discharged to the containment. Almost all of the radioactive noble gases and 0.95% of the cesium inventory were released to the environment during the accident.

  15. Supplemental study on dose control for a criticality accident

    Tokaimura criticality accident is considered as a precious material for nuclear emergency response study. In the previous report 'A Study on Dose Control for JCO Criticality Accident Termination' (JAEA-Technology 2009-043), we discussed how to control the dose received during the termination work of the criticality accident. We reevaluated the dose rate at work place based on the dose rate measurement data ranging around 40 to 100 m from the criticality accident point, and compared it with the dose rate calculated based on the worker's dose received. They matched within 60% to 80% accuracy. In this paper, we focused on the difference of the way in which dose rate attenuates between within 100 m from the source point and beyond 100 m and discussed the validity of using log-log plotting / semi-log plotting of dose rate - distance relation in order to extrapolate the dose rate at work place near the criticality accident point. In addition, we studied on the effect of the number of dose rate measurement data to be used for extrapolation. We recommend that about 10 mSv which is a half of 20 mSv annual dose limit should be used as worker's dose control target for the high neutron dose field work to ensure enough safety margin considering the following three points; 1. annual dose limit for workers, 2. dose received before, 3. measurement error. (author)

  16. Program for rapid dose assessment in criticality accident, RADAPAS

    In a criticality accident, a person near fissile material can receive extremely high dose which can cause acute health effect. For such a case, medical treatment should be carried out for the exposed person, according to severity of the exposure. Then, radiation dose should be rapidly assessed soon after an outbreak of an accident. Dose assessment based upon the quantity of induced 24Na in human body through neutron exposure is expected as one of useful dosimetry techniques in a criticality accident. A dose assessment program, called RADAPAS (RApid Dose Assessment Program from Activated Sodium in Criticality Accidents), was therefore developed to assess rapidly radiation dose to exposed persons from activity of induced 24Na. RADAPAS consists of two parts; one is a database part and the other is a part for execution of dose calculation. The database contains data compendiums of energy spectra and dose conversion coefficients from specific activity of 24Na induced in human body, which had been derived in a previous analysis using Monte Carlo calculation code. Information for criticality configuration or characteristics of radiation in the accident field is to be interactively given with interface displays in the dose calculation. RADAPAS can rapidly derive radiation dose to the exposed person from the given information and measured 24Na specific activity by using the conversion coefficient in database. This report describes data for dose conversions and dose calculation in RADAPAS and explains how to use the program. (author)

  17. Validation and verification of accident consequence assessment models

    Homma, T.; Togawa, O. [Japan Atomic Energy Research Inst., Tokyo (Japan); Takahashi, T. [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Arkhipov, A.N. [Chernobyl Science and Technology Centre for International Research (Ukraine)

    2001-03-01

    An accident consequence assessment code, OSCAAR, primarily designed by Japan Atomic Energy Research Institute (JAERI) for use in probabilistic safety assessment (PSA) of nuclear reactors in Japan, was applied to use for siting, emergency planning, and development of design criteria, and in the comparative risk studies of different energy systems. After verifying the code system through the international code comparison organized by CEC and OECD/NEA, the validation and improvements of the individual models and the verification of the whole OSCAAR code system were made. The cooperative research between Chernobyl Science and Technology Center for International Research (CHESCIR) and JAERI provided a valuable opportunity to test the performance of the accident consequence assessment models by comparing the model predictions with data obtained in the Chernobyl accidents. The predictive capabilities of OSCAAR were demonstrated using the accident source term and meteorological data for estimating the early exposure to the public occurred during and shortly after plume passage. The calculations indicated that ground-shine dose and inhalation dose, particularly from large nonvolatile particulates were the main contributors in the early stage of the accident. (S. Ohno)

  18. Waste form characterization and its relationship to transportation accident analysis

    The response of potential waste forms should be determined for extreme transportation environments that must be postulated for environmental impact analysis and also for hypothetical accident conditions to which packagings and contents must be subjected for licensing purposes. The best approach may be to test materials up to and beyond their failure point; such an approach would establish failure thresholds. Specification of what denotes failure would be defined by existing or proposed regulations or dictated by requirements developed from accident analysis. Responses to physical and thermal insults are the most important for licensing or analysis and need to be thoroughly characterized. Others in need of characterization might be responses to extreme chemical environments and to intense and prolonged radiation exposure. A complete characterization of waste-form responses would be desirable for environments that are considered extreme for transportation accidents but which may be typical for processing or disposal environments. In addition, the characterizations that are performed must be completed in laboratory environments which can be readily correlated to accident environments and must be meaningfully conveyed to a transportation impact analyst. As an example, leaching data as commonly presented are not usable to the analyst and are obtained under conditions that are not directly applicable to conditions of most transportation accidents. Transportation analysts are in need of data useful for calculating environmental impacts and for licensing of packagings. Future waste form development programs and associated decisions should consider the needs of transportation analysts

  19. Plutonium emission from the Fukushima accident

    A strong earthquake and subsequent tsunami on 11th March 2011 initiated a severe accident in units 1 to 4 of Fukushima Dai-ichi nuclear power plant, resulting in substantial releases of radionuclides. While much has since been published 00 environmental contamination and exposure to radio--iodine and radio-caesium, little is known about releases of plutonium and other non-volatile elements. Although the total activities of released 131I, 134Cs and 137Cs are of the same order of magnitude as of the Chernobyl accident in 1986, the contribution of little volatile elements, including Pu, is much smaller in Fukushima fallout. The reason is the different physical nature of the accident sequence which led to a release of some 10-5% of the core inventories only (to be compared with 3.5% from Chernobyl). In this contribution the available data on Pu in Fukushima fallout will be reviewed. Data sources are mainly reports and press releases by Japanese authorities and a few scientific articles. The mean ratio 239+240Pu: 137Cs in the near field around the NPP (mainly part of Fukushima prefecture and districts of adjacent prefectures) can be assumed about 3 x 10-7, to be compared to nearly 0.01 in the vicinity of Chernobyl, down to about 3 x 10 -6 in Central Europe. Isotopic ratios 238Pu: 239+240 Pu are about 2.2 (0.46 and 0.035 in Chemobyl and global fallout, respectively). Activity concentrations of Fukushima- 239+240 Pu in surface soil were found up to above 0.1 Bq/kg d.m. in the immediate vicinity of the Fukushima NPP and about one order of magnitude less in Fukushima city, about 60 km away. The 239+240 Pu activity released into the atmosphere is roughly estimated some 109 Bq (Chemobyl : almost 1014 Bq). (author)

  20. Heat and fluid flow in accident of Fukushima Daiichi Nuclear Power Plant, Unit 1. Accident scenario based on thermodynamic model

    An accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 1 is analyzed from the data open to the public. Two thermodynamic modes are introduced i.e. a phase equilibrium process model in the reactor pressure vessel (RPV) and an adiabatic model in the pressure containment vessel (PVC). Almost the measured data and observed evidences are explained by the scenario that the isolation condenser was working and a crack at RPV opened at the initial stage of the accident, which is different from TEPCO and the government reports. (author)

  1. Industrial accidents in nuclear power plants

    In 12 nuclear power plants in the Federal Republic of Germany with a total of 3678 employees, 25 notifiable company personnel accidents and 46 notifiable outside personnel accidents were reported for an 18-month period. (orig./HP)

  2. Road Accident Trends in Africa and Europe

    Jørgensen, N O

    1997-01-01

    The paper decribes trends and suggests prediction models for accident risks in African and European countries......The paper decribes trends and suggests prediction models for accident risks in African and European countries...

  3. 49 CFR 229.17 - Accident reports.

    2010-10-01

    ... CFR part 225. ... 49 Transportation 4 2010-10-01 2010-10-01 false Accident reports. 229.17 Section 229.17..., DEPARTMENT OF TRANSPORTATION RAILROAD LOCOMOTIVE SAFETY STANDARDS General § 229.17 Accident reports. (a)...

  4. How to reduce the number of accidents

    2012-01-01

    Among the safety objectives that the Director-General has established for CERN in 2012 is a reduction in the number of workplace accidents.   The best way to prevent workplace accidents is to learn from experience. This is why any accident, fire, instance of pollution, or even a near-miss, should be reported using the EDH form that can be found here. All accident reports are followed up. The departments investigate all accidents that result in sick leave, as well as all the more common categories of accidents at CERN, essentially falls (slipping, falling on stairs, etc.), regardless of whether or not they lead to sick leave. By studying the accident causes that come to light in this way, it is possible to take preventive action to avoid such accidents in the future. If you have any questions, the HSE Unit will be happy to answer them. Contact us at safety-general@cern.ch. HSE Unit

  5. Lessons of the radiological accident in Goiania

    On the basis of the lessons teamed from the radiological accident of Goiania, actions are described which a nuclear regulatory body should undertake while responding to an accident of this nature. (author)

  6. Traffic accident with radioactive material

    A traffic accident with a package with radioactive contents of the category 'III-YELLOW' remaining undamaged, caused complete confusion among the responsible rescue services. All forces active until professional fire-brigades arrived showed a deficit of tactical radiation protection behaviour. Even a medical unit with an equipped emergency task force in situ and radiation protection equipment did not feel responsible. (DG)

  7. Accident consequence assessment code development

    This paper describes the new computer code system, OSCAAR developed for off-site consequence assessment of a potential nuclear accident. OSCAAR consists of several modules which have modeling capabilities in atmospheric transport, foodchain transport, dosimetry, emergency response and radiological health effects. The major modules of the consequence assessment code are described, highlighting the validation and verification of the models. (author)

  8. Consequences of the Chernobyl accident

    A collection of three papers about the fallout in Austria from the 1986 Chernobyl reactor accident is given: 1. An overview of the research projects in Austria; 2. On the transfer into and uptake by crops and animal fodder; 3. On the reduction of cesium concentration in food. 18 tabs., 21 figs., 69 refs

  9. Standby after the Chernobyl accident

    The report is an investigation concerning strandby and actions by SKI (Swedish Nuclear Power Inspectorate) and SSI (National Institute of Radiation Protection) due to the Chernobyl reactor accident. It consists of a final report and two appendices. The final report is divided into two parts: 'I: Facts' and 'II: Analyzes'. 'Facts': The Swedish model for information: radio, press. Basic knowledge about ionizing radiation in the society. Resources for information. Need for information. Message forms for information. Announcements from the authorities in TV, radio, press, meeting, advertisements. Statements concerning the reactor accident and its consequences in Swedish mass media. How did the public recieve the information? 'Analyzis': Information responsibilities and policies. SSI information activities concerning radiologic accidents, conditions, methods and resources. Ditto for SKI, Swedish National Food Administration and the National Board of Agriculture. Appendix I: Information from authorities in the press three weeks after the Chernobyl accident: The material and the methods. The acute phase, the adoptation phase, the extension of the persective. What is said about the authorities in connection with Chernobyl? Appendix II: The fallout from Chernobyl, the authorities and the media coverage: The nationwide, regional and local coverage from radio and television. Ditto from the press. Topic and problem areas in reporting. Instructions from the authorities in media. Contribution in the media from people representing the authorities. Fallout in a chronologic perspective. (L.F.)

  10. Consequences of radioactive releases into the sea resulting from the accident at the Fukushima Dai-ichi nuclear power plant - Evolution of expert investigation according to the data available

    Laguionie, Philippe; Bailly du Bois, Pascal; Boust, D.; Fievet, B.; Garreau, Pierre; Connan, O.; Charmasson, Sabine; Arnaud, M; Duffa, Celine; Champion, D.

    2012-01-01

    The accident at the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) in March 2011 led to an unprecedented direct input of artificial radioactivity into the marine environment. The Institute for Radioprotection and Nuclear Safety was requested by the French authorities to investigate the radioecological impact of this input, in particular the potential contamination of products of marine origin used for human consumption. This article describes the close link between the responses provided and ...

  11. Trismus: An unusual presentation following road accident

    Thakur Jagdeep

    2007-01-01

    Full Text Available Trismus due to trauma usually follows road accidents leading to massive faciomaxillary injury. In the literature there is no report of a foreign body causing trismus following a road accident, this rare case is an exception. We present a case of isolated presentation of trismus following a road accident. This case report stresses on the thorough evaluation of patients presenting with trismus following a road accident.

  12. Heat and fluid flow in accident of Fukushima Daiichi Nuclear Power Plant, Unit 2. Accident scenario based on thermodynamic model

    An accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 2 is analyzed from the data open to the public. Phase equilibrium process model was introduced that the vapor and water are at saturation point in the vessels. Proposed accident scenario agrees very well with the data of the plant parameters obtained just after the accident. The estimation describes that the rupture time of the reactor pressure vessel (RPV) was at 22:50 14/3/2011. The estimation shows that the rupture time of the pressure containment vessel (RCP) was at 7:40 15/3/2011. These estimations are different from the ones by TEPCO, however; many measured evidences show good accordance with the present scenario. (author)

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

    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

  14. SEASONAL VARIATION OF ROAD TRAFFIC ACCIDENTS IN THE CITY OF KRASNODAR

    Pogorelov A. V.

    2013-11-01

    Full Text Available The article reviews some aspects of the seasonal variation of road accidents in the city of Krasnodar on the extensive statistical data (2001-2011. The regularities of the temporal variability of the road accidents, as well as their factors are shown

  15. Video-recorded accidents conflicts and road user behaviour: A step forward in traffic safety research

    Horst, A.R.A. van der

    2013-01-01

    TNO conducted long-term video observations to collect data on the pre-crash phase of real accidents (what exactly happened just before the collision?). The video recordings of collisions were used to evaluate and validate the safety value of in-depth accident analyses, road scene analyses, and behav

  16. Occupational accidents in the Danish merchant fleet and the nationality of seafarers

    Ádám, Balázs; Rasmussen, Hanna Barbara; Nørgaard Fløe Pedersen, Randi;

    2014-01-01

    Background: The aim of the study was to examine occupational accidents reported from non-passenger merchant ships registered in the Danish International Ship Register in 2010-2012, with a focus on analysing nationality differences in the risk of getting injured in an accident. Methods: Data about...

  17. Do Blue Laws Save Lives? The Effect of Sunday Alcohol Sales Bans on Fatal Vehicle Accidents

    Lovenheim, Michael F.; Steefel, Daniel P.

    2011-01-01

    This paper analyzes the effect of state-level Sunday alcohol sales restrictions ("blue laws") on fatal vehicle accidents, which is an important parameter in assessing the desirability of these laws. Using a panel data set of all fatal vehicle accidents in the U.S. between 1990 and 2009 combined with 15 state repeals of blue laws, we show that…

  18. 48 CFR 636.513 - Accident prevention.

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Accident prevention. 636... CONTRACTING CONSTRUCTION AND ARCHITECT-ENGINEER CONTRACTS Contract Clauses 636.513 Accident prevention. (a) In... contracting activities shall insert DOSAR 652.236-70, Accident Prevention, in lieu of FAR clause...

  19. 48 CFR 836.513 - Accident prevention.

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Accident prevention. 836... prevention. The contracting officer must insert the clause at 852.236-87, Accident Prevention, in solicitations and contracts for construction that contain the clause at FAR 52.236-13, Accident Prevention....

  20. 48 CFR 1836.513 - Accident prevention.

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Accident prevention. 1836... 1836.513 Accident prevention. The contracting officer must insert the clause at 1852.223-70, Safety and Health, in lieu of FAR clause 52.236-13, Accident Prevention, and its Alternate I....