WorldWideScience

Sample records for accident types

  1. The influence of accident measures on accident scenarios for VVER-1000-Type reactors

    For VVER-1000-type reactors severe accident scenarios and possible mitigation strategies are investigated. The Station blackout sequence is chosen as reference case. At first a comparison between the cases with and without working spray systems is discussed. Afterwards the results of a parametric study investigating the influence of different water volumes on the course of the accident are presented. It can be shown that most of these accident mitigation measures will maintain the containment integrity and reduce the source term. (author)

  2. Investigation of accident management strategies for VVER-1000-Type reactors

    The goal of this work is the search for an optimal accident management strategy to prevent containment failure and to stop the core/concrete interaction from hindering cavity bottom melt-through on the one hand and from ending the ex-vessel source term increase on the other hand, i.e., to terminate the accident. The work is based on the results of previous studies of physical and chemical phenomena during different accident scenarios for VVER-1000-type reactors. For a TMLB' sequence (an accident caused by a transient in which core melt occurs because the electric power cannot be restored before the pressure vessel melts through), a number of calculations were performed using the source term code package (STCP) to investigate the influence of several accident management measures on the core/concrete interaction and the containment integrity

  3. Serious accidents of PWR type reactors for power generation

    This document presents the great lines of current knowledge on serious accidents relative to PWR type reactors. First, is exposed the physics of PWR type reactor core meltdown and the possible failure modes of the containment building in such a case. Then, are presented the dispositions implemented with regards to such accidents in France, particularly the pragmatic approach that prevails for the already built reactors. Then, the document tackles the case of the European pressurized reactor (E.P.R.), for which the dimensioning takes into account explicitly serious accidents: it is a question of objectives conception and their respect must be the object of a strict demonstration, by taking into account uncertainties. (N.C.)

  4. Safety Approach of BORAX Type Accidents in French Research Reactors

    Most of pool type French research reactors are designed to withstand an explosive BORAX accident, defined as a pressure load on the pool walls. The purpose of this paper is to present the approach implemented at IRSN to analyse this accident by linking safety assessment and supporting studies. Examples of recent work on Jules Horowitz Reactor (JHR) and ORPHEE will be presented. Although all aspects of the accident are addressed, we will focus on the first two frames of the transient: the reactivity insertion and the consequences on the core. The first step of the BORAX analysis is to identify the most penalizing plausible reactivity insertion. This means characterising the sequences of events that can induce a reactivity surge and evaluate the worth of such variation. Neutronic computations are then required to quantify the reactivity increase. To comply with the geometrical specificities of research reactors, IRSN chose to use the homemade Monte Carlo code MORET5. The control rod worth calculations on the JHR were in good agreement with the operator results, whereas in ORPHEE, IRSN demonstrated that the beam channels reactivity worth was largely. In both cases the obtained results allowed an interesting dialogue with the operator and were used in the conclusions of the safety assessment. Following the accidental sequence of events, the second stage analysed by IRSN is the power transient occurring in the core and the consequences on the fuel. IRSN applied on JHR a homemade simplified model based on point kinetics and standard thermal balance equations to compute power evolution taking into account the temperatures of the fuel for feedback reactivity. As heat exchange coefficients between cladding and water for such fast transients are unknown, IRSN took the conservative hypothesis of adiabatic heating of the plates. The comparison the JHR power pulse calculation results against SPERT experimental measurements enabled IRSN to be optimistic about the possibility

  5. Phenomenology of severe accidents in BWR type reactors. First part

    A Severe Accident in a nuclear power plant is a deviation from its normal operating conditions, resulting in substantial damage to the core and, potentially, the release of fission products. Although the occurrence of a Severe Accident on a nuclear power plant is a low probability event, due to the multiple safety systems and strict safety regulations applied since plant design and during operation, Severe Accident Analysis is performed as a safety proactive activity. Nuclear Power Plant Severe Accident Analysis is of great benefit for safety studies, training and accident management, among other applications. This work describes and summarizes some of the most important phenomena in Severe Accident field and briefly illustrates its potential use based on the results of two generic simulations. Equally important and abundant as those here presented, fission product transport and retention phenomena are deferred to a complementary work. (Author)

  6. Beyond designed functional margins in CANDU type NPP. Radioactive nuclei assessment in an LOCA type accident

    Budu Andrei Razvan

    2015-01-01

    Full Text Available European Union's energy roadmap up to year 2050 states that in order to have an efficient and sustainable economy, with minimum or decreasing greenhouse gas emissions, along with use of renewable resources, each constituent state has the option for nuclear energy production as one desirable option. Every scenario considered for tackling climate change issues, along with security of supply positions the nuclear energy as a recommended option, an option that is highly competitive with respect to others. Nuclear energy, along with other renewable power sources are considered to be the main pillars in the energy sector for greenhouse gas emission mitigation at European level. European Union considers that nuclear energy must be treated as a highly recommended option since it can contribute to security of energy supply. Romania showed excellent track-records in operating in a safe and economically sound manner of Cernavoda NPP Units 1&2. Both Units are in top 10 worldwide in terms of capacity factor. Due to Romania's need to ensure the security of electricity supply, to meet the environmental targets and to move to low carbon generation technologies, Cernavoda Units 3&4 Project appears as a must. This Project was started in 2010 and it is expected to have the Units running by 2025. Cost effective and safety operation of a Nuclear Power Plant is made taking into consideration functional limits of its equipment. As common practice, every nuclear reactor type (technology used is tested according to the worse credible accident or equipment failure that can occur. For CANDU type reactor, this is a Loss of Cooling Accident (LOCA. In a LOCA type accident in a CANDU NPP, using RELAP/SCDAP code for fuel bundle damage assessment the radioactive nuclei are to be quantified. Recently, CANDU type NPP accidents are studied using the RELAP/SCDAP code only. The code formerly developed for PWR type reactors was adapted for the CANDU geometry and can assess the

  7. "Dual causation accident": a third type of work-related accident and its importance for occupational health surveillance

    Lenz Alberto Alves Cabral

    2014-12-01

    Full Text Available The scope of this study is to contribute to the improvement of Occupational Health Surveillance in the Unified Health System (UHS, through the recognition and inclusion of a third type of work-related accident in the current Brazilian legislation classification: the dual causation accident. This classification aims at facilitating the establishment of a causal connection, thus broadening the understanding of the relationship between work process and the production of diseases. It also aims at improving legal rules to protect the health of workers. This approach, besides enabling the identification of sentinel events (starting point of surveillance activities, might contribute not only to a decrease in underreporting of work-related accidents, but also to the uniformity of concepts and the implementation of integrated actions of the National Social Security Institute (NISS, the UHS, the Ministry of Labor (MLE and the Judiciary for the protection of workers. To propose a third type of occupational accident, a study of occupational accidents and causes of underreporting was conducted, with reference to the Brazilian labor legislation in the context of the National Policy on Occupational Health and the UHS.

  8. Cerebrovascular accidents in patients with type 2 diabetes mellitus

    S V Kakorin

    2013-03-01

    Full Text Available Cerebrovascular accident (CA is a nowadays widely spread, highly incapacitating and often lethal event that poses a prominent clini- cal problem. Cardiovascular disease (CVD and type 2 diabetes mellitus (T2DM – an “epidemic” of the century, – are known to be its primary risk factors. Hyperglycemia promotes CA risks by induction of protein glycosylation, elevation of blood plasma atherogenic potential, activation of coagulation system with higher risk for thrombosis and disturbance of microcirculation on tissue and organ lev- els. Influence of hyperglycemia on severity and extent of neurologic damage is still under evaluation. Development of macroangiopathy is thought to be associated with media calcification, distal polyneuropathy and renal disorders, all of which are cardiovascular risk factors. Application of so-called metabolic drugs resulted in certain disillusionment, as these agents failed to prove their efficacy during clinical trials. Incidence of pulmonary edema in patients with ischemic CA and T2DM is important as it dictates the necessity for use of loop diuretics. Incidence and severity of heart failure and its correlation with degree of glycemic disorders, incidence of pulmonary em- bolism, as well as tactics of management and prognosis in patients with ischemic CA and T2DM, remains a relevant research problem.

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

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

  10. Consideration of BORAX-type reactivity accidents applied to research reactors; Prise en compte des accidents de type 'BORAX' pour les reacteurs de recherche

    Couturier, Jean; Meignen, Renaud; Bourgois, Thierry; Biaut, Guillaume; Mireau, Jean-Pierre [Direction de la surete des reacteurs, Institut de Radioprotection et de Surete Nucleaire - IRSN, 31, avenue de la Division Leclerc, 92260 Fontenay-aux-Roses (France); Natta, Marc [Direction de la strategie, du developpement et des partenariats, Institut de Radioprotection et de Surete Nucleaire - IRSN, 31, avenue de la Division Leclerc, 92260 Fontenay-aux-Roses (France)

    2011-08-08

    Most of the research reactors discussed in this document are pool-type reactors in which the reactor vessel and some of the reactor coolant systems are located in a pool of water. These reactors generally use fuel in plate assemblies formed by a compact layer of uranium (or U{sub 3}Si{sub 2}) and aluminium particles, sandwiched between two thin layers of aluminium serving as cladding. The fuel melting process begins at 660 deg. C when the aluminium melts, while the uranium (or U{sub 3}Si{sub 2}) particles may remain solid. The accident that occurred in the American SL-1 reactor in 1961, together with tests carried out in the United States as of 1954 in the BORAX-1 reactor and then, in 1962, in the SPERT-1 reactor, showed that a sudden substantial addition of reactivity in this type of reactor could lead to explosive mechanisms caused by degradation, or even fast meltdown, of part of the reactor core. This is what is known as a 'BORAX-type' accident. The aim of this document is first to briefly recall the circumstances of the SL-1 reactor accident, the lessons learned, how this operational feedback has been factored into the design of various research reactors around the world and, second, to describe the approach taken by France with regard to this type of accident and how, led by IRSN, this approach has evolved in the last decade. (authors)

  11. Influence of accident management strategies on source terms of VVER-1000-type reactors

    The source term can be mitigated by effective accident management. The goal of this work is the investigation of the influence of a number of accident management strategies on the source term of a VVER-1000-type reactor. This work is one of a series of studies investigating the behavior of a VVER-1000-type reactor during severe accidents. In particular, it is based on the study in which the pressure rise in the containment and the melt-through of the cavity bottom was investigated, indicating potential mitigation strategies. To rate the usefulness of these strategies, the source terms of selected scenarios are also calculated in the present work. All the calculations were performed using the Source Term Code Package; hydrogen explosions are not considered. For the first time, the source term behavior of these scenarios was simulated up to the very end of the accident the solidification of the melt

  12. Risk factors affecting fatal bus accident severity: Their impact on different types of bus drivers.

    Feng, Shumin; Li, Zhenning; Ci, Yusheng; Zhang, Guohui

    2016-01-01

    While the bus is generally considered to be a relatively safe means of transportation, the property losses and casualties caused by bus accidents, especially fatal ones, are far from negligible. The reasons for a driver to incur fatalities are different in each case, and it is essential to discover the underlying risk factors of bus fatality severity for different types of drivers in order to improve bus safety. The current study investigates the underlying risk factors of fatal bus accident severity to different types of drivers in the U.S. by estimating an ordered logistic model. Data for the analysis are retrieved from the Buses Involved in Fatal Accidents (BIFA) database from the USA for the years 2006-2010. Accidents are divided into three levels by counting their equivalent fatalities, and the drivers are classified into three clusters by the K-means cluster analysis. The analysis shows that some risk factors have the same impact on different types of drivers, they are: (a) season; (b) day of week; (c) time period; (d) number of vehicles involved; (e) land use; (f) manner of collision; (g) speed limit; (h) snow or ice surface condition; (i) school bus; (j) bus type and seating capacity; (k) driver's age; (l) driver's gender; (m) risky behaviors; and (n) restraint system. Results also show that some risk factors only have impact on the "young and elder drivers with history of traffic violations", they are: (a) section type; (b) number of lanes per direction; (c) roadway profile; (d) wet road surface; and (e) cyclist-bus accident. Notably, history of traffic violations has different impact on different types of bus drivers. PMID:26513334

  13. Consideration of BORAX-type reactivity accidents applied to research reactors

    Most of the research reactors discussed in this document are pool-type reactors in which the reactor vessel and some of the reactor coolant systems are located in a pool of water. These reactors generally use fuel in plate assemblies formed by a compact layer of uranium (or U3Si2) and aluminium particles, sandwiched between two thin layers of aluminium serving as cladding. The fuel melting process begins at 660 deg. C when the aluminium melts, while the uranium (or U3Si2) particles may remain solid. The accident that occurred in the American SL-1 reactor in 1961, together with tests carried out in the United States as of 1954 in the BORAX-1 reactor and then, in 1962, in the SPERT-1 reactor, showed that a sudden substantial addition of reactivity in this type of reactor could lead to explosive mechanisms caused by degradation, or even fast meltdown, of part of the reactor core. This is what is known as a 'BORAX-type' accident. The aim of this document is first to briefly recall the circumstances of the SL-1 reactor accident, the lessons learned, how this operational feedback has been factored into the design of various research reactors around the world and, second, to describe the approach taken by France with regard to this type of accident and how, led by IRSN, this approach has evolved in the last decade. (authors)

  14. Bubbling-vacuum system for accident localization in WWER-type NPP

    The system is intended for standard dual-cycle NPP of Soviet type. It ensures safety by reduction of the post-accident pressure in the corresponding sealed spaces. The system quarantees economy of the special fittings and preservation of the environment from the concequencies of the possible emergency operational modes of NPP. The system has an enhanced functional reliability which is reached by simplification and switching of the self-closed overflow reverse fittings. Installing of at least one vibration-acoustic detector ensures timely indication of small and comparatively frequent loss-of-coolant accidents. 2 claims, 1 fig

  15. Channel blockage accident analysis for research reactors with MTR- type fuel elements

    It is the purpose of this study to investigate the feasibility of removing the residual decay heat from core of TR-2 ,which is a pool-type research reactor, after a channel blockage accident event and to identify the principal factors involved in cooling process. To analyze this accident scenery, THEAP-I computer code, which is a single phase transient 3-D structure/1-D flow thermal hydraulics code developed with the aim to contribute mainly to the safety analysis of the open pool research reactors, was modified and used. All of the analysis results figured out the fact that the core melting was inevitable in case of an uninterrupted operation (continuous operation) preceding a channel blockage accident of the TR-2 Reactor. Such a result will even be met if the blockage occurs only in a single fuel element. The results of analysis are expressed in terms of temperature field distribution as a function of time

  16. Chemistry aspects of the source term formation for a severe accident in a CANDU type reactor

    Constantin, A.; Constantin, M. [Institute for Nuclear Research, Pitesti (Romania)

    2013-07-15

    The progression of a severe accident in a CANDU type reactor is slow because the core is surrounded by a large quantity of heavy and light water which acts as a heat sink to remove the decay heat. Therefore, the source term formation is a complex and long process involving fission products transport and releasing in the fuel matrix, thermal hydraulics of the transport fluid in the primary heat system and containment, deposition and transport of fission products, chemistry including the interaction with the dousing system, structural materials and paints, etc. The source term is strongly dependent on initial conditions and accident type. The paper presents chemistry aspects for a severe accident in a CANDU type reactor, in terms of the retention in the primary heat system. After releasing from the fuel elements, the fission products suffer a multitude of phenomena before they are partly transferred into the containment region. The most important species involved in the deposition were identified. At the same time, the influence of the break position in the transfer fractions from the primary heat system to the containment was investigated. (orig.)

  17. Source term and radiological consequence evaluation for nuclear accidents using a 'hand type' methodology

    In the last decades, hand type calculations have been replaced by computerized solutions, which are much more accurate, but the preparation of an input to run the code can be a time consuming process and can require a laborious work. This is why, a place for hand calculation based on nomograms still exist in some areas. An example is emergency response to an accidental release of radioactive contaminants when the health of persons close to the accident site might be at risk. In this case, results from computerized accident consequences assessment models may be delayed due to the equipment malfunction or the time required developing minimal input files and performing the calculations (typically more than five minutes). A simple nomogram (developed using computerized dispersion model calculations) can provide dispersion and dose estimates within a minute. The paper presents the methodology used for these 'hand type' calculation and the nomograms, figures and tables used to evaluate the dose to an individual close to the release point. In order to illustrate the use of methodology, a hypothetical severe accident scenario involving 14-MW INR-TRIGA research reactor was considered. (authors)

  18. Reactivity initiated accident (RIA) type tests and annular core pulse reactor (ACPR) operational experience

    This paper describes the test conducted to investigate the failure threshold of the fuel when subject to RIA, accomplished in the TRIGA ACPR Nuclear Research Institute, Pitesti. The reactor facility, the capsule used in experiments and the experimental results are presented. The failure threshold was determined at 200 cal/g for an atmospheric gap pressure comparable with similar tests. The failure threshold decreases with increasing gap pressure. The tests proved useful for a better understanding of the fuel behavior in the transient conditions. As it is known RIA is not a common accident for the CANDU reactors, but the fuel failure mechanism can be similar to other type of accidents as LOCA and PCM. The program will be continued, with better instrumentation for the fuel sample and also independent instrumentation to measure pulse characteristics with better statistics. A new project for the experimental fuel elements must be considered to eliminate fuel-endcap interactions. (author)

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

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

  20. Assessment of the radiological risks of road transport accidents involving Type A packages

    An assessment and evaluation of the potential radiological risks of transport accidents involving Type A package shipments by road have been performed by five EU Member States, France, Germany, Sweden, The Netherlands, and the UK. The analysis involved collection and analysis of information on a national basis related to the type, volume, and characteristics of Type A package consignments, the associated radioactive traffic, and the expected frequency and consequences of potential vehicular road transport accidents. It was found that the majority of Type A packaged radioactive material shipments by road is related to applications of non-special form radioactive material, i.e. radiopharmaceuticals, radiochemicals etc., in medicine, research, and industry and special form material contained in radiography and other radiation sources, e.g. gauging equipment. The annual volumes of Type A package shipments of radiopharmaceuticals and radiochemicals by road differ considerably between the participating EU Member States from about 12,000 Type A packages in Sweden to about 240,000 in the Netherlands. The broad range reflects to a large extent the supply of radioactive material for the national populations and the production and distribution operations prevailing in the participating EU Member States (some are producer countries, others are not!). Very few standard package designs weighing from about 1-25 kg are predominant in Type A package shipments in all participating countries. Type A packages contain typically a range of radioactivity from a few mega becquerels to a few tens of giga becquerels, the average package activity contents is in terms of fractions of A2 about 0.01, i.e. about one hundredth of a Type A package contents limits. Based on a probabilistic risk assessment method it has been concluded that the expected frequencies of occurrence of vehicular road transport accidents with the potential to result in an environmental release - including radiologically

  1. Loss Of Secondary coolant accident analysis for Pius type reactor using Relap5/MOD2

    Process inherent ultimate safety (Pius) reactor concept is a reactor concept that intrinsically based on passive safety. This reactor refer to Pressurized water reactor (PWR) wherein the primary system is submerged in a pool of poison water. the operating principle is to maintain the pressure balance, so that no inflow from pool to the primary system. On loss of secondary coolant accident, primary coolant temperature increases, it is followed by the increase of primary pump speed. When the upper limit is reached, the pump is tripped due to the pressure balance disturbance, poison water flows from pool to the primary system, then reactor shut down. this accident condition was simulated by experimental and numerical simulation using RELAP5/MOD2. Numerical simulation was done to the experimental apparatus nodalization that was set on the norm of RELAP5/MOD2. This nodalization consist of 119 volumes, 127 junctions, and 106 heat structures. Analysis was carried out using both experimental and numerical simulation results. it can be concluded that PIUS type reactor is able to anticipate loss of secondary coolant accident because its capability of self shut down

  2. The risk of an air accident as a result of a serious incident of the hybrid type

    Safety in air traffic is a multilayered concept and consists of many safety barriers. The practical side of increasing safety is mainly based on analysing the causes of accidents and incidents. This analysis leads to finding gaps in the safety structure and to developing corrective recommendations in order to eliminate them. In this paper we indicate that this practice is insufficient. Most incidents could transform into accidents with fatalities. The standard method of investigating incidents does not answer the question as to whether safety barrier is permanent or whether it was activated accidentally. This paper proposes a new method for analysing incidents aimed at finding their consequences rather than their causes. This makes it possible to find areas that need improvement. Stochastic, timed, coloured Petri nets were used for the analysis. There are three types of air traffic incidents, distinguished according to events that lead to a transformation of an incident into an accident: causal and temporal. The hybrid case, in which both types are important, has been discussed in detail. The method is useful in evaluating the current level of safety in air traffic. Applicability of this method has been shown on the example of the runway incursion problem. - Highlights: • Current accident investigation procedure is not sufficient. • New method aimed to study incident’s conversion into accident was proposed. • The Petri net model of air traffic accident was developed. • Method allows calculating accident probability. • The hybrid case in which both causal and temporal events are important is discussed

  3. Containment filter system for WWER type reactors in case of beyond design basis accident

    The papers presents a scheme of a filter design for WWER type reactors for the releasing of the pressurized vapour-air mixture from the containment and filtering of the radioactive products (fine particles and aerosols) in case of a beyond design basis accident,. The first main component of the filter is a bubbling type mixer where a condensations of the vapour component takes part and the non-condensed (air ) component has been filtered. Experiment have been performed for various values of the weight ratio between the steam and air components, corresponding to the conditions in case of a severe accident with a leakage in the containment. The tested bubbling mixer has 80 cm2 effective flow section. The results show a full vapour component condensation in case of an effective phase mixing. Analyses, made for the WWER-1000 reactors of the Kozloduy NPP, show that the expected vapour consumption can be assured by using of 1-3 parallel units. The second element of this unit - separator - consists of two elements - a demister, which presents a patch of metal wool separated by a metal net with a large effective section, and a droplets turbo-separator. The combination of a demister and turbo-separator can ensure up to 99.5% cleaning. The turbo-separator is tested is introduced in production with very good results

  4. Dose calculation for accident situations at TRIGA research reactor using LEU fuel type

    The 14 MW TRIGA R.R. is a unique design of TRIGA conception. The core was fully converted in May 2006 to use LEU fuel instead of the HEU fuel type. The core contains 29 fuel assemblies, 8 control rods and beryllium reflector, associated instrumentation and controls. The U-235 enrichment for TRIGA - HEU fuel is 93.15 wt % and for TRIGA - LEU is 40.00 wt %. The differences between the two fuel types, as shown by the calculations, will results in a higher core inventory especially for heavy elements (i.e. actinides and transuranium elements), but modifications for noble gases, halogens and other volatile fission products are not so important. Dose calculations for an hypothetical accident scenario was considered and dose and radiological consequence calculations were performed. The results of the calculations and a discussion related on the differences between the consequences in the two cases are also presented. (authors)

  5. Hydrogen combustion management during a severe accident at the plant with the ice condenser type containment

    Watada, M.; Furuta, T.; Ohtani, M. [Kansai Electric Power Co., Inc., Osaka (Japan); Ogino, M. [Mitsubishi Heavy Industry Co., Ltd., Yokohama (Japan)

    1997-03-01

    In Japan, hydrogen mitigation measures inside the containment vessel during a severe accident are taken against the plant with the ice condenser type containment. Ohi Power Station Unit No.1 and 2, which Kansai Electric Power Co.,Inc. owns, are the only plants of this kind in Japan. Kansai has investigated the hydrogen mitigation measures in collaboration with Mitsubishi Heavy Industry Co.,Ltd. As a result of extensive experiments and analyses, the glow plug type igniter was selected as a hydrogen mitigation device. Environmental conditions were investigated for the purpose of selection of the device. To decide the location of installation, Kansai performed analysis of mixing behavior of hydrogen focusing on the results of small scale combustion testing conducted by Nupec (Nuclear Power Engineering Corporation). This paper will introduce the detailed results of Kansai's investigation of hydrogen mitigation measures for Ohi Power Station Unit No.1 and 2. (author)

  6. Hydrogen combustion management during a severe accident at the plant with the ice condenser type containment

    In Japan, hydrogen mitigation measures inside the containment vessel during a severe accident are taken against the plant with the ice condenser type containment. Ohi Power Station Unit No.1 and 2, which Kansai Electric Power Co.,Inc. owns, are the only plants of this kind in Japan. Kansai has investigated the hydrogen mitigation measures in collaboration with Mitsubishi Heavy Industry Co.,Ltd. As a result of extensive experiments and analyses, the glow plug type igniter was selected as a hydrogen mitigation device. Environmental conditions were investigated for the purpose of selection of the device. To decide the location of installation, Kansai performed analysis of mixing behavior of hydrogen focusing on the results of small scale combustion testing conducted by Nupec (Nuclear Power Engineering Corporation). This paper will introduce the detailed results of Kansai's investigation of hydrogen mitigation measures for Ohi Power Station Unit No.1 and 2. (author)

  7. Clinical and metabolic features of type 2 diabetes mellitus in participants of Chernobyl accident clean-up

    The clinical and metabolic features of type 2 diabetes mellitus (DM) in the participants of Chernobyl accident clean-up (PCAC) was studied. It was found out that DM in PCAC was first diagnosed against a background of formed cardiovascular pathology and hyper coagulation

  8. Analysis of simulation results of damaged nuclear fuel accidents at NPPs with shell-type nuclear reactors

    Lessons from the accident at the Fukushima NPP made it necessary to reevaluate and intensificate the work on modeling and analyzing various scenarios of severe accidents with damage to the nuclear fuel in the reactor, containment and spent nuclear fuel storage pool with the expansion of the primary initiating event causes group listing. Further development of computational tools for modeling the explosion prevention criteria as to steam and gas mixtures, considering the specific thermal-hydrodynamic conditions and mechanisms of explosive situations arrival at different stages of a severe accident development, is substantiated. Based on the analysis of the known shell-type nuclear reactors accidents results the explosion safety thermodynamic criteria are presented, the parameters defining the steam and gas explosions conditions are found, the need to perform the further verification and validation of deterministic codes serving to simulate general accident processes behavior as well as phase-to-phase interaction calculated dependencies is established. The main parameters controlling and defining the criteria explosion safety effective regulation areas and their optimization conditions are found

  9. Analysis of simulation results of damaged nuclear fuel accidents at NPPs with shell-type nuclear reactors

    Igor L. Kozlov

    2015-03-01

    Full Text Available Lessons from the accident at the Fukushima Daiichi NPP made it necessary to reevaluate and intensificate the work on modeling and analyzing various scenarios of severe accidents with damage to the nuclear fuel in the reactor, containment and spent nuclear fuel storage pool with the expansion of the primary initiating event causes group listing. Further development of computational tools for modeling the explosion prevention criteria as to steam and gas mixtures, considering the specific thermal-hydrodynamic conditions and mechanisms of explosive situations arrival at different stages of a severe accident development, is substantiated. Based on the analysis of the known shell-type nuclear reactors accidents results the explosion safety thermodynamic criteria are presented, the parameters defining the steam and gas explosions conditions are found, the need to perform the further verification and validation of deterministic codes serving to simulate general accident processes behavior as well as phase-to-phase interaction calculated dependencies is established. The main parameters controlling and defining the criteria explosion safety effective regulation areas and their optimization conditions are found.

  10. Supplementary safety device in a system for accident localization at WWER-type NPP

    The device proposed consists in a circulation loop and an assembly for combustion and recombination of hydrogen. Its main advantage is possibility for retaining the secondary side with oxigen-free atmosphere before the accident as well as elimination of the possibility of ignition of post-accident atmosphere in the secondary side, which could lead to its decomposition and contamination of the environment. 1 cl., 2 figs

  11. Deterministic Analysis of a Beyond Design Basis Accident in a Low Power, Pin-Type Fuel Research Reactor

    Nagah Abdou, Hesham Mohammed [INVAP S. E., Bariloche (Argentina)

    2013-07-01

    A Beyond Design Basis Accident has been analyzed for a pool type research reactor with pin-type, Zry4 clad fuel. This is a low power research reactor (maximum power: 100kW) with neutron beam facilities. Two scenarios are considered: a neutron beam rapture that results in a fraction of the core submerged in water and a catastrophic failure that results in a fully uncovered core. The paper discusses the different cooling mechanisms for these two BDBAs and compares results for both scenarios, with predictions of no core damage in any situation. Core damage is defined as CHFR↔1.5 and/or Tclad→T start of breakaway oxidation temperature. In addition, the paper compares calculations with a thermalhydraulic code and an analytical model. This paper allows to analyze the applicability of regular thermalhydraulic codes to BDBA accident scenarios in low power research reactors.

  12. A Statistical Description of the Types and Severities of Accidents Involving Tractor Semi-Trailers, Updated Results for 1992-1996

    BLOWER,DANIEL F.; CLAUSS,DAVID B.

    1999-10-01

    This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. A previous study (SAND93-2580) reviewed the availability of accident data, identified the TIFA (Trucks Involved in Fatal Accidents) as the best source of accident data for accidents involving heavy trucks, and provided statistics on accident data collected between 1980 and 1990. The current study is an extension of the previous work and describes data collected for heavy truck accidents occurring between 1992 and 1996. The TIFA database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports and interviewing responders and witnesses for selected TEA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, effective fire temperature, fire size, fire separation, and fire duration.

  13. A Statistical Description of the Types and Severities of Accidents Involving Tractor Semi-Trailers, Updated Results for 1992-1996; TOPICAL

    This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. A previous study (SAND93-2580) reviewed the availability of accident data, identified the TIFA (Trucks Involved in Fatal Accidents) as the best source of accident data for accidents involving heavy trucks, and provided statistics on accident data collected between 1980 and 1990. The current study is an extension of the previous work and describes data collected for heavy truck accidents occurring between 1992 and 1996. The TIFA database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports and interviewing responders and witnesses for selected TEA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, effective fire temperature, fire size, fire separation, and fire duration

  14. 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.)

  15. Dose calculation for accident situations at WWR-S type spent nuclear fuel repository

    Full text: The Spent Nuclear Fuel Repository at IFIN-HH Bucharest (SNFR IFIN-HH) consists in four pools, repository hall, radiological monitoring system, ventilation system and auxiliary systems. At the moment the remaining activity in the repository is about 3500 Ci. Despite of the small activity, for emergency preparedness purposes, several accident scenarios, with a non zero probability of occurrence during the repository lifetime, have been postulated. Evaluations of radiological consequences to personnel, general public and environment, for each accident scenario have been performed. The radioactive inventory was evaluated with ORIGEN code from SCALE computer code system and radiological consequences were evaluated with COSYMA computer code. Assumptions for the source term determination, meteorological conditions and release, are presented. The calculated values of doses and risk are also presented. The impact of these accident scenarios on population and environment is also discussed. (authors)

  16. Bubbling-vacuum installation for accident localization in standard NPP with two WWER-type reactors

    The present installation enchances the efficiency and safety in the elimination of the accident concequencies, as well as the efficiency of the dual-cycle NPP with 2x440 PWR. It is proposed to use only the volume of the usable part of the secondary circuit, e.g., the air chambers. The maximum accident superfluous pressure in the secondary side (linked air chambers) is reduced. The reduction of the superfluous pressure correspond to the reduced total amount of radioactive effluents and to reduction of radioactive burden in tne NPP environment. 2 cls., 2 figs

  17. Probabilistic methods for identification of significant accident sequences in loop-type LMFBRs

    The aim of the Probabilistic Accident Progression Analysis (PAPA) described herein is to establish a framework for better use of the probability measure; first, as a basis for deterministic calculations, and second, as a part of a comprehensive method for risk assessment in its own right. The achievement of this goal rests on: (1) improvements in the existing approaches for acquisition and analysis of accident sequences; (2) defining a new measure of probabilistic importance that aids in the ranking of sequences of highly uncertain events; and (3) implementation of new techniques for quantification of dependent failures of similar components. The existing techniques related to the above three topics are discussed and the state of the art is reviewed. The PAPA approach is described. The techniques of PAPA are applied to a class of Protected Transients (transients in which the reactor is successfully shutdown) in the Clinch River Breeder Reactor Plant (CRBRP). The results of the application of these techniques are described

  18. Probabilistic methods for identification of significant accident sequences in loop-type LMFBRs

    Jamali, K M.A.

    1983-06-01

    The aim of the Probabilistic Accident Progression Analysis (PAPA) described herein is to establish a framework for better use of the probability measure; first, as a basis for deterministic calculations, and second, as a part of a comprehensive method for risk assessment in its own right. The achievement of this goal rests on: (1) improvements in the existing approaches for acquisition and analysis of accident sequences; (2) defining a new measure of probabilistic importance that aids in the ranking of sequences of highly uncertain events; and (3) implementation of new techniques for quantification of dependent failures of similar components. The existing techniques related to the above three topics are discussed and the state of the art is reviewed. The PAPA approach is described. The techniques of PAPA are applied to a class of Protected Transients (transients in which the reactor is successfully shutdown) in the Clinch River Breeder Reactor Plant (CRBRP). The results of the application of these techniques are described.

  19. Analysis of the source term formation in a severe accident initiated by end fitting failure in CANDU type reactors

    Constantin, Marin; Constantin, Alina; Apostol, Minodora [Institute for Nuclear Research, Pitesti (Romania)

    2014-04-15

    CANDU type reactors have some peculiarities in initiation and progression of severe accidents. In the present paper one of the specificities - the End Fitting Failure accident - is analysed from the point of view of source term formation. The accident is initiated by a failure of the re-fueling machine. Fuel bundles are ejected in the re-fuelling machine room and fuel elements suffer a significant fragmentation by mechanical impact and by the rapid increase of the temperature. A direct transfer of the fission products occurs directly to the containment. The source term in the containment and also the source term to the environment is calculated supposing an open venting communication to the external atmosphere. The simulation is performed by using the ASTEC code in coupled calculation CPA-IODE-ISODOPE-DOSE option. The evolution of the distributions for the most important released fission products is presented for different regions and for different hosts. The most important factors of influence on the source term formation are identified and discussed. (orig.)

  20. Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

    Highlights: • The number of failing fuel rods in a LB-LOCA in an EPR is evaluated. • 59 scenarios are simulated with the system code APROS. • 1000 rods per scenario are simulated with the fuel performance code FRAPTRAN-GENFLO. • All the rods in the reactor are simulated in the worst scenario. • Results suggest that the regulations set by the Finnish safety authority are met. - Abstract: In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks’ formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance – thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks’ formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail)

  1. A model for the analysis of loss of decay heat removal accident in MTR pool type research reactors

    During a loss of coolant accident leading to total emptying of the reactor pool, the decay heat could be removed through air natural convection. However, under partial pool emptying the core is partially submerged and the coolant circulation inside the fuel element could no more be possible. In such conditions, a core overheat take place, and the heat is essentially diffused from the core to its periphery by combined thermal radiation and conduction. In order to predict fuel element temperature evolution under such conditions a mathematical model is performed. The model is based on a three dimensional geometry and takes into account a variety of core configurations including fuel elements (standard and control), reflector elements and grid plates. The homogeneous flow model is used and the time and space dependent non-linear partial differential fluid conservation equations are solved using a semi-implicit finite difference method. Preliminary tests of the developed model were made by considering a series of hypothetical accidents. In the current framework a loss of decay heat removal accidents in the IAEA benchmark open pool MTR-type research reactor is considered. It is shown that in the case of a low core immersion height no water boiling is observed and the fuel surface temperature rise remains below the melting point of the aluminium cladding. (author)

  2. Modeling in fast dynamics of accidents in the primary circuit of PWR type reactors

    Two kinds of accidents, liable to occur in the primary circuit of a Pressurized Water Reactor and involving fast dynamic phenomena, are analyzed. The Loss Of Coolant Accident (LOCA) is the accident used to define the current PWR. It consists in a large-size break located in a pipe of the primary circuit. A blowdown wave propagates through the circuit. The pressure differences between the different zones of the reactor induce high stresses in the structures of the lower head and may degrade the reactor core. The primary circuit starts emptying from the break opening. Pressure decreases very quickly, involving a large steaming. Two thermal-hydraulic simulations of the blowdown phase of a LOCA are computed with the Europlexus code. The primary circuit is represented by a pipe-model including the hydraulic peculiarities of the circuit. The main differences between both computations concern the kind of reactor, the break location and model, and the initialization of the accidental operation. Steam explosion is a hypothetical severe accident liable to happen after a core melting. The molten part of the core (called corium) falls in the lower part of the reactor. The interaction between the hot corium and the cold water remaining at the bottom of the vessel induces a massive and violent vaporization of water, similar to an explosive phenomenon. A shock wave propagates in the vessel. what can damage seriously the neighbouring structures or drill the vessel. This work presents a synthesis of in-vessel parametrical studies carried out with the Europlexus code, the linkage of the thermal-hydraulic code Mc3d dedicated to the pre-mixing phase with the Europlexus code dealing with the explosion, and finally a benchmark between the Cigalon and Europlexus codes relative to the Vulcano mock-up. (author)

  3. Radiation risk models for all solid cancers other than those types of cancer requiring individual assessments after a nuclear accident.

    Walsh, Linda; Zhang, Wei

    2016-03-01

    In the assessment of health risks after nuclear accidents, some health consequences require special attention. For example, in their 2013 report on health risk assessment after the Fukushima nuclear accident, the World Health Organisation (WHO) panel of experts considered risks of breast cancer, thyroid cancer and leukaemia. For these specific cancer types, use was made of already published excess relative risk (ERR) and excess absolute risk (EAR) models for radiation-related cancer incidence fitted to the epidemiological data from the Japanese A-bomb Life Span Study (LSS). However, it was also considered important to assess all other types of solid cancer together and the WHO, in their above-mentioned report, stated "No model to calculate the risk for all other solid cancer excluding breast and thyroid cancer risks is available from the LSS data". Applying the LSS models for all solid cancers along with the models for the specific sites means that some cancers have an overlap in the risk evaluations. Thus, calculating the total solid cancer risk plus the breast cancer risk plus the thyroid cancer risk can overestimate the total risk by several per cent. Therefore, the purpose of this paper was to publish the required models for all other solid cancers, i.e. all solid cancers other than those types of cancer requiring special attention after a nuclear accident. The new models presented here have been fitted to the same LSS data set from which the risks provided by the WHO were derived. Although it is known already that the EAR and ERR effect modifications by sex are statistically significant for the outcome "all solid cancer", it is shown here that sex modification is not statistically significant for the outcome "all solid cancer other than thyroid and breast cancer". It is also shown here that the sex-averaged solid cancer risks with and without the sex modification are very similar once breast and thyroid cancers are factored out. Some other notable model

  4. Sudden unexpected death due to Chiari type I malformation in a road accident case.

    Zhang, Jianhua; Shao, Yu; Qin, Zhiqiang; Liu, Ningguo; Zou, Donghua; Huang, Ping; Chen, Yijiu

    2013-03-01

    This case concerns a sudden death of a patient with Chiari I malformation. A 17-year-old female was seen unconscious then fell off a motorbike during the vehicle acceleration. The girl was confirmed dead on the way to hospital, being previously asymptomatic and with a clean medical record. Autopsy findings showed an extremely extra-long cerebellar tonsillar herniation in the left side and unexplained multiple small cavities in cerebral hemispheres. Microscopic findings revealed loss and abnormal migration of the Purkinje cells, as well as capillary congestion in the herniated tonsil. The cause and mechanisms of this sudden death are considered as the cardiopulmonary dysfunction and arrest resulted from compression of the medulla and cervical cord, which was induced by both the positional insult and minor head trauma. In addition, this study stresses the importance of cervical cord examination in the case of unexpected sudden death following road accidents. PMID:23278920

  5. R and D relative to the serious accidents in the PWR type reactors: assessment and perspectives

    This document presents the current state of the research relative to the grave accidents realized in France and abroad. It aims at giving the most exhaustive possible and objective vision of this original field of research. He allows to contribute to the identification and to the hierarchical organization of the needs of R and D, this hierarchical organization in front of, naturally, to be completed by a strong lighting on needs in terms of safety analyses associated with the different risks and the physical phenomena, in particular with the support of probability evaluations of safety level 2, whose the level of sharpness must be sufficient not to hide, by construction, physical phenomena of which the limited knowledge leads to important uncertainties. Let us note that neither the safety analyses, nor the E.P.S. 2 are presented in this document. This report presents the physical phenomena which can arise during a grave accident, in the reactor vessel and in the reactor containment, their chain and the means allowing to ease the effects. The corresponding scenarios are presented to the chapter 2. The chapter 3 is dedicated to the progress of the accident in the reactor vessel; the degradation of the core in reactor vessel (3.1), the behavior of the corium in bottom of reactor vessel (3.2) the break of the reactor vessel (3.3) and the fusion in pressure (3.4) are thus handled there. The chapter 4 concerns the phenomena which can lead to a premature failure of the containment, namely the direct heating of gases of the containment (4.1), the hydrogen risk (4.2) and the vapor explosion (4.3). The phenomenon which can lead to a delayed failure from the containment, namely the interaction corium-concrete, is approached on the chapter 5. The chapter 6 is dedicated to the problems connected to the keeping back and to the corium cooling in reactor vessel and out of reactor vessel, namely the keeping back in reactor vessel by re-flooding of the primary circuit or by re

  6. ALMOS-2 - computer program for accident analyses of BWR-type reactor plants. Pt. 1

    ALMOS-2 is a non-linear, one-dimensional digital computer program for accident analyses of boiling water reactor plants. The program is capable of calculating transients with large amplitude deviations from steady state conditions, such as pump failures, loss of heat sink, feedwater system failures, control rod malfunction and safety system failures. The program is a suitable tool for the analysis of Anticipated Transients Without Scram (ATWS). The model includes the reactor core, the main coolant system and the safety system. Boundary conditions to these systems can be defined as functions of time by input data. The program description includes a short introduction into the physical model, a presentation of the program structure and program components and a detailed input data description. For test purposes the results of a transient calculation are added. (orig.)

  7. 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.)

  8. Effect of expansion wave on WWER type reactor model in loss-of-coolant accident

    An experimental device was developed for the investigation of the effect of the expansion wave arising during a loss-of-coolant accident on a WWER pressure vessel model (1:8). The device enables a maximum pressure of 12 MPa to be achieved in the system. Water heating is provided by electrical heating to 270 degC at the outlet from the inlet vessel neck and 300 degC from the outlet neck. A total of 100 tests were performed with different outlet opening dimensions and different models of vessel internals fixed in various ways. The starting values mostly corresponded to those for WWER-440 reactors. The results of the experiments indicate a marked thermodynamic off-equilibrium of the process in the starting stage of the outflow and existence of a bonding between the internal structure and the coolant. A semiempirical relation was derived for determining the minimal pressure during the passage of the underpressure expansion wave front. Analysis of the mutual effects of the coolant hydrodynamics and the dynamics of the internals confirmed a dispersion nature of propagation of the exciting impulse in the model. (Z.M.). 4 figs., 3 refs

  9. 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

  10. 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)

  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. 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

  13. 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.

  14. Thermohydraulic analysis of loss of forced flow accident in a pool type reactor

    This paper shows a calculation model for the fuel and pool water temperatures, and the internal building pressure of a 5 MW pool-type reactor, in the hypothetical event of the forced flow interruption. it is obtained the solution of the thermal energy and the momentum conservation equations in one dimension, which represent the heat conduction and natural convection in the coolant. The reactor building pressure increment due to the partial pool water evaporation is also calculated, using a homogenous model with thermal equilibrium of the phases (liquid water and steam) and the existing air. The heat loss to the building walls is also considered. (Author)

  15. Analysis and model testing of Super Tiger Type B packaging in accident environments

    Based on previous scale model test results with more rigid systems and the subsystem tests on drums, it is believed that the scaled models realistically replicate full scale system behavior. Future work will be performed to obtain improved stiffness data on the Type A containers. These data will be incorporated into the finite element model, and improved correlation with the test results is expected. Review of the scale model transport system test results indicated that the method of attachment of the Super Tiger to the trailer was the primary cause for detachment of the outer door during the one-eighth scale grade-crossing test. Although the container seal on the scale model of Super Tiger was not adequately modeled to provide a leak-tight seal, loss of the existing seal in a full scale test can be inferred from the results of the one-quarter scale model grade-crossing test. In each test, approximately two-thirds of the model drums were estimated to have deformed sufficiently to predict loss of drum head closure seal, with several partially losing their contents within the overpack. In no case were drums ejected from the overpack, nor was there evidence of material loss in excess of the amount assumed in the WIPP EIS from any of the Super Tiger models tested. 9 figures

  16. Fuel gases generation in the primary contention during a coolant loss accident in a nuclear power plant with reactor type BWR

    During an accident design base of coolant loos, the hydrogen gas can accumulate inside the primary contention as a result of several generation mechanisms among those that are: 1) the reaction metal-water involving the zirconium of the fuel cladding and the reactor coolant, 2) the metals corrosion for the solutions used in the emergency cooling and dew of the contention, and 3) the radio-decomposition of the cooling solutions of post-accident emergency. In this work the contribution of each generation mechanism to the hydrogen total in the primary contention is analyzed, considering typical inventories of zirconium, zinc, aluminum and fission products in balance cycle of a reactor type BWR. In the analysis the distribution model of fission products and hydrogen production proposed in the regulator guide 1.7, Rev. 2 of the US NRC was used. The results indicate that the mechanism that more contributes to the hydrogen generation at the end of a period of 24 hours of initiate the accident is the radio-decomposition of the cooling solutions of post-accident emergency continued by the reaction metal-water involving the zirconium of the fuel cladding with the reactor coolant, and lastly the aluminum and zinc oxidation present in the primary contention. However, the reaction metal-water involving the zirconium of the fuel cladding and the reactor coolant is the mechanism that more contributes to the hydrogen generation in the first moments after the accident. This study constitutes the first part of the general analysis of the generation, transport and control of fuel gases in the primary contention during a coolant loss accident in BWRs. (Author)

  17. Analysis of simulation results of damaged nuclear fuel accidents at NPPs with shell-type nuclear reactors

    Igor L. Kozlov

    2015-01-01

    Lessons from the accident at the Fukushima Daiichi NPP made it necessary to reevaluate and intensificate the work on modeling and analyzing various scenarios of severe accidents with damage to the nuclear fuel in the reactor, containment and spent nuclear fuel storage pool with the expansion of the primary initiating event causes group listing. Further development of computational tools for modeling the explosion prevention criteria as to steam and gas mixtures, considering the specific therm...

  18. 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

  19. 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.

  20. RAPTA-5 code: Modelling behaviour of WWER-type fuel rods in design basis accidents verification calculations

    RAPTA-5 code used for licensing calculations to validate the compliance with the requirements for WWER fuel safety in design basis accidents. The characteristic results are given of design modelling experiments simulating thermomechanical and corrosion behaviour of WWER and PWR fuel rods in LOCA. The results corroborate the adequate predictability of both individual design models and the code as a whole. (author). 14 refs, 12 figs

  1. 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

  2. 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)

  3. PASLOCA: two-dimensional code for loss of primary coolant accident analysis in pool type reactors for use in micro computers

    In order to improve the better performance of the MILOCA code, a 2-dimensional code for Loss of Coolant Accident Analysis in pool type research reactor for use in IBM-PC, an adaptation of the code was made from FORTRAN to PASCAL. This paper presents also the heat transfer model calculation from the fuel elements to the air after the draining of the pool water. As an example, the analysis made for the IAEA 2 MW reference reactor is presented. Differences in computing time between the two versions are also shown. (author)

  4. Simulation of LOCA type accident for CANDU fuel in TRIGA materials testing reactor and its associated facilities at INR-Pitesti

    The specific objective of the experiment regards the simulation of a LOCA type accident in an irradiation facility in order to characterize the behaviour of a CANDU fuel element with respect to fuel-cladding interaction and fission product release in the case of clad failure occurrence. The work belongs to 'Nuclear Safety Program' contributing to computer codes qualification used for safety assessment of Cernavoda NPP. The experimental results of these tests will be used, among other input reference data, for evaluating the realistic safety limits for CANDU fuel element in case of anticipated transients. (Author)

  5. Possible pressurized thermal shock events during large primary to secondary leakage. The Hungarian AGNES project and PRISE accident scenarios in VVER-440/V213 type reactor

    Perneczky, L. [KFKI Atomic Energy Research Inst., Budabest (Hungary)

    1997-12-31

    Nuclear power plants of WWER-440/213-type have several special features. Consequently, the transient behaviour of such a reactor system should be different from the behaviour of the PWRs of western design. The opening of the steam generator (SG) collector cover, as a specific primary to secondary circuit leakage (PRISE) occurring in WWER-type reactors happened first time in Rovno NPP Unit I on January 22, 1982. Similar accident was studied in the framework of IAEA project RER/9/004 in 1987-88 using the RELAP4/mod6 code. The Hungarian AGNES (Advanced General and New Evaluation of Safety) project was performed in the period 1991-94 with the aim to reassess the safety of the Paks NPP using state-of-the-art techniques. The project comprised three type of analyses for the primary to secondary circuit leakages: Design Basis Accident (DBA) analyses, Pressurized Thermal Shock (PTS) study and deterministic analyses for Probabilistic Safety Analysis (PSA). Major part of the thermohydraulic analyses has been performed by the RELAP5/mod2.5/V251 code version with two input models. 32 refs.

  6. 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.)

  7. Safety criteria and guidelines for MSR accident analysis

    Accident analysis for Molten Salt Reactor (MSR) has been investigated at ORNL for MSRE in 1960s. Since then, safety criteria or guidelines have not been defined for MSR accident analysis. Regarding the safety criteria, the authors showed one proposal in this paper. In order to establish guidelines for MSR accident analysis, we have to investigate all possible accidents. In this paper, the authors describe the philosophy for accident analysis, and show 40 possible accidents. They are at first classified as external cause accidents and internal cause accidents. Since the former ones are generic accidents, we investigate only the latter ones, and categorize them to 4 types, such as power excursion accident, flow decrease accident, fuel-salt leak accident, and other accidents mostly specific to MSR. Each accident is described briefly, with some numerical results by the authors. (author)

  8. Contribution to the study of the release to the environment of radioactive iodine during an accident sequence type SGTR

    In a Steam Generator Tube Rupture (SGTR) accident occurring to a pressurised nuclear water reactor, a fraction of the radioactive species present in the primary circuit is likely to be transferred to the environment. Particular attention is paid to iodine for two reasons; the first one, it is well known that iodine is a high contributor to the dose at short term and in second, due to possible formation of volatile species, which could be largely sprayed in the environment. In normal operating conditions, the primary circuit is contaminated with some radioactive products flowing through micro-cracks existing in the fuel rod claddings. To better estimate the releases for SGTR sequence, it is crucial to determine the iodine partition between the gas and the liquid phase downstream the tube break as well as the droplet size distribution generated during the flashing. The first part of the PhD presents a heat and mass transfer model developed to predict the two-phase jet behaviour at the break. The steam fraction is calculated as well as the droplet size distribution upstream the break. Experiments available in the literature (tests conducted at the U.S/NRC and INERIS) are used to validate the model. The second part concerns the modelling of the iodine chemical speciation in the primary conditions (irradiation, low concentration and presence of impurities). For each iodine species, the partition coefficient has been determined either in using literature data or with the help of molecular dynamics computations. Last, this global release modelling has been implemented in ASTEC, the IRSN accident simulation software and the releases have been calculated for one SGTR scenario. (author)

  9. 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...

  10. 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).

  11. 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)

  12. 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)

  13. Isotope distributions in primary heat transport and containment systems during a severe accident in CANDU type reactor

    The paper is intended to analyse the distribution of the fission products (FPs) in CANDU Primary Heat Transport (PHT) and CANDU Containment Systems by using the ASTEC code. The complexity of the data required by ASTEC and the complexity both of CANDU PHT and Containment System were strong motivation to begin with a simplified model. The data related to the nodes' definitions, temperatures and pressure conditions were chosen as possible as real data from CANDU loss of coolant accident sequence (CATHENA code results). The source term of FPs introduced into the PHT was estimated by ORIGEN code. The FPs distribution in the nodes of the circuit and the FPs mass transfer per isotope and chemical species were obtained by using SOPHAEROS module. The distributions within the containment are obtained by the CPA module (thermalhydraulic calculations in the containment and FPs aerosol transport). The results consist of mass distributions in the nodes of the circuit and the transferred mass to the containment through the break for different species (FPs and chemical species) and mass distributions in the different parts of the containment and different hosts. (authors)

  14. Type A Accident Investigation Board report on the January 17, 1996, electrical accident with injury in Technical Area 21 Tritium Science and Fabrication Facility Los Alamos National Laboratory. Final report

    An electrical accident was investigated in which a crafts person received serious injuries as a result of coming into contact with a 13.2 kilovolt (kV) electrical cable in the basement of Building 209 in Technical Area 21 (TA-21-209) in the Tritium Science and Fabrication Facility (TSFF) at Los Alamos National Laboratory (LANL). In conducting its investigation, the Accident Investigation Board used various analytical techniques, including events and causal factor analysis, barrier analysis, change analysis, fault tree analysis, materials analysis, and root cause analysis. The board inspected the accident site, reviewed events surrounding the accident, conducted extensive interviews and document reviews, and performed causation analyses to determine the factors that contributed to the accident, including any management system deficiencies. Relevant management systems and factors that could have contributed to the accident were evaluated in accordance with the guiding principles of safety management identified by the Secretary of Energy in an October 1994 letter to the Defense Nuclear Facilities Safety Board and subsequently to Congress

  15. Type A Accident Investigation Board report on the January 17, 1996, electrical accident with injury in Technical Area 21 Tritium Science and Fabrication Facility Los Alamos National Laboratory. Final report

    NONE

    1996-04-01

    An electrical accident was investigated in which a crafts person received serious injuries as a result of coming into contact with a 13.2 kilovolt (kV) electrical cable in the basement of Building 209 in Technical Area 21 (TA-21-209) in the Tritium Science and Fabrication Facility (TSFF) at Los Alamos National Laboratory (LANL). In conducting its investigation, the Accident Investigation Board used various analytical techniques, including events and causal factor analysis, barrier analysis, change analysis, fault tree analysis, materials analysis, and root cause analysis. The board inspected the accident site, reviewed events surrounding the accident, conducted extensive interviews and document reviews, and performed causation analyses to determine the factors that contributed to the accident, including any management system deficiencies. Relevant management systems and factors that could have contributed to the accident were evaluated in accordance with the guiding principles of safety management identified by the Secretary of Energy in an October 1994 letter to the Defense Nuclear Facilities Safety Board and subsequently to Congress.

  16. [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

  17. 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

  18. 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.)

  19. Lizimetric investigation of vertical transportation of Cs-137 in the different soil types for the different raining conditions: a new solution proposal and application for the Chernobyl accident

    driven from experiments which were reached by classical model calculations harmonies well with the present results. Although the present results and the conclusion reached by classical model calculations harmonies, it is observed that there are important differences between them. The vertical transportation in soil was slower in the present experiments than the classical model calculations. As a reason of this difference, it can be showed that the darcy speed which is an ideal speed for soil that is used in the classical model calculation, doesn't agree with the realistic speed that can be changing according to soil type and characteristics. In order to avoid the important differences between the classical model calculation and present experimental results, a new solution for the semi infinite convection diffusional model is proposed in the originality of this Ph.D. thesis. In this proposal of water which is taken by the darcy speed is decreased by a value of the ratio of the migration coefficient to the darcy speed. The result obtained by our new solution proposal agrees quite well with our experimental result. The results that are reached by new solution proposal for different soil types and every raining regimes are harmonies with the sequence of our experiment. Meanwhile the conclusion that is reached for the different raining regime and every soil type also harmonies with the experimental results. As a result the conclusion that is reached in new solution proposal is suitable as ones in the classical model calculations to the experiment. If we compare the results with the experimental ones, we see that our new solution agrees better than the classical model results. Therefore new solution proposal that is the originality of this Ph.D. thesis more realistic than the classical model. Moreover this proposed solution is used to examine a realistic applicational case, that is the of the nuclear reactor accident in Chernobyl in 26 April 1986 which was occurred in Ukraine

  20. 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

  1. Specific features of RBMK severe accidents progression and approach to the accident management

    Fundamental construction features of the LWGR facilities (absence of common external containment shell, disintegrated circulation circuit and multichannel reactor core, positive vapor reactivity coefficient, high mass of thermally capacious graphite moderator) predetermining development of assumed heavy non-projected accidents and handling them are treated. Rating the categories of the reactor core damages for non-projected accidents and accident types producing specific grope of damages is given. Passing standard non-projected accidents, possible methods of attack accident consequences, as well as methods of calculated analysis of non-projected accidents are demonstrated

  2. Accumulation of 137Cs by rice grown in four types of soil contaminated by the Fukushima Dai-ichi Nuclear Power Plant accident in 2011 and 2012

    The ability to predict radiocesium transfer from soil to agricultural products is necessary for assessing management options in a radiocesium contaminated area. In this study, we evaluated the differences in transfer factors among soil samples and the differences in transfer factors between the first and the second years of contamination in rice. We employed pot experiments using four types of soils that are representative of the agricultural soils present in the Fukushima Prefecture contaminated by 137Cs released from the Fukushima Dai-ichi Nuclear Power Plant after the March 2011 accident. The experiments were conducted during the 2011 and 2012 growing seasons. The geometric mean of transfer factors for brown rice and inedible rice part was 0.011 and 0.031, respectively, in 2011 and 0.0061 and 0.020, respectively, in 2012. The average decreasing rate of the transfer factor was 40% and 30% in brown rice and inedible rice part, respectively, from 2011 to 2012, presumably owing to the irreversible sorption of 137Cs to clay minerals. - Highlights: • Rice was grown in the first and the second year from 137Cs contamination. • Transfer factor was measured for rice grown in four soils contaminated by 137Cs. • Decreasing rate of transfer factor was estimated to be 40% in brown rice

  3. 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

  4. Modeling in fast dynamics of accidents in the primary circuit of PWR type reactors; Modelisation en dynamique rapide d'accidents dans le circuit primaire des reacteurs a eau pressurisee

    Robbe, M.F

    2003-12-01

    Two kinds of accidents, liable to occur in the primary circuit of a Pressurized Water Reactor and involving fast dynamic phenomena, are analyzed. The Loss Of Coolant Accident (LOCA) is the accident used to define the current PWR. It consists in a large-size break located in a pipe of the primary circuit. A blowdown wave propagates through the circuit. The pressure differences between the different zones of the reactor induce high stresses in the structures of the lower head and may degrade the reactor core. The primary circuit starts emptying from the break opening. Pressure decreases very quickly, involving a large steaming. Two thermal-hydraulic simulations of the blowdown phase of a LOCA are computed with the Europlexus code. The primary circuit is represented by a pipe-model including the hydraulic peculiarities of the circuit. The main differences between both computations concern the kind of reactor, the break location and model, and the initialization of the accidental operation. Steam explosion is a hypothetical severe accident liable to happen after a core melting. The molten part of the core (called corium) falls in the lower part of the reactor. The interaction between the hot corium and the cold water remaining at the bottom of the vessel induces a massive and violent vaporization of water, similar to an explosive phenomenon. A shock wave propagates in the vessel. what can damage seriously the neighbouring structures or drill the vessel. This work presents a synthesis of in-vessel parametrical studies carried out with the Europlexus code, the linkage of the thermal-hydraulic code Mc3d dedicated to the pre-mixing phase with the Europlexus code dealing with the explosion, and finally a benchmark between the Cigalon and Europlexus codes relative to the Vulcano mock-up. (author)

  5. 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.

  6. 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...

  7. 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

  8. Small, long-life high temperature gas-cooled reactor free from prompt supercritical accidents by particle-type burnable poisons

    A design concept for a high temperature gas-cooled reactor without the possibility of a prompt supercritical accident has been proposed by coupling the use of particle-type burnable poison (BP) and criticality control by the core temperature. The combinations of two different BPs, B4C and Gd2O3 particles and B4C and CdO particles, with the proper particle sizes and the appropriate volume ratio, showed excellent performance in controlling excess reactivity and flattening the reactivity swing. To maintain reactivity at a lower level than the prompt critical state, the reactor was designed to operate in a subcritical mode for a burnup period or for the whole operation cycle. Under subcritical operation during the partial burnup period, the core temperature had to be lowered by at least 164 K for the loading of B4C + Gd2O3 particles and by at least 178 K for the B4C + CdO particles, which in turn dropped the thermal efficiency from 48% to 42.26% and 41.77%, respectively. On the other hand, under full subcritical operation, a greater decrease of core temperature was required. Remarkable decreases in the core temperatures, approximately 347 K for the B4C + Gd2O3 case and approximately 280 K for the B4C + CdO case, resulted in the drop of thermal efficiency to only 35.9% and 38.2%, respectively. Therefore, the relative importance of the increase in passive safety and the decrease in thermal efficiency must be considered with regard to their importance in nuclear reactor design. (author)

  9. Radiation Accident Experience: Causes and Lessons Learned

    Since inception of the nuclear energy program in the United States of America, the Atomic. Energy Commission (USAEC) has maintained an extensive system for the reporting and review of radiation accidents in USAEC federal and licensing activities. Accidents required to be reported fall-into two main categories: (1) Accidents causing or threatening to cause radiation exposure to industrial workers or to the general public; (2) Accidents causing damage to or shutdown of facilities, or damage to public property. While many of the reported accidents carry with them the potential for exposure of persons to radioactivity, the cases reported, in this analysis are limited to those where certain prescribed levels of exposure have been exceeded or where significant uptake by the critical organ has occurred. This paper presents detailed analyses of the accident experience encountered in USAEC programs over the past nine years, including: (1) A breakdown of the types of work activities in the nuclear industry under which radiation accidents have occurred; (2) Characterization of the causes of such accidents as related to the types of work activities; (3) Lessons to be learned both in avoiding such accidents and in emergency planning, should such accidents occur. (author)

  10. 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 ...

  11. Accident selection methodology for TA-55 FSAR

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

  12. 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

  13. 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.)

  14. 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)

  15. R and D relative to the serious accidents in the PWR type reactors: assessment and perspectives; R and D relative aux accidents graves dans les reacteurs a eau pressurisee: bilan et perspectives

    Bentaib, A.; Bonneville, H.; Caroli, H.; Chaumont, B.; Clement, B.; Cranga, M.; Koundy, V.; Laurent, B.; Micaelli, J.C.; Meignen, R.; Pichereau, F.; Plassart, D.; Van-Dorsselaere, P. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Ducros, G.; Journeau, Ch.; Magallon, D. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Durin, M.; Studer, E. [CEA Saclay 91 - Gif sur Yvette (France); Seiler, J.M. [CEA Grenoble, 38 (France); Ranval, W. [Electricite de France (EDF), 75 - Paris (France)

    2006-07-01

    This document presents the current state of the research relative to the grave accidents realized in France and abroad. It aims at giving the most exhaustive possible and objective vision of this original field of research. He allows to contribute to the identification and to the hierarchical organization of the needs of R and D, this hierarchical organization in front of, naturally, to be completed by a strong lighting on needs in terms of safety analyses associated with the different risks and the physical phenomena, in particular with the support of probability evaluations of safety level 2, whose the level of sharpness must be sufficient not to hide, by construction, physical phenomena of which the limited knowledge leads to important uncertainties. Let us note that neither the safety analyses, nor the E.P.S. 2 are presented in this document. This report presents the physical phenomena which can arise during a grave accident, in the reactor vessel and in the reactor containment, their chain and the means allowing to ease the effects. The corresponding scenarios are presented to the chapter 2. The chapter 3 is dedicated to the progress of the accident in the reactor vessel; the degradation of the core in reactor vessel (3.1), the behavior of the corium in bottom of reactor vessel (3.2) the break of the reactor vessel (3.3) and the fusion in pressure (3.4) are thus handled there. The chapter 4 concerns the phenomena which can lead to a premature failure of the containment, namely the direct heating of gases of the containment (4.1), the hydrogen risk (4.2) and the vapor explosion (4.3). The phenomenon which can lead to a delayed failure from the containment, namely the interaction corium-concrete, is approached on the chapter 5. The chapter 6 is dedicated to the problems connected to the keeping back and to the corium cooling in reactor vessel and out of reactor vessel, namely the keeping back in reactor vessel by re-flooding of the primary circuit or by re

  16. 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.

  17. 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.

  18. Fatal accidents among Danes with multiple sclerosis

    Brønnum-Hansen, Henrik; Hansen, Thomas; Koch-Henriksen, Nils;

    2006-01-01

    -1996. The end of follow-up was 1 January 1999. We calculated standardized mortality ratios (SMRs) for various types of fatal accidents. A total of 76 persons (48 men and 28 women) died from accidents, whereas the expected number of fatalities from such causes was 55.7 (31.4 men and 24.3 women). Thus, the...... particularly high for deaths from burns (SMR = 8.90) and suffocation (SMR = 5.57). We conclude that persons with MS are more prone to fatal accidents than the general population. The excess risk is due not to traffic accidents but to burns and suffocation....

  19. 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.)

  20. 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

  1. RaCon: a software tool serving to predict radiological consequences of various types of accident in support of emergency management and radiation monitoring management

    The RaCon software system, developed by the Nuclear Research Institute Rez, is described and its application when addressing various tasks in the domain of radiation accidents and nuclear safety (accidents at nuclear facilities, transport of radioactive material, terrorist attacks) are outlined. RaCon is intended for the prediction and evaluation of radiological consequences to population and rescue teams and for optimization of monitoring actions. The system provides support to emergency management when evaluating and devising actions to mitigate the consequences of radiation accidents. The deployment of RaCon within the system of radiation monitoring by mobile emergency teams or remote controlled UAV is an important application. Based on a prediction of the radiological situation, RaCon facilitates decision-making and control of the radiation monitoring system, and in turn, refines the prediction based on observed values. Furthermore, the system can perform simulations of evacuation patterns at the Dukovany NPP and at schools in the vicinity of the power plant and can provide support to emergency management should any such situation arise. (orig.)

  2. 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)

  3. 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

  4. Accident Analysis of Station Blackout of Pool-Type Research Reactor during High Power Operation%池式研究堆高功率全厂断电事故分析

    黄洪文; 刘汉刚; 钱达志; 徐显启

    2012-01-01

    针对全厂断电事故的主要事件序列,采用RETRAN-02程序对某池式研究堆全厂断电事故的进程和关键热工参数进行分析,论证该反应堆对全厂断电事故的承受能力.分析表明,在发生全厂断电事故后,该反应堆能依靠主泵惰转、可靠电源供电的余热排除系统和自然对流方式导出堆芯的剩余发热,防止核安全事故的发生;由可靠电源供电的辅助冷却是缓解该事故的有效措施,其供电能力不小于1h.%Based on the main event sequence, RETRAN-02 code is used to analyze the power supply station blackout accident and key thermal parameters of a pool-type research reactor and demonstrate the enduring capability of the accident. The result proves that the decay heat of the reactor could be removed through the idler wheel rotating, residual heat removal system supported by reliability power, and the natural circulation, which will prevent the nuclear safety accidents. The accessorial cooling supported by reliability power is an effective measure to relieve the accident, and the power can last for an hour at least.

  5. 76 FR 30855 - Accident/Incident Reporting Requirements

    2011-05-27

    ... accident/incident report (NTSB Recommendation Number RAR-05/02). See 75 FR 68891. However, upon further... NTSB Railroad Accident Report Number 05/02 (RAR 05/02). See 75 FR 68891. To clarify, FRA added Train... Equipment Accident/Incident Report.'' See 75 FR 68897. The codes represent the type of territory...

  6. 全厂断电情景下 M310核电厂缓解措施分析%Analysis on Mitigation Measures of M310 Type NPP in SBO Accident

    周克峰; 郑继业; 冯进军; 石俊英; 俞尔俊

    2014-01-01

    T he station black-out (SBO ) is a typical initial incident w hich may lead to severe accident .In order to study the ability to deal with SBO accident in M 310 type nuclear power plant and consider the requirements of Fukushima improvement actions , MELCOR code was used to analysis mitigation ability to the SBO accident .To get the key point of the impact in SBO accident process ,the factors of main pump seal ,steam-driven auxiliary feed water ,and feed water into primary and secondary circuits were studied ,and the equipment availability and the revamping time were also taken into account .The results show that the improved M310 type nuclear power plants can mitigate the SBO accident effectively and the reactor can be cooled to controllable state to avoid the massive release of radioactive material to environment .%全厂断电(SBO )是可能导致核电厂严重事故的典型初因事件。为研究国内 M 310系列核电厂应对全厂断电事故的能力,并综合考虑福岛改进行动的要求,使用严重事故分析程序M ELCOR开展SBO事故缓解能力分析。通过研究主泵轴封,汽动辅助给水,一、二回路补水等因素,并考虑设备可用性及可到达时间,给出了影响全厂断电事故进程的关键环节。分析结果表明,改进后的M 310系列核电厂可有效缓解全厂断电事故,使反应堆冷却至可控状态,避免放射性物质向环境的大量释放。

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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...

  12. 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.

  13. Analytical functions used for description of the plastic deformation process in Zirconium alloys WWER type fuel rod cladding under designed accident conditions

    The aim of this work was to improve the RAPTA-5 code as applied to the analysis of the thermomechanical behavior of the fuel rod cladding under designed accident conditions. The irreversible process thermodynamics methods were proposed to be used for the description of the plastic deformation process in zirconium alloys under accident conditions. Functions, which describe yielding stress dependence on plastic strain, strain rate and temperature may be successfully used in calculations. On the basis of the experiments made and the existent experimental data the dependence of yielding stress on plastic strain, strain rate, temperature and heating rate for E110 alloy was determined. In future the following research work shall be made: research of dynamic strain ageing in E635 alloy under different strain rates; research of strain rate influence on plastic strain in E635 alloy under test temperature higher than 873 K; research of deformation strengthening of E635 alloy under high temperatures; research of heating rate influence n phase transformation in E110 and E635 alloys

  14. Qualification of the nuclear reactor core model DYN3D coupled to the thermohydraulic system code ATHLET, applied as an advanced tool for accident analysis of VVER-type reactors. Final report

    The nuclear reactor core model DYN3D with 3D neutron kinetics has been coupled to the thermohydraulic system code ATHLET. In the report, activities on qualification of the coupled code complex ATHLET-DYN3D as a validated tool for the accident analysis of russian VVER type reactors are described. That includes: - Contributions to the validation of the single codes ATHLET and DYN3D by the analysis of experiments on natural circulation behaviour in thermohydraulic test facilities and solution of benchmark tasks on reactivity initiated transients, - the acquisition and evaluation of measurement data on transients in nuclear power plants, the validation of ATHLET-DYN3D by calculating an accident with delayed scram and a pump trip in VVER plants, - the complementary improvement of the code DYN3D by extension of the neutron physical data base, implementation of an improved coolant mixing model, consideration of decay heat release and xenon transients, - the analysis of steam leak scenarios for VVER-440 type reactors with failure of different safety systems, investigation of different model options. The analyses showed, that with realistic coolant mixing modelling in the downcomer and the lower plenum, recriticality of the scramed reactor due to overcooling can be reached. The application of the code complex ATHLET-DYN3D in Czech Republic, Bulgaria and the Ukraine has been started. Future work comprises the verification of ATHLET-DYN3D with a DYN3D version for the square fuel element geometry of western PWR. (orig.)

  15. 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

  16. Investigation of Qom Rural Area Water Network Accident in 2010 and Minimization Approaches of Accident Frequencies

    Hossein Jafari Mansoorian

    2016-02-01

    Full Text Available Background & Aims of the Study : Accidents in water networks can lead to increase the uncounted water, costs of repair, maintenance, restoration and enter water contaminants to water network. The aim of this study is to survey the accidents of Qom rural water network and choose the right approaches to reduce the number of accidents. Materials & Methods: In this cross-sectional study, four sector of Qom province (Markazi, Dastjerd, Kahak and Qahan, were assessed over a period of 8 months (July – January 2010. This study was conducted through questionnaire of Ministry of Energy. Results: The total number of accidents was 763. The highest number of accidents in the four sectors was related to Markazi sector with 228 accidents. According to the time of the accident, the highest and lowest number of accident was related to September (19.7% and November (6.8%, respectively. According to the location of the accident on network, the highest and lowest number of accident was related to distribution network (64% and connections (17.5% and transmission pipe (18.34%, respectively. According to the type of the accident, the highest and lowest number of accident was related to breaking (47.8% and gasket failure (1.2%, respectively. Considering with the pipes’ material, the highest and lowest number of accident was related to polyethylene pipes (93% and steel and cast iron pipes (0.5%, 0.5%, respectively. Conclusions: Due to the high break rate of Polyethylene pipes, it is recommended to be placed in priority of leak detection and rehabilitation.   .

  17. 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

  18. 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)

  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. Containment leakage during severe accident conditions

    An alternate to the THRESHOLD model used in most severe accident risk assessments has been investigated. One reference plant for each of six containment types has been studied to determine the magnitude of containment leakage that would result from the pressures and temperatures associated with severe accident conditions. Containment penetrations having the greatest potential for early containment leakage are identified. The studies indicate that containment leakage through penetrations prior to reaching containment threshold pressures (currently reported containment shell failure pressures) should be considered in severe accident risk assessments. Failure of non-metallic seals for containment penetrations can be a significant source of containment leakage under severe accident pressure and temperature conditions. Although studies of containment types are useful in identifying sources of containment leakage, final conclusions may need to be plant specific. Recommendations concerning future studies to better develop the use of continuous leakage models are provided. 9 references, 4 figures, 2 tables

  2. Severe accident analysis of a representative LWR plant with MAAP5.01 and MELCOR2.1. Comparison of station blackout analysis for a BWR-5/advanced Mark-II containment type plant

    In order to investigate the differences in characteristics of MAAP5.01 and MELCOR2.1, which are dedicated codes to evaluate severe accident progression, severe accident analyses for a TBU sequence (station blackout with no emergency power supply and no recovery of short- and long-term A/C power) in a BWR-5/advanced Mark-II containment type plant were conducted by using the two codes. Based on the analysis that input settings of the decay heat of fuel, the failure criteria of fuel cladding and core support plate, and zirconium – water interaction model are adjusted between these codes, the hydrodynamic response inside the reactor pressure vessel (RPV) in the early phase (until the onset of fuel relocation) of the TBU sequence is shown to be in good agreement. However, significant differences are observed in the onset timing of the major physical phenomena after the core support plate failure. It is inferred that these disagreements are primarily caused by the differences in characteristics of analytical models in each code, such as debris relocation, coolant channel blockage, entrainment and quench of the molten debris jet in water pool, failure of the RPV lower head, and molten core – concrete interaction (MCCI). (author)

  3. National registration of accidents in Iceland.

    Olafsson, O; Axelsson, J

    1992-01-01

    Community based registration of accidents has been employed in Iceland from 1987. A form developed in the emergency ward at the city Hospital of Reykjavik has been used for the registration. The following issues have been registered: the type and the seriousness of the injury, treatment, place of accident and time of accident. Health centres in Iceland have been computerized from 1976. At the time being about half of the health centres participate in the registration with the information included in the form as the source. Every health center has its well defined district. The accidents among the inhabitants in each district is registered, while accidents among other people, e.g. tourists, is registered separately. At this moment 183,000 out of a total number of 259,000 inhabitants are covered by the registration, i.e. 71% of the population. In 1989 the frequency of accidents was 198 per 100,000 inhabitants. 26% of the accidents occurred at home, 11% at work, 9% during physical activity, 6% was traffic accidents, whereas the same proportion occurred at school. This registration system has been created as a result of annual conferences on accidents arranged by the Director General of public health since 1984. Representatives for the following parties have been invited; medical doctors working in hospitals and health centres, clinical nurses, physiotherapists, the National Insurance Service, other insurance companies, rescue and ambulance personal, fire departments, the Automobile Association, the communication Council. Local communities members of the parliament, voluntary organizations, e.g. Red Cross, the Sea Rescue Service and the Aviation Board. This activity has stimulated measures aiming at preventing accidents in several local communities.(ABSTRACT TRUNCATED AT 250 WORDS) PMID:1285816

  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. 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

  7. 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

  8. 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

  9. 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)

  10. 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.)

  11. 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

  12. 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)

  13. A case study of electrostatic accidents in the process of oil-gas storage and transportation

    Ninety nine electrostatic accidents were reviewed, based on information collected from published literature. All the accidents over the last 30 years occurred during the process of oil-gas storage and transportation. Statistical analysis of these accidents was performed based on the type of complex conditions where accidents occurred, type of tanks and contents, and type of accidents. It is shown that about 85% of the accidents occurred in tank farms, gas stations or petroleum refineries, and 96% of the accidents included fire or explosion. The fishbone diagram was used to summarize the effects and the causes of the effects. The results show that three major reasons were responsible for accidents, including improper operation during loading and unloading oil, poor grounding and static electricity on human bodies, which accounted for 29%, 24% and 13% of the accidents, respectively. Safety actions are suggested to help operating engineers to handle similar situations in the future.

  14. A case study of electrostatic accidents in the process of oil-gas storage and transportation

    Hu, Yuqin; Wang, Diansheng; Liu, Jinyu; Gao, Jianshen

    2013-03-01

    Ninety nine electrostatic accidents were reviewed, based on information collected from published literature. All the accidents over the last 30 years occurred during the process of oil-gas storage and transportation. Statistical analysis of these accidents was performed based on the type of complex conditions where accidents occurred, type of tanks and contents, and type of accidents. It is shown that about 85% of the accidents occurred in tank farms, gas stations or petroleum refineries, and 96% of the accidents included fire or explosion. The fishbone diagram was used to summarize the effects and the causes of the effects. The results show that three major reasons were responsible for accidents, including improper operation during loading and unloading oil, poor grounding and static electricity on human bodies, which accounted for 29%, 24% and 13% of the accidents, respectively. Safety actions are suggested to help operating engineers to handle similar situations in the future.

  15. 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.)

  16. Accidents in radiotherapy: Lack of quality assurance?

    About 150 radiological accidents, involving more than 3000 patients with adverse effects, 15 patient's fatalities and about 5000 staff and public exposures have been collected and analysed. Out of 67 analysed accidents in external beam therapy 22% has been caused by wrong calculation of the exposure time or monitor units, 13% by inadequate review of patient's chart, 12% by mistakes in the anatomical area to be treated. The remaining 35% can be attributed to 17 different causes. The most common mistakes in brachytherapy were wrong activities of sources used for treatment (20%), inadequate procedures for placement of sources applicators (14%), mistakes in calculating the treatment time (12%), etc. The direct and contributing causes of radiological accidents have been deduced from each event, when it was possible and categorized into 9 categories: mistakes in procedures (30%), professional mistakes (17%), communication mistakes (15%), lack of training (8.5%), interpretation mistakes (7%), lack of supervision (6%), mistakes in judgement (6%), hardware failures (5%), software and other mistakes (5.5%). Three types of direct and contributing causes responsible for almost 62% of all accidents are directly connected to the quality assurance of treatment. The lessons learnt from the accidents are related to frequencies of direct and contributing factors and show that most of the accident are caused by lack, non-application of quality assurance (QA) procedures or by underestimating of QA procedures. The international system for collection of accidents and dissemination of lessons learnt from the different accidents, proposed by IAEA, can contribute to better practice in many radiotherapy departments. Most of the accidents could have been avoided, had a comprehensive QA programme been established and properly applied in all radiotherapy departments, whatever the size. (author)

  17. 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.)

  18. Severe accident testing of electrical penetration assemblies

    This report describes the results of tests conducted on three different designs of full-size electrical penetration assemblies (EPAs) that are used in the containment buildings of nuclear power plants. The objective of the tests was to evaluate the behavior of the EPAs under simulated severe accident conditions using steam at elevated temperature and pressure. Leakage, temperature, and cable insulation resistance were monitored throughout the tests. Nuclear-qualified EPAs were produced from D. G. O'Brien, Westinghouse, and Conax. Severe-accident-sequence analysis was used to generate the severe accident conditions (SAC) for a large dry pressurized-water reactor (PWR), a boiling-water reactor (BWR) Mark I drywell, and a BWR Mark III wetwell. Based on a survey conducted by Sandia, each EPA was matched with the severe accident conditions for a specific reactor type. This included the type of containment that a particular EPA design was used in most frequently. Thus, the D. G. O'Brien EPA was chosen for the PWR SAC test, the Westinghouse was chosen for the Mark III test, and the Conax was chosen for the Mark I test. The EPAs were radiation and thermal aged to simulate the effects of a 40-year service life and loss-of-coolant accident (LOCA) before the SAC tests were conducted. The design, test preparations, conduct of the severe accident test, experimental results, posttest observations, and conclusions about the integrity and electrical performance of each EPA tested in this program are described in this report. In general, the leak integrity of the EPAs tested in this program was not compromised by severe accident loads. However, there was significant degradation in the insulation resistance of the cables, which could affect the electrical performance of equipment and devices inside containment at some point during the progression of a severe accident. 10 refs., 165 figs., 16 tabs

  19. Severe accident testing of electrical penetration assemblies

    Clauss, D.B. (Sandia National Labs., Albuquerque, NM (USA))

    1989-11-01

    This report describes the results of tests conducted on three different designs of full-size electrical penetration assemblies (EPAs) that are used in the containment buildings of nuclear power plants. The objective of the tests was to evaluate the behavior of the EPAs under simulated severe accident conditions using steam at elevated temperature and pressure. Leakage, temperature, and cable insulation resistance were monitored throughout the tests. Nuclear-qualified EPAs were produced from D. G. O'Brien, Westinghouse, and Conax. Severe-accident-sequence analysis was used to generate the severe accident conditions (SAC) for a large dry pressurized-water reactor (PWR), a boiling-water reactor (BWR) Mark I drywell, and a BWR Mark III wetwell. Based on a survey conducted by Sandia, each EPA was matched with the severe accident conditions for a specific reactor type. This included the type of containment that a particular EPA design was used in most frequently. Thus, the D. G. O'Brien EPA was chosen for the PWR SAC test, the Westinghouse was chosen for the Mark III test, and the Conax was chosen for the Mark I test. The EPAs were radiation and thermal aged to simulate the effects of a 40-year service life and loss-of-coolant accident (LOCA) before the SAC tests were conducted. The design, test preparations, conduct of the severe accident test, experimental results, posttest observations, and conclusions about the integrity and electrical performance of each EPA tested in this program are described in this report. In general, the leak integrity of the EPAs tested in this program was not compromised by severe accident loads. However, there was significant degradation in the insulation resistance of the cables, which could affect the electrical performance of equipment and devices inside containment at some point during the progression of a severe accident. 10 refs., 165 figs., 16 tabs.

  20. Occupational Accidents: A Perspective of Pakistan Construction Industry

    Tauha Hussain Ali

    2014-07-01

    Full Text Available It has been observed that the construction industry is one of the notorious industry having higher rate of fatalities and injuries. Resulting in higher financial losses and work hour losses, which are normally faced by this industry due to occuptional accidents. Construction industry has the highest occupational accidents rate recorded throughout the world after agriculture industry. The construction work site is often a busy place having an incredibly high account of activities taking place, where everyone is moving in frenzy having particular task assigned. In such an environment, occupational accidents do occur. This paper gives information about different types of occupational accidents & their causes in the construction industry of Pakistan. A survey has been carried out to identify the types of occupational accidents often occur at construction site. The impact of each occupational accident has also been identified. The input from the different stakeholders involved on the work site was analyzed using RIW (Relative Importance Weight method. The findings of this research show that ?fall from elevation, electrocution from building power and snake bite? are the frequent occupational accidents occur within the work site where as ?fall from elevation, struck by, snake bite and electrocution from faulty tool? are the occupational accident with high impact within the construction industry of Pakistan. The results also shows the final ranking of the accidents based on higher frequency and higher impact. Poor Management, Human Element and Poor Site Condition are found as the root causes leading to such occupational accidents. Hence, this paper

  1. 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

  2. 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

  3. 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)

  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. 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.)

  6. 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)

  7. 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

  8. PWR pressure vessel integrity during overcooling accidents

    Pressurized water reactors are susceptible to certain types of hypothetical accidents that under some circumstances, including operation of the reactor beyond a critical time in its life, could result in failure of the pressure vessel as a result of propagation of crack-like defects in the vessel wall. The accidents of concern are those that result in thermal shock to the vessel while the vessel is subjected to internal pressure. Such accidents, referred to as pressurized thermal shock or overcooling accidents (OCA), include a steamline break, small-break LOCA, turbine trip followed by stuck-open bypass valves, the 1978 Rancho Seco and the TMI accidents and many other postulated and actual accidents. The source of cold water for the thermal shock is either emergency core coolant or the normal primary-system coolant. ORNL performed fracture-mechanics calculations for a steamline break in 1978 and for a turbine-trip case in 1980 and concluded on the basis of the results that many more such calculations would be required. To meet the expected demand in a realistic way a computer code, OCA-I, was developed that accepts primary-system temperature and pressure transients as input and then performs one-dimensional thermal and stress analyses for the wall and a corresponding fracture-mechanics analysis for a long axial flaw. The code is briefly described, and its use in both generic and specific plant analyses is discussed

  9. Radiological accidents, scenarios, planning and answers

    Radiological accidents, scenarios and the importance of a good planning to prevent and control these types of accidents are presented. The radiation can be only one of the risks in an accident, most of dominant radiological risks are not radiological (fire, toxic gases, etc.). The common causes of radiological accidents, potential risks such as external irradiation, internal contamination and the environment pollution are highlighted. In addition, why accidents happen and how they evolve is explained. It describes some incidents with the radiation occurred in Costa Rica from 1993 to 2007. The coordination of emergency management in Costa Rica in relation to a radiological accident, and some mechanisms of action that have practiced in other places are focuses. Among the final considerations are the need to finalize the national plan for radiological emergencies as a tool of empowerment for the teams of emergency care and the availability of information. Likewise the processes of communication, coordination and cooperation to avoid chaos, confusion and crisis are also highlighted

  10. 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.

  11. 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...

  12. 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.)

  13. 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.

  14. Occupational accidents: a perspective of pakistan construction industry

    It has been observed that the construction industry is one of the notorious industry having higher rate of facilities and injuries. Resulting in higher financial losses and work hour losses, which are normally faced by this industry due to occupational accidents. Construction industry has the highest occupational accidents rate recorded throughout the world after agriculture industry. The construction work site is often a busy place having an incredibly high account of activities taking place, where everyone is moving in frenzy having particular task assigned. In such an environment, occupational accidents do occur. This paper gives information about different types of occupational accidents and their causes in the construction industry of Pakistan. A survey has been carried out to identify the types of occupational accidents often occur at construction site. The impact of each occupational accident has also been identified. The input from the different stakeholders involved on the work site was analyzed using RIW (Relative Importance Weight) method. The findings of this research show that fall from elevation, electrocution from building power and snake bite are the frequent occupational accidents occur within the work site where as fall from elevation, struck by, snake bite and electrocution from faulty tool are the occupational accident with high impact within the construction industry of Pakistan. The results also shows the final ranking of the accidents based on higher frequency and higher impact. Poor Management, Human Element and Poor Site Condition are found as the root causes leading to such occupational accidents. Hence, this paper identify that what type of occupational accidents occur at the work place in construction industry of pakistan, in order to develop the corrective actions which should be adequate enough to prevent the re-occurrence of such accidents at work site. (author)

  15. 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

  16. Analysis of severe accidents in pressurized heavy water reactors

    Certain very low probability plant states that are beyond design basis accident conditions and which may arise owing to multiple failures of safety systems leading to significant core degradation may jeopardize the integrity of many or all the barriers to the release of radioactive material. Such event sequences are called severe accidents. It is required in the IAEA Safety Requirements publication on Safety of the Nuclear Power Plants: Design, that consideration be given to severe accident sequences, using a combination of engineering judgement and probabilistic methods, to determine those sequences for which reasonably practicable preventive or mitigatory measures can be identified. Acceptable measures need not involve the application of conservative engineering practices used in setting and evaluating design basis accidents, but rather should be based on realistic or best estimate assumptions, methods and analytical criteria. Recently, the IAEA developed a Safety Report on Approaches and Tools for Severe Accident Analysis. This publication provides a description of factors important to severe accident analysis, an overview of severe accident phenomena and the current status in their modelling, categorization of available computer codes, and differences in approaches for various applications of severe accident analysis. The report covers both the in- and ex-vessel phases of severe accidents. The publication is consistent with the IAEA Safety Report on Accident Analysis for Nuclear Power Plants and can be considered as a complementary report specifically devoted to the analysis of severe accidents. Although the report does not explicitly differentiate among various reactor types, it has been written essentially on the basis of available knowledge and databases developed for light water reactors. Therefore its application is mostly oriented towards PWRs and BWRs and, to a more limited extent, they can be only used as preliminary guidance for other types of reactors

  17. 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)

  18. 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

  19. Nuclear-powered submarine accidents

    Most of nuclear-powered ships are military ships and submarines represent 95% of the total. Most of the propulsion reactors used are of PWR type. This paper gives the principal technical characteristics of PWR ship propulsion reactors and the differences with their civil homologues. The principal accidents that occurred on US and Russian nuclear-powered submarines are also listed and the possible effects of a shipwreck on the reactor behaviour are evaluated with their environmental impact. (J.S.). 1 tab., 1 photo

  20. Elements to diminish radioactive accidents

    In this work it is presented an application of the cause-effect diagram method or Ichikawa method identifying the elements that allow to diminish accidents when the radioactive materials are transported. It is considered the transport of hazardous materials which include radioactive materials in the period: December 1996 until March 1997. Among the identified elements by this method it is possible to mention: the road type, the radioactive source protection, the grade driver responsibility and the preparation that the OEP has in the radioactive material management. It is showed the differences found between the country inner roads and the Mexico City area. (Author)

  1. Using MARS to assist in managing a severe accident

    During an accident, information about the current and possible future states of the plant provides guidance for accident managers in evaluating which actions should be taken. However, depending upon the nature of the accident and the stress levels imposed on the plant staff responding to the accident the current and future plant assessments may be very difficult or nearly impossible to perform without supplemental training and/or appropriate tools. The MAAP Accident Response System (MARS) has been developed as a calculational aid to assist the responsible accident management individuals. Specifically MARS provides additional insights on the current and possible future states of the plant during an accident including the influence of operator actions. In addition to serving as a calculational aid, the MARS software can be an effective means for providing supplemental training. The MARS software uses engineering calculations to perform an integral assessment of the plant status including a consistency assessment of the available instrumentation. In addition, it uses the Modular Accident Analysis Program (MAAP) to provide near term predictions of the plant response if corrective actions are taken. This paper will discuss the types of information that are beneficial to the accident manager and how MARS addresses each. The MARS calculational functions include: instrumentation, validation and simulation, projected operator response based on the EOPs, as well as estimated timing and magnitude of in-plant and off-site radiation dose releases. Each of these items is influential in the management of a severe accident. (author)

  2. ANALYSIS OF THE ACCIDENTS OF THE CAR MANUFACTURING INDUSTRIES

    J.Adl ; Z. Mohammad zade

    1993-08-01

    Full Text Available Car manufacturing industry accident’s rates from three major companies are analyzed. Totally 1325 accidents with 4 cases of fatality were recorded. Accident rates per 100 full-time workers have gradually increased from 5.3 to 8.7 during 3 years of study. Most of the accidents occurred during the primary hours of the work, Strains and sprains represented the most frequently occurring type of injury, accounting for 37.9% and the greatest number of injuries occurred by flying particles (3 1.6%, resulting in eye injuries. Other aspects of accidents in this industry are discussed and recommendations are given for their prevention.

  3. Strategies for dealing with resistance to recommendations from accident investigations

    Lundberg, J.; Rollenhagen, C.; Hollnagel, E.;

    2012-01-01

    Accident investigation reports usually lead to a set of recommendations for change. These recommendations are, however, sometimes resisted for reasons such as various aspects of ethics and power. When accident investigators are aware of this, they use several strategies to overcome the resistance....... This paper describes strategies for dealing with four different types of resistance to change. The strategies were derived from qualitative analysis of 25 interviews with Swedish accident investigators from seven application domains. The main contribution of the paper is a better understanding of...... effective strategies for achieving change associated with accident investigation. (C) 2011 Elsevier Ltd. All rights reserved....

  4. 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...

  5. Determinants of the property damage costs of tanker accidents

    This study investigates determinants of the vessel, oil cargo spillage, and other-property damage costs of tanker accidents. Tobit estimation of a three-equation recursive model suggests that, among types of tanker accidents, fire/explosion accidents incur the largest vessel damage costs, but the smallest oil cargo spillage costs. Alternatively, grounding accidents incur the smallest vessel damage costs, but the largest oil cargo spillage costs, reflecting the difficulty of controlling oil cargo spillage subsequent to such accidents. Also, oil cargo spillage costs are lower for US flag tanker accidents. A dollar of vessel damage cost increases other-property damage cost by 0.06 dollars, whereas a dollar of oil cargo spillage increases this cost by 1.55 dollars

  6. Analysis of accidents at the LPR (Radiochemical Processes Laboratory)

    Accidents are defined as not planned events that may result in the emission of significative quantities of radioactive materials to the environment. The pilot plant has been specifically designed to prevent this type of accidents but there still exists the possibility that one or more accidents can be produced during the plant life. In a first phase, the emission of radionuclides to the environment were evaluated for 13 credible accidents. In a second phase, by means of the calculation program SEDA, specially adapted to this purpose, the critical doses of critical group were calculated for each accident. Due to the small capacity of the pilot plant and the long cooling period of treated fuel, it is concluded that the radiological consequences for the external environment are of very small magnitude. In this way, without need of developing complex fault- or event-trees, it is shown that any of the accidents falls into the non acceptable zone of Farmer diagram. (Author)

  7. 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)

  8. 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

  9. 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

  10. 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...

  11. Role of accident analysis in development of severe accident management guidance for multi-unit CANDU nuclear power plants

    This paper discusses the role of accident analysis in support of the development of Severe Accident Management Guidance for domestic CANDU reactors. In general, analysis can identify what types of challenges can be expected during accident progression but it cannot specify when and to what degree accident phenomena will occur. SAMG overcomes these limitations by monitoring the actual values of key plant indicators that can be used directly or indirectly to infer the condition of the plant and by establishing setpoints beyond which corrective action is required. Analysis can provide a means to correlate observed post-accident plant behavior against predicted behaviour to improve the confidence in and quality of accident mitigation decisions. (author)

  12. Chernobyl accident. Exposures and effects

    to ionizing radiation. Risk of leukaemia, one of the major concerns after radiation exposure, does not appear to be elevated even among the recovery workers. Neither is there any scientific proof of other non-malignant disorders, somatic or mental, that are related to ionizing radiation. A majority of the epidemiological studies completed to date are of the descriptive type, in which average population exposures are correlated with the average rates of cancer incidence in specific time periods. As long as individual doses with reasonably low uncertainties are not available, the extent to which health effects might be radiation-related remains unclear. The reconstruction of individual doses is a key element in future research on radiation associated cancers related to the Chernobyl accident. Although the Chernobyl accident could shed some light on the knowledge on the late effects of protracted radiation exposures, it must be recognized that because of the relatively low doses received by the majority of exposed individuals, any increase in cancer incidence or mortality will be difficult to detect in epidemiological studies. (author)

  13. 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)

  14. Transient and accident analysis of a BN-800 type LMFR with near zero void effect. Final report on an international benchmark programme supported by the International Atomic Energy Agency and the European Commission 1994-1998

    Large conventional liquid metal cooled fast reactor (LMFR) cores show a significant reactivity increase if a coolant loss occurs by boiling or gas intrusion. Since this positive reactivity effect is very important for the overall behaviour of LMFRs from a safety point of view, a lot of attempts have been undertaken worldwide to reduce the sodium void reactivity effect (SVRE). One proposal has been made by the Institute of Physics and Power Engineering (IPPE), Obninsk, Russian Federation, in which the core upper axial blanket is replaced by a sodium plenum consisting of sodium filled wrapper tubes. In this case the enhanced axial neutron leakage would result in a strong negative reactivity effect in case of sodium voiding which would compensate a large fraction of the positive SVRE in the core region. The International Atomic Energy Agency (IAEA) and the European Commission (EC) Joint Benchmark Programme have assessed the capability of reducing the SVRE of such innovative core design. The analysis (IAEA-TECDOC-731, 1994) showed that overall SVRE for the reference 2100 MW(th) MOX fuel core might be close to zero. This method of reducing the SVRE has been adopted in the BN-800 reactor design in the Russian Federation. However, investigations were needed to determine differences in severe accident responses in order to estimate the feedback to overall safety that could be achieved by a reduction in the SVRE value for mixed-oxide (MOX) fuel reactor core. Therefore, recognizing the importance of such an innovative LMFR core design, a comparative exercise of severe accidents for BN-800 type reactors with reduced sodium void coefficient was jointly initiated by the IAEA and the EC in 1994. The Russian specialists took over the task to prepare the benchmark input data, a revised draft of which was distributed by the IAEA to the participants at the end of June 1995. The specifications of the benchmark were finally fixed in a meeting at the IAEA in Vienna on 11- 13 December

  15. 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)

  16. Severe accident management. Optimized guidelines and strategies

    the accident progression in near future, to identify the currently most critical tasks as well as upcoming tasks, and to qualify the emergency response team to make informed decisions for the severe accident mitigation based on state-of-the-art knowledge. In this paper, this severe accident management concept is introduced and explained. It is also shown that AREVA is able to apply this methodology to other (including non-OEM) plant types, thus providing a comprehensive safety analysis of the existing plant state with already available safety systems and instrumentation. In addition, the possible need and potential for hardware refitting can be assessed as well. Finally, the severe accident management procedures are then established or updated accordingly. (author)

  17. 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

  18. 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

  19. 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.)

  20. 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)

  1. Effectiveness of selected accident management measures

    The spectrum of application of accident management measures and the boundary conditions for their performance are discussed. An assessment is made of the feasibility and effectiveness of selected possibilities of intervention for both types of light water reactors. Detailed descriptions are given of accident management measures (bleed and feed) on the secondary and on the primary side. Investigations have revealed that West German light water reactors have a great safety potential by flexible applicaton of the existing systems for controlling events which exceed the design basis. (orig./HP)

  2. Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

    700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage

  3. 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.

  4. 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.)

  5. 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

  6. 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)

  7. 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.

  8. Taking into account a reactivity accident in research reactors design

    The particular studies realized in France for research reactors design at a Borax accident type are described. The cases of ORPHEE and RHF reactors are particularly developed. The evolution of the studies and the conservatism used are given

  9. 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

  10. 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

  11. 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

  12. 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)

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

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

    2011-07-01

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

  14. 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)

  15. 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)

  16. 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...

  17. 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

  18. 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.)

  19. Appearing consequences of the Chernobyl accident

    Full text: Chernobyl is the greatest world's tragedy after Chirosima. Global results of this tragedy is already being seen. They are the people who have received radiation dose. the first type of cancer 5 years after Chernobyl accident was the thyroid gland cancer, the reason of it, large quantities of radioactive iodine in the air, food products, milk of cattle and finally their collection in the thyroid gland cancer entering the human body. Period all of a sudden after 10 years completed the next latent type of cancer was leykoz. Giving rise to this type of cancer more sensitive to radiation of the body - a violation of the spinal brain function. After 20 years passing from the accident in the first generation one ill child must be born cause of undergoing to radiation father or mother from each three days in Belarus, Russia and Ukraine

  20. ETRR-2 control rod withdrawal accident

    A safety evaluation of Egypt new reactor, Egypt Test and Research Reactor number 2 (ETRR-2), has been completed successfully. Intensive efforts have been made for design basis accidents (DBA) analysis. The present work presents analysis of one of these accidents, i.e. the uncontrolled reactivity insertion accident (RIA) due to erroneous withdrawal of control rod (CR) during normal operating conditions. The reactivity insertion may be fast or slow, depending on the speed of CR withdrawal. The availability of the scam system is considered. The reactivity insertion function (RIF) is modeled by: 1 - an approximate ramp functions (RF), and 2 - actual S(cosine) function (CF). A computer code TRANSP19 is developed for the analysis. It models RIA of material test and research reactors (MTR). The code was verified against results obtained from RETRAN 02 and PARET codes and showed a good agreement. The study shows that ETRR-2 core, MTR type, withstands this type of perturbation, fast or slow, in condition that the shutdown system (SHDS) is available. Otherwise the coolant, clad, and fuel temperatures may exceed their design goal values [safety limits (SL)] and the clad may ruptures, coolant may boil, and the fuel may damage. The core reciprocal period never exceeds 140 s-1 for all accident cases (minimum period is 21.98 s) which demonstrates that no explosion other than sonic blockage could occur

  1. 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

  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. HIV surveillance in needlestick accidents with health workers

    Janete Lane Amadei

    2010-12-01

    Full Text Available Objective: To characterize the occurrence of needlestick accidents with health professionals submitted to rapid HIV tests. Methods: A descriptive, epidemiological study, carried out by notification of the occurrence of needlestick accidents in the Epidemiology Sector of the State Health Secretariat, in 2008. The following variables were assessed: gender, age, exposed biological material, type of exposure, source patient, and injured patient, progression of the case, accident situation, and use of personal protective equipment (PPE, 180 days serology and occupational area. Results: There have been reports of 143 accidents, prevailing in nursing, female, 20 to 30 years, involving the blood and biological material by percutaneous puncture. We found no standardization in the use of PPE. The HIV test revealed no positive cases. Conclusion: This study helped to characterize the occurrence of accidents reported in health care professionals and evaluate the protocol of care given. It also revealed non-contamination by HIV.

  4. 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

  5. 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

  6. 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.

  7. 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)

  8. 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...

  9. Analysis of an accident type sbloca in reactor contention AP1000 with 8.0 Gothic code; Analisis de un accidente tipo Sbloca en la contencion del reactor AP1000 con el codigo Gothic 8.0

    Goni, Z.; Jimenez Varas, G.; Fernandez, K.; Queral, C.; Montero, J.

    2016-08-01

    The analysis is based on the simulation of a Small Break Loss-of-Coolant-Accident in the AP1000 nuclear reactor using a Gothic 8.0 tri dimensional model created in the Science and Technology Group of Nuclear Fision Advanced Systems of the UPM. The SBLOCA has been simulated with TRACE 5.0 code. The main purpose of this work is the study of the thermo-hydraulic behaviour of the AP1000 containment during a SBLOCA. The transients simulated reveal close results to the realistic behaviour in case of an accident with similar characteristics. The pressure and temperature evolution enables the identification of the accident phases from the RCS point of view. Compared to the licensing calculations included in the AP1000 Safety Analysis, it has been proved that the average pressure and temperature evolution is similar, yet lower than the licensing calculations. However, the temperature and inventory distribution are significantly heterogeneous. (Author)

  10. 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

  11. 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)

  12. 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)

  13. 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.)

  14. 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

  15. 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

  16. Comparison of Commonly Used Accident Analysis Techniques for Manufacturing Industries

    IRAJ MOHAMMADFAM

    2015-10-01

    Full Text Available The adverse consequences of major accident events have led to development of accident analysis techniques to investigate thoroughly the accidents. However, each technique has its own advantages and shortcomings,which make it very difficult to find a single technique being capable of analyzing all types of accidents. Therefore, the comparison of accident analysis techniques would help finding out their capabilities in different circumstances to choose the most one. In this research, the techniques CBA and AABF were compared with Tripod β in order to determine the superior technique for analysis of major accidents in manufacturing industries. At first step, the comparison criteria were developed using Delphi Method. Afterwards, the relative importance of each criterion was qualitatively determined and the qualitative values were then converted to the quantitative values  applying  Fuzzy  triangular  numbers.  Finally,  the  TOPSIS  was  used  to  prioritize  the techniques in terms of the preset criteria. The results of the study showed that Tripod β is superior to the CBA and AABF. It is highly recommended to compare all available accident analysis techniques based on proper criteria in order to select the best one whereas improper choice of accident analysis techniques may lead to misguided results.

  17. 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....

  18. 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

  19. 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

  20. 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)

  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. 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.

  3. Simulation of LOF accidents with directly electrical heated UO2 pins

    The behavior of directly electrical heated UO2 pins has been investigated under loss of coolant conditions. Two types of hypothetical accidents have been simulated, first, a LOF accident without power excursion (LOF accident) and second, a LOF accident with subsequent power excursion (LOF-TOP accident). A high-speed film shows the sequence of events for two characteristic experiments. In consequence of the high-speed film analysis as well as the metallographical evaluation statements are given in respect to the cladding meltdown process, the fuel melt fraction and the energy input from the beginning of a power transient to the beginning of the molten fuel ejections

  4. 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)

  5. 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)

  6. Applicability of health physics lessons learned from the Three Mile Island Unit 2 accident to the Fukushima Daiichi accident

    The TMI-2 and Fukushima Daiichi accidents appear to be dissimilar because they involve different reactor types. However, the health physics related lessons learned from TMI-2 are applicable, and can enhance the Fukushima Daiichi recovery effort. - Highlights: ► TMI-2 health physics lessons learned are applicable to Fukushima Daiichi Accident. ► Fuel damage sequence of these accidents are similar. ► On-site recovery actions will be similar, but Fukushima Daiichi is more demanding. ► Offsite recovery actions are significantly more challenging at Fukushima Daiichi.

  7. 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

  8. 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

  9. 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

  10. Thyroid diseases after Chernobyl accident

    Radioactive iodine is released at every atomic-bomb testings and nuclear plants accidents and radioactive iodine is taken up by thyroid glands (internal radiation). In addition to the internal radiation, radioactive fallout causes the external radiation and thyroid glands are known to be sensitive to the external radiation. Furthermore, patients with radiation-induced thyroid disease can survive for a long time regardless of the treatment. The survey of thyroid diseases, therefore, is very sensitive and reliable ways to investigate the effects of radiation caused by atomic bomb explosion, testing and various types of nuclear plants' accidents. Our group from Nagasaki University was asked to investigate the thyroid diseases and jointed to the Sasakawa Project. In order to investigate the effects of radiation on thyroid disease, it is essential 1) to make a correct diagnosis in each subject, 2) to calculate a correct radiation dose in each subject and finally, 3) to find out the correlation between the radiation dose and thyroid diseases including age-, sex- and area-matched controls. We have established 5 centers (1 in Russia, 2 in Belarus, 2 in Ukraine) and supplied the most valuable ultrasonography instruments, commercial kits for the determination of serum free T4 and TSH level and for the autoantibodies, instrument for urinary iodine measurements, syringers, tubes, refrigerators, etc. We visit each center often and asked people at centers to come to Japan for training. Protocol of investigation is essentially the same as that in Nagasaki, and we are planning to investigate more than 50,000 children within 5 years. We are hoping to show a definite conclusion in the near future. Recent articles are also discussed. (author)

  11. Severe accident progression perspectives based on IPE results

    Lehner, J.R.; Lin, C.C.; Pratt, W.T. [Brookhaven National Laboratory, Upton, NY (United States); Drouin, M. [Nuclear Regulatory Commission, North Bethesda, MD (United States)

    1996-08-01

    Accident progression perspectives were gathered from the level 2 PRA analyses (the analysis of the accident after core damage has occurred involving the containment performance and the radionuclide release from the containment) described in the IPE submittals. Insights related to the containment failure modes, the releases associated with those failure modes, and the factors responsible for the types of containment failures and release sizes reported were obtained. Complete results are discussed in NUREG-1560 and summarized here.

  12. 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 ...

  13. 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.)

  14. 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

  15. 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

  16. 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

  17. 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)

  18. 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

  19. 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)

  20. 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

  1. 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

  2. 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

  3. Insomnia and accidents: cross-sectional study (EQUINOX) on sleep-related home, work and car accidents in 5293 subjects with insomnia from 10 countries.

    Léger, Damien; Bayon, Virginie; Ohayon, Maurice M; Philip, Pierre; Ement, Philippe; Metlaine, Arnaud; Chennaoui, Mounir; Faraut, Brice

    2014-04-01

    The link between sleepiness and the risk of motor vehicle accidents is well known, but little is understood regarding the risk of home, work and car accidents of subjects with insomnia. An international cross-sectional survey was conducted across 10 countries in a population of subjects with sleep disturbances. Primary care physicians administered a questionnaire that included assessment of sociodemographic characteristics, sleep disturbance and accidents (motor vehicle, work and home) related to sleep problems to each subject. Insomnia was defined using the International Classification of Sleep Disorders (ICSD-10) criteria. A total of 5293 subjects were included in the study, of whom 20.9% reported having had at least one home accident within the past 12 months, 10.1% at least one work accident, 9% reported having fallen asleep while driving at least once and 4.1% reported having had at least one car accident related to their sleepiness. All types of accident were reported more commonly by subjects living in urban compared to other residential areas. Car accidents were reported more commonly by employed subjects, whereas home injuries were reported more frequently by the unemployed. Car accidents were reported more frequently by males than by females, whereas home accidents were reported more commonly by females. Patients with insomnia have high rates of home accidents, car accidents and work accidents related to sleep disturbances independently of any adverse effects of hypnotic treatments. Reduced total sleep time may be one factor explaining the high risk of accidents in individuals who complain of insomnia. PMID:24237855

  4. Occupational Radiation Protection in Severe Accident Management

    As an early response to the Fukushima Daiichi NPP accident, the Information System on Occupational Exposure (ISOE) Bureau decided to focus on the following issues as an initial response of the joint program after having direct communications with the Japanese official participants in April 2011: - Management of high radiation area worker doses: It has been decided to make available the experience and information from the Chernobyl accident in terms of how emergency worker / responder doses were legally and practically managed, - Personal protective equipment for highly-contaminated areas: It was agreed to collect information about the types of personnel protective equipment and other equipment (e.g. air bottles, respirators, air-hoods or plastic suits, etc.), as well as high-radiation area worker dosimetry use (e.g. type, number and placement of dosimetry) for different types of emergency and high-radiation work situations. Detailed information was collected on dose criteria which are used for emergency workers /responders and their basis, dose management criteria for high dose/dose rate areas, protective equipment which is recommended for emergency workers / responders, recommended individual monitoring procedures, and any special requirement for assessment from the ISOE participating nuclear utilities and regulatory authorities and made available for Japanese utilities. With this positive response of the ISOE official participants and interest in the situation in Fukushima, the Expert Group on Occupational Radiation Protection in Severe Accident Management (EG-SAM) was established by the ISOE Management Board in May 2011. The overall objective of the EG-SAM is to contribute to occupational exposure management (providing a view on management of high radiation area worker doses) within the Fukushima plant boundary with the ISOE participants and to develop a state-of-the-art ISOE report on best radiation protection management practices for proper radiation

  5. Development of the Approach by States method and thermodynamical study of a 1300 MWe PWR type reactor following a complete water loss of vapor generator alimentation with the Cathare 2 code; Developpement de la conduite APE et etude thermohydraulique d'un REP 1300 MWe suite a un accident de perte totale d'eau alimentaire des generateurs de vapeur avec le code Cathare 2

    Girardin, F

    1998-06-30

    The objective of this report is to study the thermohydraulic behavior of a 1300 MWe PWR type reactor for a complete loss accident in water supplying of vapor generators. The Cathare computer code has been used in this aim. (N.C.)

  6. 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)

  7. 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)

  8. 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.

  9. 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 ...

  10. 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)

  11. 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)

  12. 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.

  13. 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...

  14. 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)

  15. Ophidic accident and twin pregnancy

    Saavedra-Orozco Héctor

    2012-12-01

    Full Text Available Introduction: around of 3000 types of snakes are known, from which just 15% arevenomous. Depending of the environmental, geographical and socio-demographiccharacteristics, there are significant differences in the incidence of cases of ophidicaccidents. Colombia reports 6 by each 100.000 habitants, 2.300 cases/year, with amortality of 5.6%. In a pregnant woman it is a rare event, between 1.4% and 4%, andit usually complicates seriously to the mother and to the product of the gestation. Theprevious thing will depend of the opportunity with which the suitable management isfulfilled and of the severity of the poisoning. Nowadays it isn´t clear the security of theantiophidic serum for the product, it has been related with miscarriage in early stagesof pregnancy and fetal death at the end of the pregnancy. Nevertheless, its appropriateadministration is the unique effective measure to avoid serious consequences andmaternal death.Clinical case: patient of 16 years old, G2 C1, with diagnosis of diamniotic dichorionic twinpregnancy of 36 weeks and ophidic accident of bothropic type of 16 hours of evolution.Right inferior limb with pain, edema grade III, blush, heat, formation of flictenas andecchymosis in its distal third. Laboratory tests indicate prolongation of the clotting time,elevated transaminases and elevated creatinine. It is considered the presence of severepoisoning and management with antiophidic serum is initiated. The pregnancy is finishedby cesarean as a result of maternal renal and hepatic dysfunction, and postoperativecare in UCI. The products are born with severe respiratory depression; they are carriedto neonatal intensive care unit with good evolution and hospital expenditure to thefive days. Next day to the cesarean, the patient presents compartment syndrome,for which fasciotomy is fulfilled. When the patient gets adequate recovery, it is donea cutaneous hanging tatter and after 27 days of hospitalization one gives exit withadequate

  16. 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

  17. Loss of Coolant Accident Analysis for Israel Research Reactor

    One of the main objectives of reactor safety systems is to keep the reactor core in condition that does not permit any release of radioactivity into the environment. In order to ensure this, the reactor must have sufficient safety margins during all possible operational and accident conditions. This paper focuses on the analysis of loss of coolant accident (LOCA), which is one of the most severe scenarios among other hypothetical events such as reactivity induced accidents, loss of flow accident, etc. The analysis was carried out for the Israel Research Reactor 1 (IRR-1), which is a 5MW swimming pool type research reactor. The IRR-1 core consists of MTR highlyenriched uranium (HEU) fuel type, and is reflected by Graphite elements. During normal operation, the reactor core is cooled by downward forced flow of light water circulated by a primary cooling circuit pump. But during shutdown stage, the reactor core is cooled by upward natural convection flow through a safety flapper valve. There could be several primary causes to initiate a LOCA in research reactors, such as breaks in the piping system, ruptures of the beam tubes, and concrete wall failures of the reactor pool. Although probability of large break accident in research reactors is very low, once the accident occurs, it may cause major core damages, so it must be considered

  18. 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)

  19. Preliminary report about nuclear accident of Chernobylsk reactor

    The preliminary report of nuclear accident at Chernobyl, in URSS is presented. The Chernobyl site is located geographically and the RBMK type reactors - initials of russian words which mean high power pressure tube reactors are described. The conditions of reactor operation in beginning of accident, the events which lead to reactor destruction, the means to finish the fire, the measurements adopted by Russian in the accident location, the estimative of radioactive wastes, the meteorological conditions during the accident, the victims and medical assistence, the sanitary aspects and consequences for population, the evaluation of radiation doses received at small and medium distance and the estimative of reffered doses by population attained are presented. The official communication of Russian Minister Council and the declaration of IAEA general manager during a collective interview in Moscou are annexed. (M.C.K.)

  20. 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...

  1. 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

  2. Considerations of severe accidents in the design of Korean Next Generation Reactor

    The severe accident is one of the key issues in the design of Korean Next Generation Reactor (KNGR) which is an evolutionary type of pressurized water reactor. As IAEA recommends in TECDOC-801, the design objective of KNGR with regard to safety is provide a sound technical basis by which an imminent off-site emergency response to any circumstance could be practically unnecessary. To implement this design objective, probabilistic safety goals were established and design requirements were developed for systems to mitigate severe accidents. The basic approach of KNGR to address severe accidents is firstly prevent severe accidents by reinforcing its capability to cope with the design basis accidents (DBA) and further with some accidents beyond DBAs caused by multiple failures, and secondly mitigate severe accidents to ensure the retention of radioactive materials in the containment by providing mean to maintain the containment integrity. For severe accident mitigation, KNGR principally takes the concept of ex-vessel corium cooling. To implement this concept, KNGR is equipped with a large cavity and cavity flooding system connected to the in-containment refueling water storage tank. Other major systems incorporated in KNGR are hydrogen igniters and safety depressurization systems. In addition, the KNGR containment is designed to withstand the pressure and temperature conditions expected during the course of severe accidents. In this paper, the design features and status of system designs related with severe accidents will be presented. Also, R and D activities related to severe accident mitigation system design will be briefly described

  3. 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...

  4. Research on problems in nuclear accident emergency rescue for nuclear power submarine

    This paper presents a description of nuclearpowered submarine accident types and an analysis of accident emergency rescue characteristics, including a special number of problems associated with emergencyrescue, such as emergency situation and emergency planning zone, technical rescue resources and task, protection against compound radiation inside and outside port plume zone, on-sea nuclear rescue equipment and technical assurance capacity, and other problesms related to in-accident nuclear submarine disposal. (authors)

  5. Radiation accidents and their management: emphasis on the role of nuclear medicine professionals

    Bomanji, Jamshed B.; NOVRUZOV, Fuad; Vinjamuri, Sobhan

    2014-01-01

    Large-scale radiation accidents are few in number, but those that have occurred have subsequently led to strict regulation in most countries. Here, different accident scenarios involving exposure to radiation have been reviewed. A triage of injured persons has been summarized and guidance on management has been provided in accordance with the early symptoms. Types of casualty to be expected in atomic blasts have been discussed. Management at the scene of an accident has been described, with e...

  6. Development and application of calculational theoretical methods for analysis of the RBMK reactor severe accidents

    One studied high-improbable reactor emergencies that may result in a high consequence accident. To control these accidents and to mitigate their consequences one should study and analyze similar emergencies via detailed computer simulation. Application of foreign and Russian codes for RBMK type reactor should be associated with their supplementary verification. In that context one elaborated the table list of processes for supplementary verification of thermohydraulic models of codes designed to analyze severe accidents

  7. Accidents associated with oil and gas operations: Outer continental shelf, 1956-1990. Final report

    The report is a compilation of descriptions of all blowouts, explosions and fires, pipeline breaks or leaks, significant pollution incidents, and major accidents that occurred on federally leased offshore lands from 1956 through 1990. The report identifies accidents by area, block number, lease number, platform number, well number, and operator. It describes the type of accident, corrective action taken, and the amount of pollution. It provides figures on fatalities, injuries, and property and environmental damage

  8. The causes of the Chernobyl accident

    For the man in the street Chernobyl epitomizes the danger of nuclear energy but when we examine the causes of this accident we see that this drama is not intrinsically linked to the production of electricity from nuclear fission. The author sees 2 components in the Chernobyl event: the accident itself and its sanitary consequences. The author considers 3 main causes to the accident: -) a design that makes the reactor difficult to control, -) a series of 6 humane failures or breaking of operating rules, and -) political reasons: the largest possible budget was dedicated to plutonium production so any improvement for safety was considered as costly and secondary, moreover the religion of secrecy which was well spread in the ancient Soviet Union, prevented any scientific from knowing all the information concerning this type of reactor. As for the sanitary consequences, the author considers direct causes and underlying causes. The lack of information for the local population, the delay taken for iodine distribution or for the interdiction of farm products consumption are included in the direct causes. The slowness of Soviet bureaucracy, tight budgets and politico-scientific disputes are quoted among the underlying causes. (A.C.)

  9. Coping Capability of APR Against Fukushima Accidents

    Major threats on Fukushima Daiichi plant are earthquake, tsunami, SBO (Station Black Out), and hydrogen burning and explosion. Following the 9.1 magnitude earthquake, tsunami of 15m-height caused Emergency Diesel Generator (EDG) trouble and SBO. APR+ (Advanced Power Reactors Plus) has been basically designed to have the seismic design basis of Safe Shutdown Earthquake (SSE) 0.3g, a 4-train safety concept based on N+2 design philosophy, and a Passive Auxiliary Feedwater System (PAFS). Safety issues on the Fukushima-type accident have been extensively reviewed to enhance APR+ safety. After the review, many items was selected in the APR+ standard design to cope with the accidents. The items can be categorized as follows; Design of structure and equipment against earthquakes and coastal flooding, Integrity of electric power, cooling, and fire protection systems on inundation, Countermeasures against severe accident, and Emergency response and emergency medical systems. The key items include enhancement of seismic design for Main Control Room (MCR) and capability of cooling water intake, improvement of facilities entrance such as a water tight door against tsunami or flood, provision for external cooling water of PCCT (Passive Condensate Cooling Tank), diversity design for emergency electric power sources, and capability extension of a battery for supporting the 72-hour copying time. These items to enhance the safety will have been applied to the APR+ design. Consequently, APR+ can provide higher reliability and safety against tsunami and earthquake

  10. [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

  11. 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

  12. Scenarios simulation of severe accident type small loss of coolant (Loca), with the code MELCOR version 2.1 for the nuclear power plant of Laguna Verde; Simulacion de escenarios de accidente severo tipo perdida de refrigerante (Loca) pequeno, con el codigo MELCOR version 2.1 para la central nucleo-electrica de Laguna Verde

    Cardenas V, J.; Mugica R, C. A.; Godinez S, V., E-mail: Jaime.cardenas@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    In this work was carried out the analysis of two scenarios of the accident type with loss of coolant in a recirculation loop for a break with smaller ares to 0.1 ft{sup 2} (4.6 cm{sup 2}), which is classified according to their size like small Loca. The first simulated scenario was a small Loca without action of the emergency coolant injection systems, and the second was a small Loca with only the available system LPCS. This design base accident was taken into account for its relevance with regard to the damage to the core and the hydrogen generation. Was also observed and analyzed the response of the action of the ECCS that depend of the loss of coolant reason and this in turn depends of the size and type of the pipe break. The specified scenarios were simulated by means of the use of MELCOR model for the nuclear power plant of Laguna Verde that has the Comision Nacional de Seguridad Nuclear y Salvaguardias. (Author)

  13. Validation of severe accident management guidance for the wolsong plants

    Full text: Full text: The severe accident management(SAM) guidance has been developed for the Wolsong nuclear power plants in Korea. The Wolsong plants are 700MWe CANDU-type reactors with heavy water as the primary coolant, natural uranium-fueled pressurized, horizontal tubes, surrounded by heavy water moderator inside a horizontal calandria vessel. The guidance includes six individual accident management strategies: (1) injection into primary heat transport system (2) injection into calandria vessel (3) injection into calandria vault (4) reduction of fission product release (5) control of reactor building condition (6) reduction of reactor building hydrogen. The paper provides the approaches to validate the SAM guidance. The validation includes the evaluation of:(l) effectiveness of accident management strategies, (2) performance of mitigation systems or components, (3) calculation aids, (4) strategy control diagram, and (5) interface with emergency operation procedure and with radiation emergency plan. Several severe accident sequences with high probability is selected from the plant specific level 2 probabilistic safety analysis results for the validation of SAM guidance. Afterward, thermal hydraulic and severe accident phenomenological analyses is performed using ISAAC(Integrated Severe Accident Analysis Code for CANDU Plant) computer program. Furthermore, the experiences obtained from a table-top-drill is also discussed

  14. 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

  15. 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.)

  16. 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...

  17. 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

  18. 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...

  19. 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...

  20. 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...

  1. 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

  2. 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...

  3. 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...

  4. 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

  5. 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)

  6. 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)

  7. Core-melting accidents in Chernobyl and Harrisburg

    This publication deals with the essences of the reactor accident in Chernobylsk and the conclusions to be drawn from these with regard to reactor safety. Therein the technical differences between the reactor types in the West and the East play an important role. Also attention is spent to the now generally accepted philosophy that by simplification and making use of proven technologies, a further deminishing of the risks can be achieved step by step. In ch.'s 2 and 4 the origin and course of the accidents in respectively Chernobylsk and Harrisburg are analyzed; in the analysis of the Chernobylsk accident also date have been used which were provided by the Sovjet-Union, supplied with results of studies of the U.S. Department of Energy (DOE). In ch. 3 this information is compared with the insights which have grown at KEMA about these on the base of reactor physical and thermohydraulic considerations and of computer calculations reproducing the course of the accident. An important question is if, and if so: to which extent, an accident such as the one in Chernobylsk also can take place in the West. In order to answer that question as accurate as possible the consequences of core meltings accidents and the risk for such an accident taking place are pursued. In ch. 6 the legal frameworks are indicated by which the risk may be limited and by which eventually yet occurring damage may be arranged. Ch. 7 finally deals with the lessons which the accidents in Chernobylsk and Harrisburg have learnt us and with the possible consequences of these for the further application of nuclear power in the Netherlands. (H.W.). 105 refs.; 42 figs.; 17 refs

  8. 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

  9. 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)

  10. 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

  11. Coupled simulation of steam line break accident

    The steam line break is a PWR type reactor design accident, which concerns coupled physical phenomena. To control these problems simulation are needed to define and validate the operating procedures. The benchmark OECD PWR MSLB (Main Steam Line Break) has been proposed by the OECD to validate the feasibility and the contribution of the multi-dimensional tools in the simulation of the core transients. First the benchmark OECD PWR MSLB is presented. Then the analysis of the three exercises (system with pinpoint kinetic, three-dimensional core and whole system with three-dimensional core) are discussed. (A.L.B.)

  12. 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

  13. Radiological accidents: methodologies of radio nuclides dis incorporation

    Derived of the radioactive or nuclear material management, exists the risk that accidents can happen where people cases are presented with internal radioactive contamination, who will receive specialized medical care to accelerate the radioactive dis incorporation with the purpose of diminishing the absorbed dose and the associate biological effects. In this work treatments of radioactive dis incorporation were identified, in function of the radionuclide, radiation type, radioactive half life, biological half life, critical organ, ingestion duct and patient type. The factor time is decisive for the effectiveness of the selected treatment in the blockade stage (before the accident) or dis incorporation (after the accident); this factor is related with the radioactive and biological half lives. So to achieve dis incorporation efficiencies of more to 70%, the patient clinical treatment will begin before the first third of the biological half life of the radionuclide that generated the internal contamination. (Author)

  14. Handling of Radiation Accidents. Proceedings of a Symposium on the Handling of Radiation Accidents

    Many types of radiation accidents can theoretically be foreseen, ranging from minor spills of radioactive materials within a laboratory to serious accidents characterized by the presence of intense radiation fields and the uncontrolled release of large quantities of radioactive contaminants. They could lead to the irradiation and contamination of persons and the contamination of premises and the natural environment. As a result of the great emphasis that has been placed on safety in the development of nuclear energy programmes and in the use of radiation sources, accidents involving the serious overexposure of persons are in fact very rare. Nevertheless such accidents can occur and it is necessary to plan in advance for those that can be,reasonably foreseen. The handling of serious radiation accidents requires the co-operation of experts with diverse qualifications and experience: radiation monitoring and dosimetry specialists; medical doctors experienced in diagnosing and treating radiation injury; nuclear safety, decontamination and waste management specialists; public relations officers; and many others. This symposium, organized by the International Atomic Energy Agency and the World Health Organization as part of a co-ordinated programme, was designed to enable these specialists to discuss their problems on a very broad basis. The meeting was attended by 212 participants from 34 countries and 9 international organizations. In his opening address Professor Zheludev reminded the participants that the good safety record of the nuclear industry must not give rise to complacency and that we must all learn as much as possible from reported accidents in order to be ready to deal promptly and effectively with those that may be encountered in the future. It is noteworthy that some of the most severe injuries reported were suffered by persons who found lost-sources and carried them for long periods without any knowledge of the dangers involved. Organizational

  15. 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)

  16. Severe accident mitigation features of the economic simplified boiling water reactor

    This paper provides an overview of the Economic Simplified Boiling Water Reactor (ESBWR)severe accident mitigation systems. The major severe accident types are described and the systems credited for mitigating the severe accidents are discussed, including the Basemat Internal Melt Arrest Coolability (BiMAC) device, the Passive Containment Cooling System (PCCS), and the advantages of suppression pool water for scrubbing during containment venting. The ruggedness of the containment and reactor building designs for accommodating beyond design accident conditions is also discussed. (author)

  17. 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...

  18. ROLE OF COMPUTED TOMOGRAPHY IN CERBROVASCULAR ACCID ENT

    Kalra; Kiran

    2013-01-01

    ABSTRACT: Cerebrovascular accident is characterized by the s udden loss of blood circulation to an area of the brain resulting in a corresponding lo ss of neurologic function. Stroke is mainly of two types ischaemic or haemorrhagic and differentiat ion is important as the management differs substantially with the type of stroke. Aim o f the study was to compare the clinical diagnosis with computed tomography diagnosis and to d ifferentiate between the types of ...

  19. Some Examples of Accident Analyses for RB Reactor

    The RB reactor is heavy water critical assembly operated in the Vinca Institute of Nuclear Sciences, Belgrade, Yugoslavia, since April 1959. The first Safety Analysis Report of the RB critical assembly was prepared in 1961/62. But, the first accidental analysis was done in late 1958 in aim the examine power transient and total equivalent doses received by the staff during the reactivity accident occurred on October 15, 1958. Since 1960, the RB reactor is modified few times. Beside initial natural uranium metal fuel rods, new fuel (TVR-S types) from 2% enriched metal uranium and 80% enriched UO2 were available since 1962 and 1976, respectively. Also, modifications in control and safety systems of the reactor were done occasionally. Special reactor cores were created using all three types of fuel elements, among them, the coupled fast-thermal ones. Nuclear Safety Committee of the Vinca Institute, an independent regulatory body approved for usage all these modifications of the RB reactor. For those decisions of the Committee, the Preliminary Safety Analysis Reports were prepared that, beside proposed technical modifications and new regulation rules had included analyses of various possible accidents. Special attention is given and new methodology was proposed for thoroughly analyses of design based accidents related to coupled fast-thermal cores, that include reactor central zones filled by fuel elements without moderator. In these accidents, during assumed flooding of the fast zone by moderator, a very high reactivity could be inserted in the system with very high reactivity rate. It was necessary to provide that the safety system of the reactor had fast response to that accident and had enough high (negative) reactivity to shut down the reactor timely. In this paper, a brief overview of some accidents, methodology and computation tools used for the accident analyses at RB reactor are given. (author)

  20. Including Accident Information in Automatic Bicycle Route Planning for Urban Areas

    Alex D. Singleton

    2011-01-01

    Full Text Available Between 2005 and 2007 there were 9071 traffic accidents involving bicycles within London and this paper demonstrates the utility of Geographic Information Systems as a tool for analysing and visualising these occurrences. Through linkage of these spatial locations to a street network dataset it was possible to create a variety of intelligence about the types of street infrastructure where accidents predominantly occur. Additionally, a network routing algorithm was adapted to account for the frequency of accidents within a series of proposed journeys. This pilot routing application compared the quickest route with an accident avoidance weighted route between a series of origins and destinations. The results demonstrated that the routes avoiding areas of high accident volume did not increase journey length significantly; however they did provide a “safer” route based on empirical evidence over the volume of accident locations.

  1. The health impact of major nuclear accidents: the case of Greece.

    Kollas, J G

    1993-10-01

    An assessment of the radiological consequences that would result for the population of Greece from postulated major nuclear accidents in the Kozloduy nuclear power station in Bulgaria is performed. Kozloduy lies at a distance of 225 km from the northern borders of Greece and contains six reactors, all of the Russian WWER type. The postulated accidents that are classified as level 7 accidents on the International Nuclear Event Scale, involve significant releases of radioactive materials into the environment, and widespread health and environmental effects. The analysis is performed by the MACCS code. The estimated consequences are compared to the corresponding actual impact of the Chernobyl accident in Greece. The results of the analysis indicate that, under the conservative assumptions adopted, the radiological consequences of the most severe accidents considered would be about 1.5 orders of magnitude larger than the actual radiological consequences of the Chernobyl accident. PMID:8259439

  2. Arthropods of Medical Importance in Brazil: Retrospective Epidemiological Information about Accidents Involving these Animals

    Danon Clemes Cardoso

    2009-01-01

    Full Text Available Problem statement: The epidemiological information about arthropods bites/sting in Criciúma region no was reported. The aim of this Research was to draw the epidemiologic profile of accidents with arthropods in Criciúma region. Approach: The information regarding accidents with arthropods from 1994-2006 was prospectively collected from SINAN (System of Injury Notification Information files of the 21a Municipal Health Secretary of Criciúma region. Was calculated the frequency for each variable studied and incidence coefficient for period of study. Results: Results were recorded 1821 notifications of accidents with arthropods in region studied. The numbers of occurrence increased along of the years studied. The arthropod that most result in accidents was the spider with 1,126 (75.9% cases followed by Honeybees and others Arthropods with 149 (10.0% cases, Caterpillars including Lonomia genus and others genera (54/3.7% and scorpions with the least number of accidents with 6 (0.4% cases. The incidence of accidents every thousand inhabitants had a significant increase starting in the year of 2000. The majority of accidents occurred in the warmest months, increasing in the spring and summer seasons. Was recorded more than twice of accidents with arthropods in Urban area than in rural areas. The Chi-square test revealed that the frequency of accidents between locations and type of arthropods is different. Likewise, the number the victims and activity type in moment of the bite/sting had been a differ behavior between arthropods type. However, the number of accidents involving victims of male and female gender is equal. Conclusion: Epidemiological studies of this type in the extreme south of Santa Catarina are scarce. Only few studies have reported the patterns of occurrence and incidence of accidents with poisonous animals. These and other studies are of great importance for implementation of measures mitigation programs and education for

  3. Nuclear installations abroad the accident risks and their potential consequences

    This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of 'tolerable' risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid

  4. Emergency planning and preparedness for a nuclear accident

    Based on current regulations, FEMA approves each site-specific plan of state and local governments for each power reactor site after 1) formal review offsite preparedness, 2) holding a public meeting at which the preparedness status has been reviewed, and 3) a satisfactory joint exercise has been conducted with both utility and local participation. Annually, each state, within any position of the 10-mile emergency planning zone, must conduct a joint exercise with the utility to demonstrate its preparedness for a nuclear accident. While it is unlikely that these extreme measures will be needed as a result of an accident at a nuclear power station, the fact that these plans have been well thought out and implemented have already proven their benefit to society. The preparedness for a nuclear accident can be of great advantage in other types of emergencies. For example, on December 11, 1982, a non-nuclear chemical storage tank exploded at a Union Carbide plant in Louisiana shortly after midnight. More than 20,000 people were evacuated from their homes. They were evacuated under the emergency response plan formulated for use in the event of a nuclear accident at the nearby Waterford Nuclear plants. Clearly, this illustrates how a plan conceived for one purpose is appropriate to handle other types of accidents that occur in a modern industrial society

  5. Accidental knowledge: Using accidents and other project failures to inform research in systems engineering

    Sorenson, Diane C.

    Projects experience cost overruns, late deliveries, quality issues, cancellation, and accidents despite the best efforts of the systems engineering community. There is relatively little research on why systems engineering failures in general happen, but a substantial body of work on accident causation. Here, we investigate whether systems failures in general exhibit the same patterns of causation as accidents. We conducted a review of existing accident models to develop a model that could be applied to all types of project failures. Our model helped us to classify where the factors occur during the system development/system operation phases and which entity was involved in each factor. We analyzed 58 failure case studies. The failure cases span non-accidents, accidents, and dual failures. The sources for each subset had varying depth and scope of investigation. We developed a coding method to compare the factors between failure cases that broke each factor down into an "actor-action-object" structure. We further generalized the actions from the "actor-action-object" strings into control flaws so that we could analyze the failure cases at a high level. We analyzed the control flaws, actions, and actors for each failure case and compared the results for accidents and non-accidents. Of our results that we could not attribute to study biases, we found similarities and differences between project failure causation. We also identified which control flaws, actions, and actors were the most prevalent in the different types of project failures. Of all the actions, "failure to consider factor in system development" contributed most to non-accidents, while "failure to consider step in risk management" contributed the most to accidents. Of all the actors, "company management" contributed the most to non-accidents and accidents.

  6. Spent Fuel Pool Decommissioning After a Severe Accident. Appendix

    Most decommissioning related publications by the IAEA [A.1–A.4] and other organizations clearly specify that their scope applies to the decommissioning of nuclear facilities under planned conditions. It is generally specified that decommissioning of facilities that have been subject to a severe accident is excluded from the scope of these publications. This is because of the peculiar, and generally unpredictable, circumstances resulting from a severe accident, including, among others, high radiation and contamination fields, abnormal waste and unexpected configuration changes. Based on the literature, there is no unique definition of a severe accident. All definitions include various consequence (damage) types (evacuees, injured persons, fatalities or costs) and a minimum level for each damage type. The differences between the definitions concern both the set of specific consequence types considered and the damage threshold. For the purposes of this publication, the scope of this Appendix encompasses only facilities (spent fuel pools) that have been seriously contaminated and physically damaged to the point that planned routine decommissioning strategies and techniques are unusable or impractical. It should be noted that there are three phases typically associated with a post-accident phase: stabilization, recovery and decommissioning. Stabilization refers to the immediate aftermath of a nuclear accident, and implies controlling of conditions so that impacts to the environment and public are controlled and minimized. Recovery entails the planning and implementation of activities to limit, and subsequently reduce, the extent of abnormal conditions, and prepare the plant for achievement of a longer term, safer configuration. Recovery can be viewed as a precursor to decommissioning. However, there is no clear-cut line between the three above mentioned phases. In fact, conditions generated by the accident and its evolution may initially be recognized, faced and dealt

  7. An overview of LWR containment loadings during degraded core accidents

    An overview is given of the problem of determining pressure and temperature conditions in the containment following a degraded core accident, so that structural analysis can determine the requirements for an adequate evaluation of a containment under such conditions. Also examples are given of typical expected loadings for various reactor types and containment designs. (orig.)

  8. 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

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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...

  14. [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

  15. 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

  16. 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.

  17. Review of accident analyses of RB experimental reactor

    Pešić Milan P.

    2003-01-01

    Full Text Available The RB reactor is a uranium fuel heavy water moderated critical assembly that has been put and kept in operation by the VTNCA Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro, since April 1958. The first complete Safety Analysis Report of the RB reactor was prepared in 1961/62 yet, the first accident analysis had been made in late 1958 with the aim to examine a power transition and the total equivalent doses received by the staff during the reactivity accident that occurred on October 15, 1958. Since 1960, the RB reactor has been modified a few times. Beside the initial natural uranium metal fuel rods, new types of fuel (TVR-S types of Russian origin consisting of 2% enriched uranium metal and 80% enriched UO2 dispersed in aluminum matrix, have been available since 1962 and 1976 respectively. Modifications of the control and safety systems of the reactor were made occasionally. Special reactor cores were designed and constructed using all three types of fuel elements as well as the coupled fast-thermal ones. The Nuclear Safety Committee of the VINĆA Institute, an independent regulatory body, approved for usage all these modifications of the RB reactor on the basis of the Preliminary Safety Analysis Reports, which, beside proposed technical modifications and new regulation rules, included safety analyses of various possible accidents. A special attention was given (and a new safety methodology was proposed to thorough analyses of the design-based accidents related to the coupled fast-thermal cores that included central zones of the reactor filled by the fuel elements without any moderator. In this paper, an overview of some accidents, methodologies and computation tools used for the accident analyses of the RB reactor is given.

  18. Thermal and hydraulic behaviour of CANDU cores under severe accident conditions

    This report describes work performed for the Atomic Energy Control Board on a) Formation and rewetting of dry patches on CANDU reactor calandria tubes during a Loss-of-Coolant Accident, and b) Analysis of accident sequence S11: Loss-of-Coolant Accident plus Loss-of-Emergency Core Cooling plus loss of moderator cooling system. For part (a), it is concluded that any dry patches which form on calandria tubes as a result of local heating to the critical heat flux will rewet in a short time (10 to 30 seconds for a Bruce-type reactor, 90 seconds for a Douglas Point-type reactor), with negligible effects on fuel sheath and maximum pressure tube temperatures. Pressure tube integrity is not predicted to be threatened. For part (b), preliminary analysis of the S11 accident sequence is presented. The complete analysis follows in the final report on the effects of severe accidents on CANDU cores

  19. 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)

  20. 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).

  1. 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

  2. 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

  3. 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.

  4. 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)

  5. 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.

  6. 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.

  7. 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.

  8. 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)

  9. 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)

  10. 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.)

  11. Time-dependent accident sequences including human actions

    During an accident, transitions between plant states can occur due to operator intervention and the failure of systems while running. The latter cause of transition is much less likely than the first, which includes errors of commission and omission as well as recovery of lost functions. A methodology has been developed to model these transitions in the time domain. As an example, it is applied to the analysis of Three-Mile-Island-type accidents. Statistical evidence is collected and used in assessing the frequency of stuck-open power-operated relief valves at Babcock and Wilcox plants as well as the frequency of misdiagnosis. Statistical data are also used in modeling the timing of operator actions during the accident, i.e., turning off and on the high-pressure injection system and closing the block valves

  12. Plant specific severe accident management - the implementation phase

    Many plants are in the process of developing on-site guidance for technical staff to respond to a severe accident situation severe accident management guidance (SAMG). Once the guidance is developed, the SAMG must be implemented at the plant site, and this involves addressing a number of additional aspects. In this paper, approaches to this implementation phase are reviewed, including review and verification of plant specific SAMG, organizational aspects and integration with the emergency plan, training of SAMG users, validation and self-assessment and SAMG maintenance. Examples draw on experience from assisting numerous plants to implement symptom based severe accident management guidelines based on the Westinghouse Owners Group approach, in Westinghouse, non-Westinghouse and VVER plant types. It is hoped that it will be of use to those plant operators about to perform these activities.(author)

  13. The willingness to pay of parties to traffic accidents for loss of productivity and consolation compensation.

    Jou, Rong-Chang; Chen, Tzu-Ying

    2015-12-01

    In this study, willingness to pay (WTP) for loss of productivity and consolation compensation by parties to traffic accidents is investigated using the Tobit model. In addition, WTP is compared to compensation determined by Taiwanese courts. The modelling results showed that variables such as education, average individual monthly income, traffic accident history, past experience of severe traffic accident injuries, the number of working days lost due to a traffic accident, past experience of accepting compensation for traffic accident-caused productivity loss and past experience of accepting consolation compensation caused by traffic accidents have a positive impact on WTP. In addition, average WTP for these two accident costs were obtained. We found that parties to traffic accidents were willing to pay more than 90% of the compensation determined by the court in the scenario of minor and moderate injuries. Parties were willing to pay approximately 80% of the compensation determined by the court for severe injuries, disability and fatality. Therefore, related agencies can use our study findings as the basis for determining the compensation that parties should pay for productivity losses caused by traffic accidents of different types. PMID:26363088

  14. 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

  15. Challenges in thermohydraulic analysis of LWR severe accidents: steam explosions

    A severe accident is an accident state beyond design basis events with significant core damage and release of radioactive materials to the environment. Nuclear power plants are designed to endure prescribed accident situations against which safety equipment should be effective enough to assure that environmental release of radioactive materials is avoided. However, three major severe accidents have already experienced in commercial scale power plants so far, namely, Three Mile Island (TMI), Chernobyl and Fukushima Daiichi. Thus, the severe accident is no more just a hypothesis but a reality that have to be prepared with enough effectivity. A method for assessment of steam explosion load has been established based on presently available phenomenological information and simulation technique. On the 3 other hand, the present model is not sufficient for slow long term FCIs in which the steam and non-condensable gas generation rate for vessel pressurization and the resulting debris bed geometry for its coolability are in question. Also, there are shortcomings from the present analytical method such as influences of the mesh size on the void fraction, lacking radiation heat transfer beyond meshes and so on. If the level of the model is upgraded to CFD type including more flexible particle methods, direct simulation of complicated phenomena involving molten core, may become available. This may be one of the directions of future development

  16. Severe accident countermeasure plan (draft) for nuclear power plants

    Nuclear power plants should be designed, constructed, and operated properly so that the likelihood of occurrence of a severe accident and its consequence may be minimized. The Korea Institute of Nuclear Safety has been reviewing the Nuclear Safety Policy Statement and the preceding severe accident countermeasure plan and prepared a new draft plan in order to provide a reasonable regulatory position for severe accidents. This plan has been prepared by taking into account the different reactor types and the characteristics of operating plants, new plants using the existing design, and new ones including the next generation plants. The major elements included in the plan are: establishment and application of the safety goal, performance of the probabilistic safety assessment and establishment of countermeasure plans for the vulnerabilities, provisions for severe accidents prevention and mitigation capability, set-up of a severe accident management program implementation system. Each element has been set up to move progressively toward an upgrading in safety of currently operating plants and future ones

  17. Analyzing the severity of accidents on the German Autobahn.

    Manner, Hans; Wünsch-Ziegler, Laura

    2013-08-01

    We study the severity of accidents on the German Autobahn in the state of North Rhine-Westphalia using data for the years 2009 until 2011. We use a multinomial logit model to identify statistically relevant factors explaining the severity of the most severe injury, which is classified into the four classes fatal, severe injury, light injury and property damage. Furthermore, to account for unobserved heterogeneity we use a random parameter model. We study the effect of a number of factors including traffic information, road conditions, type of accidents, speed limits, presence of intelligent traffic control systems, age and gender of the driver and location of the accident. Our findings are in line with studies in different settings and indicate that accidents during daylight and at interchanges or construction sites are less severe in general. Accidents caused by the collision with roadside objects, involving pedestrians and motorcycles, or caused by bad sight conditions tend to be more severe. We discuss the measures of the 2011 German traffic safety programm in the light of our results. PMID:23628941

  18. Best practices to reduce the accident rate hotel

    García Revilla, M. R.; Kahale Carrillo, D. T.

    2014-10-01

    Examining the available databases and existing tourism organizations can conclude that appear studies on accidents and their relationship with other variables. But in our case we want to assess this relationship in the performance of the hotel in relation to lower the accident rate. The Industrial Safety studies analyzing this accident causes (why they happen), their sources (committed activities), their agents (participants work means), its type (how the events occur or develop), all in order to develop prevention. In our case, as accidents happen because people commit wrongful acts or because the equipment, tools, machinery or workplaces are not in proper conditions, the preventive point of view we analyze through the incidence of workplace accidents hotel subsector. The crash occurs because there is a risk, so that adequate control of it would avoid despite individual factors. Absenteeism or absence from work was taken into account first by Dubois in 1977, as he realized the time lost in the nineteenth century due to the long working hours, which included the holidays. Motivation and job satisfaction were the elements that have been most important in the phenomenon of social psychology.

  19. Radiological Impact Assessment (RIA) following a postulated accident in PHWRS

    Soni, N.; Kansal, M.; Rammohan, H. P.; Malhotra, P. K. [Reactor Safety and Analysis, Nuclear Power Corporation of India Ltd., Nabhkiya Urja Bhavan, Anushakti Nagar, Mumbai Maharashtra 400094 (India)

    2012-07-01

    Radiological Impact Assessment (RIA) following postulated accident i.e Loss of Coolant Accident (LOCA) with failed Emergency Core Cooling System (ECCS), performed as part of the reactor safety analysis of a typical 700 MWe Indian Pressurized Heavy Water Reactor(PHWR). The rationale behind the assessment is that the public needs to be protected in the event that the postulated accident results in radionuclide release outside containment. Radionuclides deliver dose to the human body through various pathways namely, plume submersion, exposure due to ground deposition, inhalation and ingestion. The total exposure dose measured in terms of total effective dose equivalent (TEDE) is the sum of doses to a hypothetical adult human at exclusion zone boundary by all the exposure pathways. The analysis provides the important inputs to decide upon the type of emergency counter measures to be adopted during the postulated accident. The importance of the various pathways in terms of contribution to the total effective dose equivalent(TEDE) is also assessed with respect to time of exposure. Inhalation and plume gamma dose are the major contributors towards TEDE during initial period of accident whereas ingestion and ground shine dose start dominating in TEDE in the extended period of exposure. Moreover, TEDE is initially dominated by I-131, Kr-88, Te-132, I-133 and Sr-89, whereas, as time progresses, Xe-133,I-131 and Te-132 become the main contributors. (authors)

  20. 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.

  1. A Scenario Proposal For A Radioactive Waste Transport Accident

    In spite of all precautions that being taken during radioactive materials transport accidents to ensure safe transportation of these materials; there is still a probability for accidents to occur which, may be accompanied by injury or death of persons and damage of property So, in response to the increasing possibilities of accidents in Egypt, the government had prepared an emergency response plan for radiological accidents to coordinate the response efforts of all the national agencies. Trends for use of the radioactive materials and sources inside the country for the purpose of medical diagnosis and treatment as well as in industrial applications, are increasing. The radioactive waste resulted from these activities are transported from the centres where these materials being used to the waste management facility where they are treated and finally disposed safely at disposal site. The aim of the emergency exercise scenario is to test not only the main components of the emergency plan but also the level of emergency preparedness; that is the effectiveness with which the actions or combined actions of the different organizations involved in an emergency can be put into practice. The motivation of the present paper was undertaken to give a scenario proposal for the radiological emergency actions taken in case of a transport accident for a radioactive waste material (type A- package ) transported by a vehicle from one of the medical centers to a disposal site, 40 km northeast of cairo

  2. Severe accidents due to windsurfing in the Aegean Sea.

    Kalogeromitros, A; Tsangaris, H; Bilalis, D; Karabinis, A

    2002-06-01

    Windsurfing is a popular sport and has recently become an Olympic event. As an open-air water activity that requires the participant to be in perfect physical condition, windsurfers may be prone to accidents when certain basic rules or procedures are violated. The current study monitored severe injuries due to windsurfing over a period of 12 months in the Aegean Sea in Greece. Our study revealed 22 cases of severe accidents due to windsurfing, with a wide range of injuries including head injuries, spinal cord injuries, and severe fractures of the extremities. Prolonged hospitalization, severe disability and two deaths occurred as consequences of these accidents. The study examined the characteristics of these patients and the possible risk factors and conditions associated with the accidents. We also focused on the most common types of injuries and reviewed the mechanisms that may provoke them. Water sports and particularly windsurfing represent a major challenge for the emergency medical system, especially in the Aegean Sea. Hundreds of islands, kilometres of isolated coasts, millions of tourists, an extended summer period and rapidly changing weather create conditions that constantly test the efficacy of the emergency services. The development of an appropriate infrastructure and maximum control of the risk factors causing these accidents could reduce the morbidity and mortality that, unfortunately but rather predictably, accompany this popular summer activity. PMID:12131638

  3. Analysis of the radiation accident in El Salvador

    On 5 February 1989 at 2 a.m. local time in a cobalt-60 industrial irradiation facility, a series of events started leading to one of the most serious radiation accidents in this type of installation. It took place in Soyapango, a city situated 5 km from San Salvador, the capital of the Republic of El Salvador. In this accident, three workers were involved in the first event and a further four in the second. When the accident took place, the activity level was approximately 0.66 PBq (18,000 Ci). The source became blocked when being lowered to its safe position, where upon the technician responsible for the irradiator entered the chamber in breach of the few inadequate safety procedures, accompanied by two colleagues from an adjacent department; the three workers suffered acute radiation exposure, with the result that one of them died six-and-a-half months later, the second had both his legs amputated at mid-thigh, while the third recovered completely. This article describes the irradiator, outlines the causes of the accident and analyses the economic and social repercussions, with the aim of helping teams responsible for radiation protection and safety in industrial irradiation facilities to identify potentially hazardous circumstances and avoid accidents. (author)

  4. Theories of radiation effects and reactor accident analysis

    Muckerheide's paper was a public breakthrough on how one might assess the public health effects of low-level radiation. By the organization of a wealth of data, including the consequences of Hiroshima and Nagasaki but not including Chernobyl, he was able to conclude that present radioactive waste disposal and cleanup efforts need to be much less arduous than forecast by the U.S. Department of Energy, which, together with regulators, uses the linear hypothesis of radiation damage to humans. While the linear hypothesis is strongly defended and even recommended for extension to noncarcinogenic pollutants, exploration of a conservative threshold for very low level exposures could save billions of dollars in disposing of radioactive waste, enhance the understanding of reactor accident consequences, and assist in the development of design and operating criteria pertaining to severe accidents. In this context, the authors discuss the major differences between design-basis and severe accidents. The authors propose that what should ultimately be done is to develop a regulatory formula for severe-accident analysis that relates the public health effects to the amount and type of radionuclides released and distributed by the Chernobyl accident. Answers to the following important questions should provide the basis of this study: (1) What should be the criteria for distinguishing between design-basis and severe accidents, and what should be the basis for these criteria? (2) How do, and should, these criteria differ for older plants, newer operating plants, type of plant (i.e., gas cooled, water cooled, and liquid metal), advanced designs, and plants of the former Soviet Union? (3) How safe is safe enough?

  5. 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)

  6. 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...

  7. 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)...

  8. 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

  9. 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)

  10. Reflections on liability and radiological or nuclear accidents: the accidents at Goiania, Forbach, three mile Island and Chernobyl

    On the basis of the lessons learned today from, amongst others, the radiological accidents of Goiania in 1987 and Forbach in 1991, as well as the nuclear accident at Three Miles Island (T.M.I.) in 1979, this article tries to make a distinction between problems of liability linked, on the one hand, to the sanctioning of the absence of prevention implied by the occurrence of non-stochastic effects and, on the other hand, to the judicial sanctioning of the failure of precautionary measures taken, as regard stochastic effects. Lastly, over and above the type of damage compensated, liability also gives rise to some thoughts, in light of the experience of Chernobyl, about the impact of modes of compensation on the management of post-accident situations in areas affected over the long term by persisting contamination and the radiological risk associated with it. (N.C.)

  11. Transportation accident response of a high-capacity truck cask for spent fuel

    Two of the primary goals of this study were (i) to check the structural and thermal performance of the GA-4 cask in a broad range of accidents and (ii) to carry out a severe-accidents analysis as had been addressed in the Modal Study but now using a specific recent cask design and using current-generation computer models and capabilities. At the same time, it was desired to compare the accident performance of the Ga-4 cask to that of the generic truck cask analyzed in the Modal Study. The same range of impact and fire accidents developed in the Modal Study was adopted for this study. The accident-description data base of the Modal Study categorizes accidents into types of collisions with mobile or fixed objects, non-collision accidents, and fires. The mechanical modes of damage may be via crushing, impact, or puncture. The fire occurrences in the Modal Study data are based on truck accident statistics. The fire types are taken to be pool fires of petroleum products from fuel tanks and/or cargoes

  12. 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.

  13. 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)

  14. 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)

  15. 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

  16. 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.)

  17. Statistical description of heavy truck accidents on representative segments of interstate highway

    Hartman, W.F.; Davidson, C.A.; Foley, J.T.

    1977-01-01

    Any quantitative analysis of the risk of transportation accidents requires the use of many different statistical distributions. Included among these are the types of accidents which occur and the severity of these when they do occur. Several previous studies have derived this type of information for truck traffic over U. S. highways in general; these data are not necessarily applicable for the anticipated LMFBR spent fuel cask routes. This report presents data for highway segments representative of the specific LMFBR cask routes which are anticipated. These data are based upon a detailed record-by-record review of filed reports for accidents which occurred along the specified route segments.

  18. Statistical description of heavy truck accidents on representative segments of interstate highway

    Any quantitative analysis of the risk of transportation accidents requires the use of many different statistical distributions. Included among these are the types of accidents which occur and the severity of these when they do occur. Several previous studies have derived this type of information for truck traffic over U. S. highways in general; these data are not necessarily applicable for the anticipated LMFBR spent fuel cask routes. This report presents data for highway segments representative of the specific LMFBR cask routes which are anticipated. These data are based upon a detailed record-by-record review of filed reports for accidents which occurred along the specified route segments

  19. 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...

  20. 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.

  1. Iodine behaviour in severe accidents

    Dutton, L.M.C.; Grindon, E.; Handy, B.J.; Sutherland, L. [NNC Ltd., Knutsford (United Kingdom); Bruns, W.G.; Sims, H.E. [AEA Technology, Harwell (United Kingdom); Dickinson, S. [AEA Technology, Winfrith (United Kingdom); Hueber, C.; Jacquemain, D. [IPSN/CEA, Cadarache, Saint Paul-Lez-Durance (France)

    1996-12-01

    A description is given of analyses which identify which aspects of the modelling and data are most important in evaluating the release of radioactive iodine to the environment following a potential severe accident at a PWR and which identify the major uncertainties which affect that release. Three iodine codes are used namely INSPECT, IODE and IMPAIR, and their predictions are compared with those of the PSA code MAAP. INSPECT is a mechanistic code which models iodine behaviour in the aqueous aerosol, spray water and sump water, and the partitioning of volatile species between the aqueous phases and containment gas space. Organic iodine is not modelled. IODE and IMPAIR are semi-empirical codes which do not model iodine behaviour in the aqueous aerosol, but model organic iodine. The fault sequences addressed are based on analyses for the Sizewell `B` design. Two types of sequence have been analysed.: (a) those in which a major release of fission products from the primary circuit to the containment occur, e.g. a large LOCAS, (b) those where the release by-passes the containment, e.g. a leak into the auxiliary building. In the analysis of the LOCA sequences where the pH of the sump is controlled to be a value of 8 or greater, all three codes predict that the oxidation of iodine to produce gas phase species does not make a significant contribution to the source term due to leakage from the reactor building and that the latter is dominated by iodide in the aerosol. In the case where the pH of the sump is not controlled, it is found that the proportion of gas phase iodine increases significantly, although the cumulative leakage predicted by all three codes is not significantly different from that predicted by MAAP. The radiolytic production of nitric acid could be a major factor in determining the pH, and if the pH were reduced, the codes predict an increase in gas phase iodine species leaked from the containment. (author) 4 figs., 7 tabs., 13 refs.

  2. FRACTAL DIMENSIONS FOR RADIOISOTOPE POLLUTION PATTERNS BY NUCLEAR POWER PLANT ACCIDENTS

    Saito, K.; Ogawa, S.

    2015-01-01

    The radioisotope pollution shows two types of patterns: dry and wet deposits for nuclear power plant accidents. Two surface pollution patterns were analysed by fractal. In Fukushima nuclear power plant accident, surface pollution by wet deposits was estimated to occur. However, actually it was no rain and white crystals were observed on the surface. Then, fractal analysis was carried out for the spatial distribution patterns of radio isotopes on the surface to judge the types of depo...

  3. 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

  4. Airway accidents in critical care unit: A 3-year retrospective study in a Public Teaching Hospital of Eastern India

    Sugata Dasgupta

    2016-01-01

    Full Text Available Background: Although tracheal tubes are essential devices to control and protect airway in a critical care unit (CCU, they are not free from complications. Aims: To document the incidence and nature of airway accidents in the CCU of a government teaching hospital in Eastern India. Methods: Retrospective analysis of all airway accidents in a 5-bedded (medical and surgical CCU. The number, types, timing, and severity of airway accidents were analyzed. Results: The total accident rate was 19 in 233 intubated and/or tracheostomized patients over 1657 tube days (TDs during 3 years. Fourteen occurred in 232 endotracheally intubated patients over 1075 endotracheal tube (ETT days, and five occurred in 44 tracheostomized patients over 580 tracheostomy TDs. Fifteen accidents were due to blocked tubes. Rest four were unplanned extubations (UEs, all being accidental extubations. All blockages occurred during night shifts and all UEs during day shifts. Five accidents were mild, the rest moderate. No major accident led to cardiorespiratory arrest or death. All blockages occurred after 7th day of intubation. The outcome of accidents were more favorable in tracheostomy group compared to ETT group (P = 0.001. Conclusions: The prevalence of airway accidents was 8.2 accidents per 100 patients. Blockages were the most common accidents followed by UEs. Ten out of the 15 blockages and all 4 UEs were in endotracheally intubated patients. Tracheostomized patients had 5 blockages and no UEs.

  5. 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...

  6. 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....

  7. 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....

  8. On the nature of risk and accidents

    By consensus, 'errors of omission' and 'errors of commission' have their origin in the human rather than in the technological parts of the system. It has therefore been customary to base explanations on the available psychological 'error models', which mostly have been of the human information processing and internal 'error mechanisms' type. Yet the fact that an 'error of commission' necessarily involves a human action does not mean that the explanation, hence the modelling, must be confined to human functions - cognitive or otherwise. On the contrary, the experience from accident analyses as well as state-of-the-art HRA approaches all emphasize that action failures reflect the impact of the working conditions more than any specific mechanism'. This corresponds to a change in accident models from sequential, over epidemiological, to systemic. According to the latter, action failures - or action error modes - should be seen as the irregular, but not totally random, outcome of the system's performance variability rather than as specific effects of specific causes. This change in perspective have significant consequences for the ways in which action error modes are modelled and classified, and therefore also for the methods that can be used for prediction. (author)

  9. Several accidents about ERHRS of CEFR

    An analysis of about several unusual accidents about Emergency Residual Heat Removal System (ERHRS) of China Experiment Fast Reactor (CEFR) is presented. CEFR is a pool-type sodium-cooled fast reactor. The ERHRS of this reactor is designed in passive principle, which enhances the interior reliability of CEFR. It consists of two sets of independent channels. Each channel is comprised of decay heat exchanger (DHX), intermediate circuit, sodium-air heat exchanger (AHX) and related auxiliary system. Both DHX are located in the hot pool of the main vessel directly, which is used to cool the hot sodium. The whole set of ERHRS is completely passive except the ventilation valves of AHX. But, as a very important set of engineered safety features which is the final way to remove the heat from the reactor core, it is necessary to pay attention to all of the possibilities that may reduce this ability. Several accidents are analyzed including when the ventilation valves couldn't be opened, when only one set of ERHRS could work and so on. The calculation results show that the ERHRS can keep the reactor in a safety status. Even though it is, experiments are still necessary in the view of engineering. (author)

  10. Potentialities of robots in major accident situations

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

  11. OSSA - An optimized approach to severe accident management: EPR application

    There is a recognized need to provide nuclear power plant technical staff with structured guidance for response to a potential severe accident condition involving core damage and potential release of fission products to the environment. Over the past ten years, many plants worldwide have implemented such guidance for their emergency technical support center teams either by following one of the generic approaches, or by developing fully independent approaches. There are many lessons to be learned from the experience of the past decade, in developing, implementing, and validating severe accident management guidance. Also, though numerous basic approaches exist which share common principles, there are differences in the methodology and application of the guidelines. AREVA/Framatome-ANP is developing an optimized approach to severe accident management guidance in a project called OSSA ('Operating Strategies for Severe Accidents'). There are still numerous operating power plants which have yet to implement severe accident management programs. For these, the option to use an updated approach which makes full use of lessons learned and experience, is seen as a major advantage. Very few of the current approaches covers all operating plant states, including shutdown states with the primary system closed and open. Although it is not necessary to develop an entirely new approach in order to add this capability, the opportunity has been taken to develop revised full scope guidance covering all plant states in addition to the fuel in the fuel building. The EPR includes at the design phase systems and measures to minimize the risk of severe accident and to mitigate such potential scenarios. This presents a difference in comparison with existing plant, for which severe accidents where not considered in the design. Thought developed for all type of plants, OSSA will also be applied on the EPR, with adaptations designed to take into account its favourable situation in that field

  12. 25 years since Chernobyl nuclear accident

    000 Bq/l. After decrease of I-131 activity, especially by decay, a special attention was paid to cesium radionuclides (Cs-134 and Cs-137) detected in food (dairy, meat, vegetables and fruits, etc.) with activities of about 100 Bq/kg. The level of contamination of the environment, drinking water and food decreased over years after accident, so in the early 90's the measurement values returned to levels existing before the accident, excepting Cs-137. This radionuclide is still present in the environment, especially in soil. The lowest values are in the cultivated soil, and the highest in the uncultivated soil, forest soil and in some mountain areas. Although the transfer of Cs-137 in vegetation is low, yet it can be easily detected in some plants from natural ecosystems (spontaneous mushrooms, berries etc.) and quite difficult in food (at levels of mBq order). Current level of contamination of the environment and food in Romania after the Chernobyl nuclear accident is very low, making it difficult to highlight the two long-life contaminants, Cs-137 and Sr-90 that can be measured only by laboratories who have performing equipment and can perform radiochemical analyses. Quantifying the levels of contamination throughout Romania allowed assessing the doses received by the population and hence the analysing the effects (birth defects, leukemia and thyroid cancer) and carrying epidemiological studies on various types of diseases attributed to incorporation of radionuclides in particular in the target group of children. (authors)

  13. Computerised severe accident management aids

    The OECD Halden Reactor Project in Norway is running two development projects in the area of computerised accident management in cooperation with the Swedish nuclear plant Forsmark unit 2. Also other nuclear organisations in the Nordic countries take part in the projects. The SAS II system is installed at Forsmark and is now being validated against the plant compact simulator and is later to be installed in the plant control room. It is designed to follow all defined critical safety functions in the same manner as is done in the functionally oriented Emergency Operating Procedures. The shift supervisor thus uses SAS II as a complementary information system after a plant disturbance . The plant operators still use the ordinary instrumentation and the event oriented procedures. This gives to a high extent both redundancy and diversity in information channels and in procedures. Further, a new system is under discussion which goes a step further in accident management than SAS II. It is called the Computerised Accident Management Support (CAMS) system. The objective is to make a computerised tool that can assist both the control room crew and the technical support centre in accident mitigation, especially in the early stages of an accident where the integrity of the core still can be maintained if proper counteractions to the accident sequence are taken. In CAMS another approach is taken than in SAS II by putting the process parameters in focus. A more elaborate signal validation is proposed. The validated signals are input to models that calculates mass and energy balances of the primary system. Among parameters calculated are residual heat. Experiences from these two approaches to computerised accident management support are presented and discussed. In summary: The original project proposal aimed particularly for operator and TSC support during severe accidents. In the CAMS design proposal we have, however, promoted the SMABRE code which is not designed for such

  14. Safety characteristics of mid-sized MOX fueled liquid metal reactor core of high converter type in the initiating phase of unprotected loss of flow accident. Effect of low specific fuel power density on ULOF behavior brought by employment of large diameter fuel pins

    Safety characteristics in core disruptive accidents (CDAs) of mid-sized MOX fueled liquid metal reactor core of high converter type have been examined by using the CDA initiating phase analysis code SAS4A. The design concept of high converter type reactor core has been studied as one of options in the category of sodium-cooled reactor in Phase II of Feasibility Study on Commercialized Fast Reactor Cycle System. An unprotected loss-of-flow accident (ULOF) has been selected as a representative CDA initiator for this study. A core concept of high converter type, which employed a large diameter fuel pin of 11.1 mm with 1.2 m core height to get a large fuel volume fraction in the core to achieve high internal conversion ratio was proposed in JFY2001. Each fuel subassembly of the core (abbreviated here as UPL120)was provided with an upper sodium plenum directly above the core to reduce the sodium void reactivity worth. Because of the large fuel pin diameter, average specific fuel power density (31 kW/kg-MOX) of UPL120 is about one half of those of conventional large MOX cores. The reactivity worth of sodium voiding is 6$ in the whole core, and -1$ in the all upper plenums. Initiating phase of ULOF accident in UPL120 under the conditions of nominal design and best estimate analysis resulted in a slightly super-prompt critical power burst. The causes of the super-prompt criticality have been identified twofold: (a) the low specific fuel power density of core reduced the effectiveness of prompt negative reactivity feedback of Doppler and axial fuel expansion effects upon increase in reactor power, and (b) the longer core height compared with conventional 1m cores brought, together with the lower specific power density, a remarkable delay in insertion of negative fuel dispersion reactivity after the onset of fuel disruption in sodium voided subassembly due to the lower linear heat rating in the top portion of the core. During the delay, burst-type fuel failures in sodium un

  15. 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 known to us, the various road locations are treated as isolated spots. With small accident figures it is difficult to detect such places in the known procedures. An alternative procedure starts from...

  16. Occupational accidents in Turkey and providing and development of safety culture in preventing occupational accidents

    Dursun, Salih

    2011-01-01

    Occupational accidents cause socially and economically significant loss both in developed and developing countries. According to ILO each year, 2.2 million people lost their lives in the occupational accident. In Turkey, over 1600 people die in these accidents every year. In this case, an important part of occupational accidents like 95% based on “human”, requires more people-oriented approaches towards the prevention of accidents. In this context, to provide and develop the safety culture, w...

  17. Use of PSA and severe accident assessment results for the accident management

    The objectives for this study are to investigate the basic principle or methodology which is applicable to accident management, by using the results of PSA and severe accident research, and also facilitate the preparation of accidents management program in the future. This study was performed as follows: derivation of measures for core damage prevention, derivation of measures for accident mitigation, application of computerized tool to assess severe accident management

  18. 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

  19. 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

  20. Road Traffic Accident Patterns: A Conceptual Grouping Approach to Evaluate Crash Clusters

    Nowakowska, Marzena

    2012-03-01

    The aim of the work is to highlight road traffic accident patterns in the context of interrelations between road characteristics and a traffic safety threat. The actual data concerning multi-vehicle accidents without pedestrians on non-urban roads in a chosen region of Poland was the subject of the research. The roadway and roadside data at the accident site have been combined with the crash data that define the roadway hazard, i.e. driver's behaviour, type and accident severity. The data were subject to multivariate segmentation by means of such conceptual grouping techniques as the K-means clustering algorithm and competitive artificial neural networks. The Ward's method was used as a supporting tool in establishing the final number of accident profiles. Six distinct accident patterns have been recognised, quantified and labelled, where the first, second and third one are typical of rural areas, the fourth and fifth - of built-up areas, and the last one - of intersections. The analysis indicates that apart from threat factors, the following road related features play an important role in road accident profiling tasks: area type and area development level, roadway surface condition, intersection indicator, shoulder type, and also to some extent: lighting conditions, shoulders' width, and horizontal curve radius.

  1. Development of TRAIN for accident management

    Severe accident management can be defined as the use of existing and alternative resources, systems, and actions to prevent or mitigate a core-melt accident in nuclear power plants. TRAIN (Training pRogram for AMP In NPP), developed for training control room staff and the technical group, is introduced in this paper. The TRAIN composes of phenomenological knowledge base (KB), accident sequence KB and accident management procedures with AM strategy control diagrams and information needs. This TRAIN might contribute to training them by obtaining phenomenological knowledge of severe accidents, understanding plant vulnerabilities, and solving problems under high stress. (author)

  2. Cost per severe accident as an index for severe accident consequence assessment and its applications

    The Fukushima Accident emphasizes the need to integrate the assessments of health effects, economic impacts, social impacts and environmental impacts, in order to perform a comprehensive consequence assessment of severe accidents in nuclear power plants. “Cost per severe accident” is introduced as an index for that purpose. The calculation methodology, including the consequence analysis using level 3 probabilistic risk assessment code OSCAAR and the calculation method of the cost per severe accident, is proposed. This methodology was applied to a virtual 1,100 MWe boiling water reactor. The breakdown of the cost per severe accident was provided. The radiation effect cost, the relocation cost and the decontamination cost were the three largest components. Sensitivity analyses were carried out, and parameters sensitive to cost per severe accident were specified. The cost per severe accident was compared with the amount of source terms, to demonstrate the performance of the cost per severe accident as an index to evaluate severe accident consequences. The ways to use the cost per severe accident for optimization of radiation protection countermeasures and for estimation of the effects of accident management strategies are discussed as its applications. - Highlights: • Cost per severe accident is used for severe accident consequence assessment. • Assessments of health, economic, social and environmental impacts are included. • Radiation effect, relocation and decontamination costs are important cost components. • Cost per severe accident can be used to optimize radiation protection measures. • Effects of accident management can be estimated using the cost per severe accident

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

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

  4. HIV surveillance in needlestick accidents with health workers - doi: 10.5020/18061230.2010.p325

    Janete Lane Amadei

    2012-01-01

    Full Text Available Objective: To characterize the occurrence of needlestick accidents with health professionals submitted to rapid HIV tests. Methods: A descriptive, epidemiological study, carried out by notification of the occurrence of needlestick accidents in the Epidemiology Sector of the State Health Secretariat, in 2008. The following variables were assessed: gender, age, exposed biological material, type of exposure, source patient, and injured patient, progression of the case, accident situation, and use of personal protective equipment (PPE, 180 days serology and occupational area. Results: There have been reports of 143 accidents, prevailing in nursing, female, 20 to 30 years, involving the blood and biological material by percutaneous puncture. We found no standardization in the use of PPE. The HIV test revealed no positive cases. Conclusion: This study helped to characterize the occurrence of accidents reported in health care professionals and evaluate the protocol of care given. It also revealed non-contamination by HIV.

  5. WASA-BOSS. ATHLET-CD model for severe accident analysis for a generic KONVOI reactor

    Tusheva, Polina; Schaefer, Frank; Kozmenkov, Yaroslav; Kliem, Soeren [Helmholtz-Zentrum Dresden-Rossendorf, Dresden (Germany). Reactor Safety Div.; Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany); Trometer, Ailine; Buck, Michael [Stuttgart Univ. (Germany). Dept. of Reactor Safety, Systems and Environment

    2015-07-15

    Within the scope of the ongoing joint research project WASA-BOSS (Weiterentwicklung und Anwendung von Severe Accident Codes - Bewertung und Optimierung von Stoerfallmassnahmen) an ATHLET-CD model for investigation of severe accident scenarios has been developed. The model represents a generic pressurized water reactor (PWR) of type KONVOI. It has been applied for analyzing selected hypothetical core degradation scenarios, considering application of countermeasures and accident management measures, during the early phase of an accident, as well as the late in-vessel phase, when the core degradation process has already begun. Possible accident management measures for loss of coolant (LOCA) and station blackout (SBO) scenarios are discussed. This paper focuses on the ATHLET-CD model development and results from selected simulations for a SBO scenario without and with application of countermeasures.

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

    Qiao Tong

    2016-03-01

    Full Text Available 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 province, Hunan province, Yunnan province and Heilongjiang province are the accident prone provinces. GM (1, 1 dynamic prediction model is used to model and forecast the future million tons mortality in China. The forecast results show that the coal mine's million tons mortality rate of China showed a decreasing trend. The forecast results are scientific and reliable, and it is of great significance to the safety management of coal mine.

  7. WASA-BOSS. ATHLET-CD model for severe accident analysis for a generic KONVOI reactor

    Within the scope of the ongoing joint research project WASA-BOSS (Weiterentwicklung und Anwendung von Severe Accident Codes - Bewertung und Optimierung von Stoerfallmassnahmen) an ATHLET-CD model for investigation of severe accident scenarios has been developed. The model represents a generic pressurized water reactor (PWR) of type KONVOI. It has been applied for analyzing selected hypothetical core degradation scenarios, considering application of countermeasures and accident management measures, during the early phase of an accident, as well as the late in-vessel phase, when the core degradation process has already begun. Possible accident management measures for loss of coolant (LOCA) and station blackout (SBO) scenarios are discussed. This paper focuses on the ATHLET-CD model development and results from selected simulations for a SBO scenario without and with application of countermeasures.

  8. Major chemical accidents in industrializing countries: the socio-political amplification of risk.

    de Souza Porto, M F; de Freitas, C M

    1996-02-01

    Accidents in the chemical industry, such as those that took place in Seveso (1976) and Bhopal (1984), may kill or injure thousands of people, cause serious health hazards and irreversible environmental damage. The aim of this paper is to examine the ever-increasing risk of similar accidents becoming a frequent ocurrence in the so-called industrializing countries. Using figures from some of the worst chemical accidents in the last decades, data on the Bhopal disaster, and Brazil's social and institutional characteristics, we put forward the hypothesis that present social, political and economic structures in industrializing countries make these countries much more vulnerable to such accidents and create the type of setting where--if and when these accidents occur--they will have even more catastrophic consequences. The authors argue that only the transformation of local structures, and stronger technical cooperation between international organizations, industrialized and industrializing countries could reduce this vulnerability. PMID:8868221

  9. Medical management of radiological accidents in non-specialized clinics: mistakes and lessons

    In 1996-2002 three radiological accidents were developed in Georgia. There were some people injured in those accidents. During medical management of the injured some mistakes and errors were revealed both in diagnostics and scheme of the treatment. The goal of this article is to summarize medical management of the mentioned radiological accidents, to estimate reasons of mistakes and errors, to present the lessons drawn in result of Georgia radiological accidents. There was no clinic with specialized profile and experience. Accordingly due to having no relevant experience late diagnosis can be considered as the main error. It had direct influence on the patients' health and results of treatment. Lessons to be drawn after analyzing Georgian radiological accidents: 1. informing medical staff about radiological injuries (pathogenesis, types, symptoms, clinical course, principles of treatment and etc.); 2. organization of training and meetings in non-specialized clinics or medical institutions for medical staff; 3. preparation of informational booklets and guidelines.(author)

  10. Study on severe accidents and countermeasures for WWER-1000 reactors using the integral code ASTEC

    The research field focussing on the investigations and the analyses of severe accidents is an important part of the nuclear safety. To maintain the safety barriers as long as possible and to retain the radioactivity within the airtight premises or the containment, to avoid or mitigate the consequences of such events and to assess the risk, thorough studies are needed. On the one side, it is the aim of the severe accident research to understand the complex phenomena during the in- and ex-vessel phase, involving reactor-physics, thermal-hydraulics, physicochemical and mechanical processes. On the other side the investigations strive for effective severe accident management measures. This paper is focused on the possibilities for accident management measures in case of severe accidents. The reactor pressure vessel is the last barrier to keep the molten materials inside the reactor, and thus to prevent higher loads to the containment. To assess the behaviour of a nuclear power plant during transient or accident conditions, computer codes are widely used, which have to be validated against experiments or benchmarked against other codes. The analyses performed with the integral code ASTEC cover two accident sequences which could lead to a severe accident: a small break loss of coolant accident and a station blackout. The results have shown that in case of unavailability of major active safety systems the reactor pressure vessel would ultimately fail. The discussed issues concern the main phenomena during the early and late in-vessel phase of the accident, the time to core heat-up, the hydrogen production, the mass of corium in the reactor pressure vessel lower plenum and the failure of the reactor pressure vessel. Additionally, possible operator's actions and countermeasures in the preventive or mitigative domain are addressed. The presented investigations contribute to the validation of the European integral severe accidents code ASTEC for WWER-1000 type of reactors

  11. Accident Risks In The Energy Sector: Comparative Evaluations

    Hirschberg, S.; Burgherr, P

    2005-03-01

    Severe accidents are considered one of the most controversial issues in current comparative studies of the environmental and health impact of energy systems. The present work focuses on severe accident scenarios relating to fossil energy chains (coal, oil and gas), nuclear power and hydro-power. The scope of the study is not limited to the power production (conversion) step of these energy chains, but, wherever applicable, also includes full energy chains. With the exception of the nuclear chain, the focus of the present work is on the evaluation of the historical experience of accidents. The basis for this evaluation is the comprehensive database ENSAD (Energy-Related Severe Accident Database), which has been established at PSI. For hypothetical nuclear accidents, a probabilistic technique has also been employed. The broader picture, derived from examination of full energy chains, leads, on a world-wide basis, to the conclusion that immediate fatality rates are much higher for the fossil chains than expected if only power plants are considered. Generally, immediate fatality rates are significantly higher for non-OECD countries than for OECD countries, and, in the case of hydro and nuclear, the difference is rather dramatic. In addition to aggregated values, frequency-consequence curves are also provided, since they not only reflect implicitly a ranking based on aggregated values, but also include such information as the observed, or predicted, chain-specific maximum extent of damages. Finally, damage and external costs of severe accidents for the different energy chains have been estimated, based on the unit cost values for the various consequence types. (author)

  12. Accident Risks In The Energy Sector: Comparative Evaluations

    Severe accidents are considered one of the most controversial issues in current comparative studies of the environmental and health impact of energy systems. The present work focuses on severe accident scenarios relating to fossil energy chains (coal, oil and gas), nuclear power and hydro-power. The scope of the study is not limited to the power production (conversion) step of these energy chains, but, wherever applicable, also includes full energy chains. With the exception of the nuclear chain, the focus of the present work is on the evaluation of the historical experience of accidents. The basis for this evaluation is the comprehensive database ENSAD (Energy-Related Severe Accident Database), which has been established at PSI. For hypothetical nuclear accidents, a probabilistic technique has also been employed. The broader picture, derived from examination of full energy chains, leads, on a world-wide basis, to the conclusion that immediate fatality rates are much higher for the fossil chains than expected if only power plants are considered. Generally, immediate fatality rates are significantly higher for non-OECD countries than for OECD countries, and, in the case of hydro and nuclear, the difference is rather dramatic. In addition to aggregated values, frequency-consequence curves are also provided, since they not only reflect implicitly a ranking based on aggregated values, but also include such information as the observed, or predicted, chain-specific maximum extent of damages. Finally, damage and external costs of severe accidents for the different energy chains have been estimated, based on the unit cost values for the various consequence types. (author)

  13. Investigation of VVER 1000 Fuel Behavior in Severe Accident Condition

    This paper presents the results obtained during a simulation of fuel behavior with the MELCOR computer code in case of severe accident for the VVER reactor core. The work is focused on investigating the influence of some important parameters, such as porosity, on fuel behavior starting from oxidation of the fuel cladding, fusion product release in the primary circuit after rupture of the fuel cladding, melting of the fuel and reactor core internals and its further relocation to the bottom of the reactor vessel. In the analyses are modeled options for blockage of melt and debris during its relocation. In the work is investigated the uncertainty margin of reactor vessel failure based on modeling of the reactor core and an investigation of its behavior. This is achieved by performing sensitivity analyses for VVER 1000 reactor core with gadolinium fuel type. The paper presents part of the work performed at the Institute for Nuclear Research and Nuclear Energy (INRNE) in the frame of severe accident research. The performed work continues the effort in the modeling of fuel behavior during severe accidents such as Station Blackout sequence for VVER 1000 reactors based on parametric study. The work is oriented towards the investigation of fuel behavior during severe accident conditions starting from the initial phase of fuel damaging through melting and relocation of fuel elements and reactor internals until the late in-vessel phase, when melt and debris are relocated almost entirely on the bottom head of the reactor vessel. The received results can be used in support of PSA2 as well as in support of analytical validation of Sever Accident Management Guidance for VVER 1000 reactors. The main objectives of this work area better understanding of fuel behavior during severe accident conditions as well as plant response in such situations. (author)

  14. Reactor accident diagnostic expert system: DISKET

    A reactor accident diagnostic system DISKET has been developed to identify the cause and the type of an abnormal transient of a nuclear power plant. The system is based on the knowledge engineering and consists of an inference engine IERIAS and a knowledge base. The main features of DISKET are the following: Time-varying characteristics of transient can be treated and knowledge base can be divided into several knowledge units to handle a lot of rules effectively. This report has been provided for the convenience of DISKET's users and consists of three parts. The first part is the description of the whole system, the details of the knowledge base of DISKET are described in the second part, and how to use the DISKET system is explained in the third part. (author)

  15. Frequency of road accidents in prishtina in the period 2007-2010

    Basri Lenjani; Salih Krasniqi; Njiazi Gashi; Ilaz Bunjaku; Thaxhedin Zaimi

    2012-01-01

    Objective: To assess the predictors of fatal road traffic accidents following the war during the year 1999. Methods: The period January 2007-December 2010 has been considered for this research. The used criterion for this research was the distribution of vehicle accidents on a yearly basis, injuries based on systems, vehicle drivers based on their sex, age, causes, accident location, road type, accident type and presence of driving permit. Results: The injured in traffic accidents who have sought emergency medical assistance in the Emergency Center from January 2008 until December 2010. In the period January to December 2007 was 44 111, from which 2 235 or 5.06% were the injured in the road traffic accidents. In the period January to December 2008 the total number of sick, injured and poisoned persons who have sought emergency medical assistance in the Emergency Center was 43 610, with a total number of 2 148 or 5.00% injured in the road traffic accidents. In the period January to December 2009 the total number of sick, injured and poisoned persons who have sought emergency medical assistance in the Emergency Center was 44 228, and the total number of injured in the road traffic accidents was 2 774, or 6.27%. In the period January to December 2010 the total number of sick, injured and poisoned who have sought emergency medical assistance in the Emergency Center was 41 614, and injured from road traffic accidents were 2 384, or 5.72%. Conclusions: Young age, high speed, and alcohol are predictors of fatal road traffic accidents in Pristine district.

  16. Emergency department radiation accident protocol.

    Leonard, R B; Ricks, R C

    1980-09-01

    Every emergency department faces the potential problem of handling one or more victims of a radiation accident. While emergency departments near nuclear power plants or isotope production laboratories probably have a detailed protocol for such emergencies, a similar protocol is needed for the emergency department that may have to handle an isolated event, such as a vehicular accident that spills radioactive material and contaminates passengers or bystanders. This communication attempts to answer that need, presenting a step-by-step protocol for decontamination of a radiation victim, the rationale on which each step is based, a list of needed supplies, and a short summary of decorporation procedures that should be started in the emergency department. PMID:7425419

  17. 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....

  18. Psychological factors of radiation accidents

    With reference to world, internal and personal experience, an attempt is made to reveal psychological mechanisms determining the attitude of a person to ionizing radiation using for this purpose the conceptions of mental stress and psychological adaptation. On the example of Chernobyl Nuclear Power Plant, in the light of the above conceptions, the paper describes psychic reactions of the personnel of the nuclear power plant and other groups of people to the heavy radiation accident. For improvement of the activity for liquidation of the accident after-effects it is suggested to use the system of psychophysiological support of the rescue units, including psychophysiological training and support, as well as functional rehabilitation of specialists. 11 refs

  19. Accident analysis of recreation vehicle. Human factors from statistic analysis and case study; RV sha no jiko bunseki. Tokei bunseki to jikorei bunseki ni miru untensha yoin

    Takubo, N. [Institute for Traffic Accident Research and Data Analysis, Tokyo (Japan); Mori, K. [Honda R and D Co. Ltd., Tokyo (Japan)

    1998-05-01

    Concern is heightening recently on traffic accidents associated with leisure activities. Therefore, with an objective to obtain referential information for preventing accidents caused by recreational vehicles, macroscopic (statistical) and microscopic (case study) investigations were carried out on accidents. As a result of analyzing the statistics, a trend was discovered that recreational vehicles cause accidents at higher rate than by other types of vehicles in the following types of accidents: accidents with pedestrians, children and elderly people, accidents caused by young drivers, and accidents during personal activities. Furthermore, four cases were analyzed on accident trends. Accident trends must be discussed from the following two viewpoints: frequency in occurrence of circumstances (chances) that link with accidents, and how high the accident rate (hazard risk) is under such circumstances. The former point has high correlation with how recreational vehicles are used, and drivers` attributes, and the latter point with structures and motion characteristics of recreational vehicles (for example, leisure use, cars driven by young drivers, and high vehicle height). 1 ref., 12 figs.

  20. Accident analysis of heavy water cooled thorium breeder reactor

    Yulianti, Yanti [Department of Physics, University of Lampung Jl. Sumantri Brojonegoro No.1 Bandar Lampung, Indonesia Email: y-yanti@unila.ac.id (Indonesia); Su’ud, Zaki [Department of Physics, Bandung Institute of Technology Jl. Ganesha 10 Bandung, Indonesia Email: szaki@fi.itb.ac.id (Indonesia); Takaki, Naoyuki [Department of Nuclear Safety Engineering Cooperative Major in Nuclear Energy (Graduate School) 1-28-1 Tamazutsumi,Setagayaku, Tokyo158-8557, Japan Email: ntakaki@tcu.ac.jp (Japan)

    2015-04-16

    Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by Tokai University and Tokyo Institute of Technology. That is oxide fueled, PWR type reactor with heavy water as primary coolant. An example of the optimized core has relatively small moderator to fuel volume ratio (MFR) of 0.6 and the characteristics of the core are burn-up of 67 GWd/t, breeding ratio of 1.08, burn-up reactivity loss during cycles of < 0.2% dk/k, and negative coolant reactivity coefficient. One of the nuclear reactor accidents types examined here is Unprotected Transient over Power (UTOP) due to withdrawing of the control rod that result in the positive reactivity insertion so that the reactor power will increase rapidly. Another accident type is Unprotected Loss of Flow (ULOF) that caused by failure of coolant pumps. To analyze the reactor accidents, neutron distribution calculation in the nuclear reactor is the most important factor. The best expression for the neutron distribution is the Boltzmann transport equation. However, solving this equation is very difficult so that the space-time diffusion equation is commonly used. Usually, space-time diffusion equation is solved by employing a point kinetics approach. However, this approach is less accurate for a spatially heterogeneous nuclear reactor and the nuclear reactor with quite large reactivity input. Direct method is therefore used to solve space-time diffusion equation which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference method is solved by using iterative methods. The indication of UTOP accident is decreasing macroscopic absorption cross-section that results large external reactivity, and ULOF accident is indicated by decreasing coolant flow. The

  1. Accident analysis of heavy water cooled thorium breeder reactor

    Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by Tokai University and Tokyo Institute of Technology. That is oxide fueled, PWR type reactor with heavy water as primary coolant. An example of the optimized core has relatively small moderator to fuel volume ratio (MFR) of 0.6 and the characteristics of the core are burn-up of 67 GWd/t, breeding ratio of 1.08, burn-up reactivity loss during cycles of < 0.2% dk/k, and negative coolant reactivity coefficient. One of the nuclear reactor accidents types examined here is Unprotected Transient over Power (UTOP) due to withdrawing of the control rod that result in the positive reactivity insertion so that the reactor power will increase rapidly. Another accident type is Unprotected Loss of Flow (ULOF) that caused by failure of coolant pumps. To analyze the reactor accidents, neutron distribution calculation in the nuclear reactor is the most important factor. The best expression for the neutron distribution is the Boltzmann transport equation. However, solving this equation is very difficult so that the space-time diffusion equation is commonly used. Usually, space-time diffusion equation is solved by employing a point kinetics approach. However, this approach is less accurate for a spatially heterogeneous nuclear reactor and the nuclear reactor with quite large reactivity input. Direct method is therefore used to solve space-time diffusion equation which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference method is solved by using iterative methods. The indication of UTOP accident is decreasing macroscopic absorption cross-section that results large external reactivity, and ULOF accident is indicated by decreasing coolant flow. The

  2. Accident analysis of heavy water cooled thorium breeder reactor

    Yulianti, Yanti; Su'ud, Zaki; Takaki, Naoyuki

    2015-04-01

    Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by Tokai University and Tokyo Institute of Technology. That is oxide fueled, PWR type reactor with heavy water as primary coolant. An example of the optimized core has relatively small moderator to fuel volume ratio (MFR) of 0.6 and the characteristics of the core are burn-up of 67 GWd/t, breeding ratio of 1.08, burn-up reactivity loss during cycles of coolant reactivity coefficient. One of the nuclear reactor accidents types examined here is Unprotected Transient over Power (UTOP) due to withdrawing of the control rod that result in the positive reactivity insertion so that the reactor power will increase rapidly. Another accident type is Unprotected Loss of Flow (ULOF) that caused by failure of coolant pumps. To analyze the reactor accidents, neutron distribution calculation in the nuclear reactor is the most important factor. The best expression for the neutron distribution is the Boltzmann transport equation. However, solving this equation is very difficult so that the space-time diffusion equation is commonly used. Usually, space-time diffusion equation is solved by employing a point kinetics approach. However, this approach is less accurate for a spatially heterogeneous nuclear reactor and the nuclear reactor with quite large reactivity input. Direct method is therefore used to solve space-time diffusion equation which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference method is solved by using iterative methods. The indication of UTOP accident is decreasing macroscopic absorption cross-section that results large external reactivity, and ULOF accident is indicated by decreasing coolant flow. The power reactor has a peak value

  3. 基于事故发展与控制的隐患分级方法%Risk Classification Method for Accident Potential Based on Development and Control Measures of Accident

    赵东风; 申玉琪; 赵志强; 张佑明; 孟亦飞

    2012-01-01

    For the purpose of making the management of accident potential more scientific, the relationship between accident potential and accident was discussed and studied. The fundamental property of accident potential was brought forward that it can make the accident happen or develop. The mechanism whereby accident potential functions in the accident was revealed clearly, by predicting the impelling and inhibiting factors in the accident process. The accident potential was classified into two types (the first type of accident potential and the second type of accident potential) according to the different time they work. In the risk assessment, the problem of specific accident potential grading was resolved. By introducing the assessment indexes of accident potential exposure frequency, possibility of other factors, corrective actions, the initial value of the consequences of the accident, the correction factor of personnel protection, the correction factor of personnel exposure, the correction factor of emergency measures, the correction factor of property loss, an assessment index system was established. By calculating the risk of accident potential-causing accident, the real risk of accident potential was assessed.%为使隐患管理工作更加科学,对隐患与事故的关系进行研讨,提出隐患的根本属性是能够促使事故发生或发展.通过预估促使和控制(阻碍)事故发展的因素,来揭示隐患在事故过程中的作用机制.根据发生作用的时间将隐患分为第1类隐患和第2类隐患.在风险评估过程中,解决了具体隐患风险分级的问题,提出隐患暴露频率、其他条件的可能性、隐患纠正系数、事故后果初始分值、人员防护修正系数、人员暴露修正系数、应急处理与事故控制修正系数和财产损失修正系数等评价指标.通过隐患致因事故风险的计算,评估隐患的最终风险.

  4. Accident Simulation: Design and Results

    Idasiak, Vincent; David, Pierre

    2007-01-01

    International audience The French legislation regulates the functioning of factories that may be dangerous towards their environment. This legislation imposes the creation of an Internal Operation Plan (P.O.I.) on the plant managers. Those plans describe the proceedings that have to be implemented in case of an accident. Within a framework involving our laboratory and a gas company we have designed a software to create, maintain and execute P.O.I.s . In this paper, in addition to the softw...

  5. Transport accident emergency response plan

    To comply with the IAEA recommendations for the implementation of an Emergency Response Plan as described in Safety Series 87, Transnucleaire, a company deeply involved in the road and rail transports of the fuel cycle, masters means of Emergency Response in the event of a transport accident. This paper aims at analyzing the solutions adopted for the implementation of an Emergency Response Plan and the development of a technical support and adapted means for the recovery of heavy packagings. (authors)

  6. Standards for reactor accident cases

    The Committee on Standards for reactor accident cases in the Netherlands published its recommendations to the Minister of Health. Maximum permissible quantities of radiation and radionuclide intake are presented for adults and children as well as pregnant women. Exposure limit standards for the whole body as well as specific organs and other parts are given. Also considered is the contamination of cattle and cows' milk. The standards are compared with those of the ICRP and the English Medical Research Council

  7. Radiation accident in Viet Nam

    In November 1992 a Vietnamese research physicist was working with a microtron accelerator when he received a radiation overexposure that required the subsequent amputation of his right hand. A team from the International Atomic Energy Agency visited Hanoi in March 1993 to carry out an investigation. It was concluded that the accident occurred primarily due to a lack of safety systems although the lack of both written procedures and training in basic radiation safety were also major contributors. (author)

  8. Accident/Mishap Investigation System

    Keller, Richard; Wolfe, Shawn; Gawdiak, Yuri; Carvalho, Robert; Panontin, Tina; Williams, James; Sturken, Ian

    2007-01-01

    InvestigationOrganizer (IO) is a Web-based collaborative information system that integrates the generic functionality of a database, a document repository, a semantic hypermedia browser, and a rule-based inference system with specialized modeling and visualization functionality to support accident/mishap investigation teams. This accessible, online structure is designed to support investigators by allowing them to make explicit, shared, and meaningful links among evidence, causal models, findings, and recommendations.

  9. 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.)

  10. Thermal Hydraulic design parameters study for severe accidents using neural networks

    Roh, Chang Hyun; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Chang, Keun Sun [Sunmoon University, Asan (Korea, Republic of)

    1997-12-31

    To provide the information on severe accident progression is very important for advanced or new type of nuclear power plant (NPP) design. A parametric study, therefore, was performed to investigate the effect of thermal hydraulic design parameters on severe accident progression of pressurized water reactors (PWRs). Nine parameters, which are considered important in NPP design or severe accident progression, were selected among the various thermal hydraulic design parameters. The backpropagation neural network (BPN) was used to determine parameters, which might more strongly affect the severe accident progression, among nine parameters. For training, different input patterns were generated by the latin hypercube sampling (LHS) technique and then different target patterns that contain core uncovery time and vessel failure time were obtained for Young Gwang Nuclear (YGN) Units 3 and 4 using modular accident analysis program (MAAP) 3.0B code. Three different severe accident scenarios, such as two loss of coolant accidents (LOCAs) and station blackout (SBO), were considered in this analysis. Results indicated that design parameters related to refueling water storage tank (RWST), accumulator and steam generator (S/G) have more dominant effects on the progression of severe accidents investigated, compared to the other six parameters. 9 refs., 5 tabs. (Author)

  11. Accident risk and safety measures in the transport sector in Norway; Ulykkesrisiko og sikkerhetstiltak i transportsektoren

    NONE

    1998-12-01

    The scope of the work described in this report was (1) to evaluate methods for risk mapping considering all of the different means of transport, (2) to evaluate the extent to which measures should be taken against various types of accidents, (3) to evaluate cost-benefit assessments of accident-reducing measures irrespective of the different means of transport, (4) to evaluate the preferences of measures/cost effectiveness of different measures within different sectors, and (4) to evaluate the possibility of improving the efficiency of possible measures. It also considers the risk situation for ferry service. In addition to the purely human aspect, traffic accidents constitute an expensive social problem. Yet it would be too costly to meet a potential requirement that traffic accidents should disappear. The resources used by society to combat accidents have to be seen in the light of (1) the profit that can be achieved compared to alternative use of the resources, and (2) the possible negative consequences of different safety measures on, for instance, travel time and the extent of the transport. It is pointed out that when accident risk is compared from one transport means to another, different relative positions are found depending on how risk is quantified. Thus, for instance, on average, per year 5 times as many people die in accidents involving private cars as in motor cycle accidents, while for the number of deaths per billion person kilometers the ratio is almost the opposite,1:6.5. 34 refs., 12 figs., 13 tabs.

  12. Prevention of the causes and consequences of a criticality accident - measures adopted in France

    The question of safety in regard to criticality accident risks has two aspects: prevention of the cause and limitation of the consequences. These two aspects are closely connected. The effort devoted to prevention of the causes depends on the seriousness of the possible human psychologic and economic consequences of the accident. The criticality accidents which have occurred in the nuclear industry, though few in number, do reveal the imperfect nature of the techniques adopted to prevent the causes, and also constitute the only available realistic basis for evaluating the consequences and developing measures to limit them. The authors give a analysis of the known causes and consequences of past criticality accidents and on this basis make a number of comments concerning: the validity of traditional safety criteria, the probability of accidents for different types of operations, characteristic accidents which can serve as models, and the extent of possible radiological consequences. The measures adopted in France to limit the consequences of a possible criticality accident under the headings: location, design and lay-out of the installations, accident detection, and dosimetry for the exposed personnel, are briefly described after a short account of the criteria used in deciding on them. (author)

  13. Mutual emergency assistance for radiation accidents

    In 1963 the International Atomic Energy Agency (IAEA) issued a document, WP.35, dated 23 November 1963, based on information provided by a number of its Member States on the type of radiological assistance that they might be able to make available in the event of a radiation emergency in another country at the request of that country. The document was subsequently revised in 1968 and 1971 with the participation of the World Health Organization (WHO), the Food and Agriculture Organization of the United Nations (FAO) and the International Labour Organisation (ILO). In 1979, an expanded questionnaire to ascertain what could be required by the State in the event of a major radiation accident, was sent jointly by these organizations with the participation of the Office of the United Nations Disaster Relief Co-ordinator (UNDRO), to all their Member States. The text of the expanded questionnaire is reproduced. The present document lists all the information, received up to mid 1980, that contains offers of assistance made by a State. It also lists information on the assistance that might be required by the State. In general, the replies have been reproduced in the form in which they were received, although a few changes in presentation have been introduced in the interest of brevity and clarity. Some countries have pointed out that their replies are necessarily of a general character and that the full extent of the assistance they would be capable of providing could be determined only after a specific request had been received. The information given in this document should therefore be regarded only as a guide to the type of radiological assistance that might be available and/or needed. Other available international assistance includes that provided by the Agency through the IAEA Radiation (Emergency) Assistance Procedures, by WHO through its system of Collaborating Centres on human radiation pathology, and by various States via regional or inter-countries' agreements on

  14. Thyroid blocking after nuclear accidents

    Following the Chernobyl accident a marked increase in thyroid cancer incidence among the children in Belarus, the Ukraine and Russia has been detected, strongly suggesting a causal relationship to the large amounts of radioactive iodine isotopes in the resulting fallout. Taking into account the Chernobyl experience the German Committee on Radiation Protection decided to reduce the intervention levels on the basis of the 1989 WHO recommendations and adopted a new concept concerning thyroid blocking in response to nuclear power plant accidents. Experimental animal studies and theoretical considerations show that thyroid blocking with potassium iodide (KI) in a dose of about 1.4 mg per kg body weight is most effective in reducing irradiation to the thyroid from the intake of radioiodine nuclides, provided KI is given within 2 hours after exposure. According to the new concept, persons over 45 years of age should not take iodine tablets because the drug could cause a greater health risk due to prevalent functional thyroid autonomy in this age group than the radioactive iodine averted by KI. On the basis of accident analysis and the new philosophy suitable distribution strategies and logistics are proposed and discussed. (orig.)

  15. Medical consequences of Chernobyl accident

    Galstyan I.A.

    2015-12-01

    Full Text Available Aim: to study the long-term effects of acute radiation syndrome (ARS, developed at the victims of the Chernobyl accident. Material and Methods. 237 people were exposed during the accident, 134 of them were diagnosed with ARS. Dynamic observation implies a thorough annual examination in a hospital. Results. In the first 1.5-2 years after the ARS mean group indices of peripheral blood have returned to normal. However, many patients had transient expressed moderate cytopenias. Granulocytopenia, thrombocytopenia, lymphopenia and erythropenia were the most frequently observed things during the first 5 years after the accident. After 5 years their occurences lowered. In 11 patients the radiation cataract was detected. A threshold dose for its development is a dose of 3.2 Gy Long-term effects of local radiation lesions (LRL range from mild skin figure smoothing to a distinct fibrous scarring, contractures, persistently recurrent late radiation ulcers. During all years of observation we found 8 solid tumors, including 2 thyroid cancers. 5 hematologic diseases were found. During 29 years 26 ARS survivors died of various causes. Conclusion. The health of ones with long-term ARS effects is determined by the evolution of the LRL effects on skin, radiation cataracts, hema-tological diseases and the accession of of various somatic diseases, not caused by radiation.

  16. Leukaemia incidents after Chernobyl accident

    Romania and especially its Eastern territory were among the most heavily affected area after Chernobyl accident. The objective of our study was to investigate whether or not the nuclear accident determined an increased number of leukaemia cases. The specific rates of leukaemia incidents by age group were calculated in 588167 children aged 0-6 years in April 1986 and 99917 children which have been exposed 'in utero'. The rates of 1989-1994 period were compared with the rates of 1980-1985 period. The incidence rates were lower in the exposed group than that in controls for children under 1 year (20.52/105 inh vs 23.11/105 inh), 1-3 years (13.26/105 inh vs 16.11/105 inh) and 4-6 years (9.58/105 inh vs 10.58/105 inh). The cohort of 'in utero' exposed children presented a leukaemia incidences insignificantly higher than that before the accident (23.10/105 inh vs 15.93/105 inh)

  17. Accident analysis and DOE criteria

    In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied

  18. Severe accidents at nuclear power plants. Their risk assessment and accident management

    This document is to explain the severe accident issues. Severe Accidents are defined as accidents which are far beyond the design basis and result in severe damage of the core. Accidents at Three Mild Island in USA and at Chernobyl in former Soviet Union are examples of severe accidents. The causes and progressions of the accidents as well as the actions taken are described. Probabilistic Safety Assessment (PSA) is a method to estimate the risk of severe accidents at nuclear reactors. The methodology for PSA is briefly described and current status on its application to safety related issues is introduced. The acceptability of the risks which inherently accompany every technology is then discussed. Finally, provision of accident management in Japan is introduced, including the description of accident management measures proposed for BWRs and PWRs. (author)

  19. Traffic accidents with motorcycles and their relationship to mortality.

    de Oliveira, Nelson Luiz Batista; de Sousa, Regina Marcia Cardoso

    2011-01-01

    This study characterizes traffic accidents involving motorcycles according to local conditions, data concerning the type of accident, date and time, and identifies among these variables those associated with the death of victims. This retrospective study uses data from traffic collision reports from 2004 and death records from the institute of forensic medicine. A total of 99.4% of the events occurred in urban areas, where illumination (87.4%), weather conditions (80.6%); and traffic signs (70.6%) were satisfactory. Collisions between motorcycles and cars or pickup trucks prevailed (55.5%), followed by motorcycle falls (18.0%). In relation to the type of collision, the highest percentage was observed in broadside collision category (35.2%). There were differences between the groups of fatalities and survivors in relation to the area and illumination in the collision's site, in addition to the types of collision and impact. The conclusion is that local conditions and types of collision and impact stand out among the multiple variables defining the severity of accidents involving motorcycles. PMID:21584389

  20. The risk of accident in nuclear power plants - Quotes and questions. National debate on energy transition. Taking the risk of nuclear accident into account. Note to the 'scenarios' subgroup of the group of experts

    After an overview of the production of electricity from nuclear energy and of its risks, the author discusses the issue of nuclear safety by distinguishing the different points of view, by describing the different levels between a severe and a major accident, and by recalling the statements made by the ASN and the IRSN on this issue. He describes the various reasons and consequences of accidents: types of accidents which could result in a core fusion, the containment failure as the major accident. He discusses the questions and comments about major issues like: strength of reactor vessels, hydrogen explosion, water vapour explosion, corium crossing the concrete sill plate, corium recovery, MOX as an aggravating situation for safety. In the last part, the author discusses the global assessment of a risk of a nuclear accident: probabilities and occurrences, significant accidents on PWRs, premonitory analysis, demonstration of nuclear safety

  1. Safety against releases in severe accidents. Final report

    The work scope of the RAK-2 project has involved research on quantification of the effects of selected severe accident phenomena for Nordic nuclear power plants, development and testing of a computerised accident management support system and data collection and description of various mobile reactors and of different reactor types existing in the UK. The investigations of severe accident phenomena focused mainly on in-vessel melt progression, covering a numerical assessment of coolability of a degraded BWR core, the possibility and consequences of a BWR reactor to become critical during reflooding and the core melt behavior in the reactor vessel lower plenum. Simulant experiments were carried out to investigate lower head hole ablation induced by debris discharge. In addition to the in-vessel phenomena, a limited study on containment response to high pressure melt ejection in a BWR and a comparative study on fission product source term behaviour in a Swedish PWR were performed. An existing computerised accident management support system (CAMS) was further developed in the area of tracking and predictive simulation, signal validation, state identification and user interface. The first version of a probabilistic safety analysis module was developed and implemented in the system. CAMS was tested in practice with Barsebaeck data in a safety exercise with the Swedish nuclear authority. The descriptions of the key features of British reactor types, AGR, Magnox, FBR and PWR were published as data reports. Separate reports were issued also on accidents in nuclear ships and on description of key features of satellite reactors. The collected data were implemented in a common Nordic database. (au)

  2. Safety against releases in severe accidents. Final report

    Lindholm, I.; Berg, Oe.; Nonboel, E. [eds.

    1997-12-01

    The work scope of the RAK-2 project has involved research on quantification of the effects of selected severe accident phenomena for Nordic nuclear power plants, development and testing of a computerised accident management support system and data collection and description of various mobile reactors and of different reactor types existing in the UK. The investigations of severe accident phenomena focused mainly on in-vessel melt progression, covering a numerical assessment of coolability of a degraded BWR core, the possibility and consequences of a BWR reactor to become critical during reflooding and the core melt behavior in the reactor vessel lower plenum. Simulant experiments were carried out to investigate lower head hole ablation induced by debris discharge. In addition to the in-vessel phenomena, a limited study on containment response to high pressure melt ejection in a BWR and a comparative study on fission product source term behaviour in a Swedish PWR were performed. An existing computerised accident management support system (CAMS) was further developed in the area of tracking and predictive simulation, signal validation, state identification and user interface. The first version of a probabilistic safety analysis module was developed and implemented in the system. CAMS was tested in practice with Barsebaeck data in a safety exercise with the Swedish nuclear authority. The descriptions of the key features of British reactor types, AGR, Magnox, FBR and PWR were published as data reports. Separate reports were issued also on accidents in nuclear ships and on description of key features of satellite reactors. The collected data were implemented in a common Nordic database. (au) 39 refs.

  3. Rates of thoracic trauma and mortality due to accidents in Brazil

    To report on the causes of trauma, indexes of trauma, and mortality related to thoracic trauma in one region of Brazil. This prospective study was performed at the Regional Trauma Center in Syo Josi do Rio Preto over a 1-year period, from 1 st July 2004 to 30 th June 2005. We included all patients attending the center's emergency room with thoracic trauma and an anatomic injury scale (AIS) > - 2. We collected data using a protocol completed on arrival in hospital utilizing the AIS. We studied the types of accidents as well as the mortality and the AIS scores. Prevalence rates were calculated and the paired t-test and logistic regression were employed for the statistical analysis.There were a total of 373 casualties with AIS > - 2 and there were 45 (12%) deaths. The causes of thoracic trauma among the 373 casualties were as follows: 91 (24.4%) car crashes, 75 (20.1%) falls, 46 (12.3%) motorbike accidents, 40 (10.7%) stabbings, 22 (5.9%) accidents involving pedestrians, 21 (5.6%) bicycle accidents, 17 (4.6%) shootings, and 54 (14.5%) other types of accident. The severity of the injuries was classified according to the AIS: 224 (60%) were grade 2, 101 (27%) were grade 3, 27 (7.2%) were grade 4, 18 (4.9%) were grade 5, and 3 were (0.8%) grade 6. With respect to thoracic trauma, pedestrians involved in accidents and victims of shootings had mortality rates that were significantly higher than that of those involved in other types of accidents. Road accidents are the main cause of thoracic injury, with accidents involving pedestrians and shootings being associated with a greater death rate. (author)

  4. Severe Accident Recriticality Analyses (SARA)

    Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B4C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate

  5. Severe Accident Recriticality Analyses (SARA)

    Frid, W. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Hoejerup, F. [Risoe National Lab. (Denmark); Lindholm, I.; Miettinen, J.; Puska, E.K. [VTT Energy, Helsinki (Finland); Nilsson, Lars [Studsvik Eco and Safety AB, Nykoeping (Sweden); Sjoevall, H. [Teoliisuuden Voima Oy (Finland)

    1999-11-01

    Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B{sub 4}C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding

  6. Elderly patients attended in emergency health services in Brazil: a study for victims of falls and traffic accidents

    Mariana Gonçalves de Freitas; Palmira de Fátima Bonolo; Edgar Nunes de Moraes; Carla Jorge Machado

    2015-01-01

    The article aims to describe the profile of elderly victims of falls and traffic accidents from the data of the Surveillance Survey of Violence and Accidents (VIVA). The VIVA Survey was conducted in the emergency health-services of the Unified Health System in the capitals of Brazil in 2011. The sample of elderly by type of accident was subjected to the two-step cluster procedure. Of the 2463 elderly persons in question, 79.8% suffered falls and 20.2% were the victims of traffic accidents. Th...

  7. Strategy generation in accident management support

    An increased interest for research in the field of Accident Management can be noted. Several international programmes have been started in order to be able to understand the basic physical and chemical phenomena in accident conditions. A feasibility study has shown that it would be possible to design and develop a computerized support system for plant staff in accident situations. To achieve this goal the Halden Project has initiated a research programme on Computerized Accident Management Support (CAMS project). The aim is to utilize the capabilities of computerized tools to support the plant staff during the various accident stages. The system will include identification of the accident state, assessment of the future development of the accident and planning of accident mitigation strategies. A prototype is developed to support operators and the Technical Support Centre in decision making during serious accident in nuclear power plants. A rule based system has been built to take care of the strategy generation. This system assists plant personnel in planning control proposals and mitigation strategies from normal operation to severe accident conditions. The ideal of a safety objective tree and knowledge from the emergency procedures have been used. Future prediction requires good state identification of the plant status and some knowledge about the history of some critical variables. The information needs to be validated as well. Accurate calculations in simulators and a large database including all important information form the plant will help the strategy planning. (author). 12 refs, 2 figs

  8. The severe accident research program at KIT

    The understanding of the plant behaviour under beyond design basis accidents as well as the interaction of the operators with the plant is the most important prerequisite to develop proper strategies to both control the accident progression and to minimize the radiological risk that may derive from operating nuclear power plants. In view of the Fukushima accident, a review of many issues important to safety e.g. severe accident analysis methodologies and assumptions, emergency operational procedures, severe accident management procedures (SAM), decision lines of the emergency team, etc. is needed to draw conclusions in order to avoid a repetition of Fukushima-like accidents.In addition, situations like the ‘black control room’ need to be reconsidered and a re-evaluation of the necessary instrumentation for hypothetical severe accident situations is urgently needed. If the real plant state during core meltdown accidents is unknown, no effective measures can be initiated by the emergency team in order to assure the integrity of the safety barriers and hence the release of radioactive material to the environment. The work performed in this area is integrated in the European Networks such as SARNET (Severe Accident Research Network) for the severe accidents, and for emergency management in the NERIS-TP. In future all the activities will be included in the NUGENIA platform. A brief overview of the KIT activities together with the experimental test facilities is given

  9. Temporal Statistic of Traffic Accidents in Turkey

    Erdogan, S.; Yalcin, M.; Yilmaz, M.; Korkmaz Takim, A.

    2015-10-01

    Traffic accidents form clusters in terms of geographic space and over time which themselves exhibit distinct spatial and temporal patterns. There is an imperative need to understand how, where and when traffic accidents occur in order to develop appropriate accident reduction strategies. An improved understanding of the location, time and reasons for traffic accidents makes a significant contribution to preventing them. Traffic accident occurrences have been extensively studied from different spatial and temporal points of view using a variety of methodological approaches. In literature, less research has been dedicated to the temporal patterns of traffic accidents. In this paper, the numbers of traffic accidents are normalized according to the traffic volume and the distribution and fluctuation of these accidents is examined in terms of Islamic time intervals. The daily activities and worship of Muslims are arranged according to these time intervals that are spaced fairly throughout the day according to the position of the sun. The Islamic time intervals are never been used before to identify the critical hour for traffic accidents in the world. The results show that the sunrise is the critical time that acts as a threshold in the rate of traffic accidents throughout Turkey in Islamic time intervals.

  10. Analysis of Surface Water Pollution Accidents in China: Characteristics and Lessons for Risk Management

    Yao, Hong; Zhang, Tongzhu; Liu, Bo; Lu, Feng; Fang, Shurong; You, Zhen

    2016-04-01

    Understanding historical accidents is important for accident prevention and risk mitigation; however, there are no public databases of pollution accidents in China, and no detailed information regarding such incidents is readily available. Thus, 653 representative cases of surface water pollution accidents in China were identified and described as a function of time, location, materials involved, origin, and causes. The severity and other features of the accidents, frequency and quantities of chemicals involved, frequency and number of people poisoned, frequency and number of people affected, frequency and time for which pollution lasted, and frequency and length of pollution zone were effectively used to value and estimate the accumulated probabilities. The probabilities of occurrences of various types based on origin and causes were also summarized based on these observations. The following conclusions can be drawn from these analyses: (1) There was a high proportion of accidents involving multi-district boundary regions and drinking water crises, indicating that more attention should be paid to environmental risk prevention and the mitigation of such incidents. (2) A high proportion of accidents originated from small-sized chemical plants, indicating that these types of enterprises should be considered during policy making. (3) The most common cause (49.8 % of the total) was intentional acts (illegal discharge); accordingly, efforts to increase environmental consciousness in China should be enhanced.

  11. Response of HEPA filters to simulated-accident conditions

    High-efficiency particulate air (HEPA) filters have been subjected to simulated accident conditions to determine their response to abnormal operating events. Both domestic and European standard and high-capacity filters have been evaluated to determine their response to simulated fire, explosion, and tornado conditions. The HEPA filter structural limitations for tornado and explosive loadings are discussed. In addition, filtration efficiencies during these accident conditions are reported for the first time. Our data indicate efficiencies between 80% and 90% for shock loadings below the structural limit level. We describe two types of testing for ineffective filtration - clean filters exposed to pulse-entrained aerosol and dirty filters exposed to tornado and shock pulses. Efficiency and material loss data are described. Also, the resonse of standard HEPA filters to simulated fire conditions is presented. We describe a unique method of measuring accumulated combustion products on the filter. Additionally, data relating to pressure drop vs accumulated mass during plugging are reported for simulated combustion aerosols. The effects of concentration and moisture levels on filter plugging were evaluated. We are obtaining all of the above data so that mathematical models can be developed for fire, explosion, and tornado accident analysis computer codes. These computer codes can be used to assess the response of nuclear air cleaning systems to accident conditions

  12. Possibilities for Improved Treatment of Persons Exposed in Radiation Accidents

    The number of persons exposed to acute radiation accidents continues to be small and the clinical experience in handling them is thus obviously limited. The great increase in use of radioactive materials and the growing number of power reactors constitute greatly augmented potential sites for accidents, but fortunately the number of accidents is not increasing. There appears to be some shift in the type of accidents, with a relative increase in those in which excessive dose to a small part of the body is the predominant feature. There has been little progress in treating local radiation injury but methods for handling the hematopoietic syndrome are definitely improved. With platelet transfusions we have a powerful aid in managing hemorrhage; the more difficult problem in persons with severe marrow depression is infection. The development of sterile environment facilities and the availability of better antibiotic therapy are important advances. Where these measures are not adequate, more experimental procedures give some promise: the injection of concentrated leukemic or normal leukocytes, the use of cross circulation, or the injection of allogeneic bone marrow. Classification of the injury and estimation of its severity are more effectively done now than a few years ago, and contribute to better treatment. (author)

  13. PSA modeling of long-term accident sequences

    In the traditional Level 1 PSA, the long term of the accident sequences is usually taken into account in a simplified manner. For example, some of the mitigations which are needed at long term are taken into account in the PSA, but the analysis and the associated failures probabilities quantification are estimated based on generic assessments. In the context of the extension of PSA scope to include the external hazards, in France, both operator (EDF) and IRSN work for the improvement of methods to better take into account in the PSA the long term of accident sequences induced by initiators which affect the whole site containing several nuclear installations (reactors, fuel pools, ...). This is an essential prerequisite for the development of external hazards PSA. It has to be noted that in the French PSA, even before Fukushima, this type of accident sequences was already taken into account, many insight being used, as complementary information, to enhance the safety level of the plants. The recent French and international operating experience is an opportunity for tuning the actual PSA methods for long term accident sequences modeling. The paper presents the main results of the ongoing efforts in this area. (author)

  14. The Fukushima Accident and the Public Opinion in Slovenia

    Nuclear Training Center (ICJT) at the Jozef Stefan Institute is actively involved also in public information of nuclear issues in Slovenia. After the accident in Fukushima ICJT was one of the main sources of technical information and explanation for the journalists. Organized groups, mainly schoolchildren, traditionally come to ICJT, where they listen to a live lecture and visit the permanent exhibition on nuclear energy. Each year in spring, around 1000 of visitors are polled regarding their knowledge and attitude towards nuclear energy. As the visitors of ICJT are not a representative sample of general population, the results of the poll can not be taken absolutely, but they are valuable when compared to previous years' results - to monitor trends in the (younger) public. In the year 2011, the poll was conducted one month after the accident in Fukushima. ICJT is also analysing media reports by following articles in all types of media: TV, radio, press and web. The first two months after the Fukushima accident the frequency of reports increased drastically and then slowly faded away to reach pre-accident level in about 6 months. Naturally there were a lot of concerned reports, some of them also very negative, but given the circumstances and compared with some other countries, e.g. Austria or Germany, the reporting was relatively objective. The paper will analyze the trends in public opinion in Slovenia based on direct contacts with journalists, opinion polls and media analyses.(author).

  15. Iodine–paint interactions during nuclear reactor severe accidents

    Highlights: • Iodine interacts with containment paint in several ways. • Some mechanistic understanding is required. • Paint aging and degradation mechanisms. • Iodine adsorption and release mechanisms. • The Severe Accident Research Network (SARNET) facilitates collaboration between members. - Abstract: To assess the radiological consequences of a severe reactor accident, it is important to be able to predict the behaviour of iodine in containment. Some interactions between iodine and containment paint (e.g., adsorption) have been well known for a long time. However, in recent years, new phenomena have been identified that can affect the gas phase iodine concentration in the longer term (e.g., the release of molecular iodine and organic iodides from irradiated painted surfaces). Several international collaborations and organizations around the world are currently addressing different aspects of this topic, including laboratory experiments and theoretical studies (ab initio) designed to improve the mechanistic understanding of the phenomena. Knowledge of the underlying mechanisms will provide explanations for behavioural differences observed between paint types, and will support the extrapolation of laboratory results to the safety analyses of nuclear reactors. The purpose of this paper is to present a selection of recent work performed by Severe Accident Research Network (SARNET) members regarding iodine–paint interactions and paint aging in order to improve the common understanding and better define what has still to be done in this area. The Severe Accident Research Network (SARNET) provides a framework within which members can share and discuss results

  16. Relevant scenarios and uncertainty analysis of severe accidents in the U.S. EPR

    As part of U.S. EPR design certification activities, AREVA has prepared analyses to support the US NRC's regulatory expectation with regard to the resolution of several severe accident safety issues identified in SECY 93-087. To address the large uncertainties associated with severe accident progression, AREVA NP has developed and applied a best-estimate plus uncertainty methodology to the analysis of severe accidents. The uncertainty methodology considers a broad spectrum of phenomenological and process uncertainties. Unique among the uncertainty parameters considered is the sampling of event sequence (i.e., scenario type). (authors)

  17. The Chernobyl reactor accident and its consequences. Informative report prepared on behalf of the IAEA meeting, Vienna, August 25-29, 1986. Pt. 1

    GRS has revised the German translation of part 1 of the report on the Chernobyl reactor accident. The translation is technically clear and intelligible and contains the current technical terms. The report comprises a description of RBMK-1000, a chronological description of the accident, the analysis of the accident, the causes of the accident, measures preventing the further development of the accident as well as measures controlling the radioactive contamination of the environment and the population. The report discusses immediate emergency measures improving the safety of RBMK-type nuclear power plants and deals with recommendations for nuclear safety engineering. (DG)

  18. An epidemiologic survey of road traffic accidents in Iran: analysis of driver-related factors

    Moafian Ghasem

    2013-06-01

    Full Text Available 【Abstract】Objective: Road traffic accident (RTA and its related injuries contribute to a significant portion of the burden of diseases in Iran. This paper explores the as-sociation between driver-related factors and RTA in the country. Methods: This cross-sectional study was conducted in Iran and all data regarding RTAs from March 20, 2010 to June 10, 2010 were obtained from the Traffic Police Department. We included 538 588 RTA records, which were classified to control for the main confounders: accident type, final cause of accident, time of accident and driver-related factors. Driver-related factors included sex, educational level, license type, type of injury, duration between accident and getting the driving license and driver’s error type. Results: A total of 538 588 drivers (91.83% male, sex ratio of almost 13:1 were involved in the RTAs. Among them 423 932 (78.71% were uninjured; 224 818 (41.74% had a diploma degree. Grade 2 driving license represented the highest proportion of all driving licenses (290 811, 54.00%. The greatest number of accidents took place at 12:00-13:59 (75 024, 13.93%. The proportion of drivers involved in RTAs decreased from 15.90% in the first year of getting a driving license to 3.13% after 10 years’ of driving experience. Ne-glect of regulations was the commonest cause of traffic crashes (345 589, 64.17%. Non-observance of priority and inattention to the front were the most frequent final causes of death (138 175, 25.66% and 129 352, 24.02%, respectively. We found significant association between type of acci-dent and sex, education, license type, time of accident, final cause of accident, driver’s error as well as duration between accident and getting the driving license (all P<0.001. Conclusion: Our results will improve the traffic law enforcement measures, which will change inappropriate be-havior of drivers and protect the least experienced road users. Key words: Accidents, traffic; Automobile

  19. Accident management advisor system (AMAS): A Decision Aid for Interpreting Instrument Information and Managing Accident Conditions in Nuclear Power Plants

    for the development of models specifically tailored to real-time accident management. While it is almost impossible to develop and utilize exact models of the evolution of all possible accident sequences for each given type of nuclear power plant and containment design (e.g., PWR and BWR designs at various power ratings, large dry containment or ice condenser types, etc.), it appears possible to develop a sound approach to monitor the progression of an accident with respect to the integrity and effectiveness of a set of principal safety functions. The key to doing this is the development of a knowledge base 'housing structure', where uncertain knowledge regarding the predicted plant behavior and real-time, but also uncertain, information compiled from plant instrumentation readings can be compared and matched to produce the best possible identification of plant states and possible accident control actions. In summary: This paper illustrates the concept and the architecture of the Accident Management Advisor System, a decision aid which enables the use of combined instrument information to reduce uncertainty in decision making associated with nuclear plant accident conditions. The principal benefits offered by this concept are the definition of an approach to utilize instrument information under uncertain accident conditions in such a way as to allow the best possible assessment of plant status and the implementation of a formalized accident management decision-making strategy by means of a computer-based operator assistance tool. When fully developed, we expect AMAS to find application in both the commercial and government sections of the U.S. nuclear industry. We currently plan to have a working prototype of the system, ready to demonstrate its functionality for a representative commercial PWR plant, by the end of the next phase of our research, in which both model development and software development activities will have to be carried out. Finally, the AMAS

  20. Thermal-hydraulic modeling of reactivity accidents in MTR reactors

    Khater Hany; Abu-El-Maty Talal; El-Morshdy El-Din Salah

    2006-01-01

    This paper describes the development of a dynamic model for the thermal-hydraulic analysis of MTR research reactors during a reactivity insertion accident. The model is formulated for coupling reactor kinetics with feedback reactivity and reactor core thermal-hydraulics. To represent the reactor core, two types of channels are considered, average and hot channels. The developed computer program is compiled and executed on a personal computer, using the FORTRAN language. The model is validated...

  1. Recommendations on accident management for NPP with WWER

    The work deals with the analysis of practices in the field of beyond design basis accidents (BDBA) management in countries operating WWER type reactors. The recommendations of the working group are presented. The aim is to cooperate the actions of the regulatory bodies for the development of an unified concept for recommendations and to speed up the DBDA management realization for the decreasing of the risk from the nuclear power plant operation

  2. Modeling of DECL accident in the reactor containment by the CONTAIN 2.0 code

    Abbasi, Molood; Rahgoshay, Mohhamad [Islamic Azad Univ., Teheran (Iran, Islamic Republic of). Dept. of Nuclear Engineering, Science and Research Branch

    2013-11-15

    In this paper, a specific type of the Loss of Coolant Accident (LOCA), the DECL (Double Ended Cold Leg) break, that means totally Guillotine type of break in the cold leg pipe, has been modeled. The accident is simulated with the CONTAIN 2.0 code. In the event of a LOCA accident, coolant mass and energy are released to the containment through the break. This causes an increase of pressure and temperature in the containment. The modeling is performed in the VVER-1000 reactor containment. The analysis includes average pressure in the containment and temperature distribution in sample cells in the long-time. The results are compared with the existing reports on studies that used the ANGAR code. Results show that the CONTAIN 2.0 code is an adaptable tool for the analysis of nuclear events such as DECL accident. (orig.)

  3. Modeling of DECL accident in the reactor containment by the CONTAIN 2.0 code

    In this paper, a specific type of the Loss of Coolant Accident (LOCA), the DECL (Double Ended Cold Leg) break, that means totally Guillotine type of break in the cold leg pipe, has been modeled. The accident is simulated with the CONTAIN 2.0 code. In the event of a LOCA accident, coolant mass and energy are released to the containment through the break. This causes an increase of pressure and temperature in the containment. The modeling is performed in the VVER-1000 reactor containment. The analysis includes average pressure in the containment and temperature distribution in sample cells in the long-time. The results are compared with the existing reports on studies that used the ANGAR code. Results show that the CONTAIN 2.0 code is an adaptable tool for the analysis of nuclear events such as DECL accident. (orig.)

  4. Cognitive workload analysis of Angra II nuclear power plant operators under design basis accidents

    This article presents an application of cognitive modelling for evaluation the workload of nuclear operator crew. The task chosen for modelling was the small break LOCA accident in Angra II nuclear power plant. In this modelling the operation teamwork is composed by a reactor operator, a turbine operator and a shift supervisor. In the simulation the correct identification of the accident type by the team during the period of automatic actions carried through the plant protection systems is considered, i.e., the identification of the accident type is carried out during the first thirty minutes after the accident beginning. The ACT-R (Adaptive Control of Thought - Rules) was used for the simulation. The article also presents the description of the basic features of ACT-R model. We conclude that, despite the approaches made in the cognitive tasks, program ACT-R is a useful instrument for cognitive analysis of operator crew. (author)

  5. Worst case reactor accidents: a paradox

    The preliminary results from the application of improved source term methodology indicate a diversity of results for plants of different design, and for different accident sequences postulated for the same plant. While significant reductions from previous estimates are calculated with the new methodology for some accident scenarios, the same methodology predicts release magnitudes of minor difference from those produced with earlier methods for other accident sequences and plants. This divergence of calculated results precludes the adoption of a worst case as a meaningful characterization of severe accident consequences. This situation reinforces the need to consider the consequences of severe accidents only in light of their probability, even in those applications outside the traditional risk assessment process, and may necessitate re-consideration of a probability threshold for extremely low probability events. A practical approach to such a threshold value is discussed, based on NRC's experience with severe accident considerations in environmental impact statements

  6. Public health response to the nuclear accident

    The Act on Special Measures Concerning Nuclear Emergency Preparedness was established in 2000 as a specific act within the broader Disaster Control Measures and Reactor Regulation Act which was written in response to the JCO Criticality Accident of 1999. However, this regulatory system did not address all aspects of the Fukushima Daiichi Nuclear Power Plant Accident. This was especially evident with public health issues. For example, radioactive screening, prophylactic use of potassium iodide, support for vulnerable people, and management of contaminated dead bodies were all requested immediately after the occurrence of the nuclear power plant accident but were not included in these regulatory acts. Recently, the regulatory system for nuclear accidents has been revised in response to this reactor accident. Herein we review the revised plan for nuclear reactor accidents in the context of public health. (author)

  7. 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

  8. Barriers to learning from incidents and accidents

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

    2015-01-01

    This document provides an overview of knowledge concerning barriers to learning from incidents and accidents. It focuses on learning from accident investigations, public inquiries and operational experience feedback, in industrial sectors that are exposed to major accident hazards. The document discusses learning at organizational, cross-organizational and societal levels (impact on regulations and standards). From an operational standpoint, the document aims to help practitioners to identify...

  9. Social disparities and correlates of domestic accidents.

    Baumann, Michèle; Spitz, E.; Ravaud, J.; Guillemin, F.; Chau, N

    2009-01-01

    Domestic accidents are a public health problem. This study assessed the disparities between socioeconomic positions and the confounding role of gender, age, education, living alone, income, poor health, obesity, current tobacco use, alcohol abuse, fatigue/sleep disorders, and physical, sensorial and cognitive disabilities. Methods: 6,198 people aged ≥15, randomly selected in north-eastern France completed a post-mailed questionnaire including domestic accident(s) during the last two years. Th...

  10. Psychiatric consequences of road traffic accidents.

    Mayou, R; Bryant, B.; Duthie, R

    1993-01-01

    OBJECTIVE--To determine the psychiatric consequences of being a road traffic accident victim. DESIGN--Follow up study of road accident victims for up to one year. SETTING--Emergency department of the John Radcliffe Hospital, Oxford. SUBJECTS--188 consecutive road accident victims aged 18-70 with multiple injuries (motorcycle or car) or whiplash neck injury, who had not been unconscious for more than 15 minutes, and who lived in the catchment area. MAIN OUTCOME MEASURES--Present state examinat...

  11. Transportation accident scenarios for commercial spent fuel

    A spectrum of high severity, low probability, transportation accident scenarios involving commercial spent fuel is presented together with mechanisms, pathways and quantities of material that might be released from spent fuel to the environment. These scenarios are based on conclusions from a workshop, conducted in May 1980 to discuss transportation accident scenarios, in which a group of experts reviewed and critiqued available literature relating to spent fuel behavior and cask response in accidents

  12. Transportation accident scenarios for commercial spent fuel

    Wilmot, E L

    1981-02-01

    A spectrum of high severity, low probability, transportation accident scenarios involving commercial spent fuel is presented together with mechanisms, pathways and quantities of material that might be released from spent fuel to the environment. These scenarios are based on conclusions from a workshop, conducted in May 1980 to discuss transportation accident scenarios, in which a group of experts reviewed and critiqued available literature relating to spent fuel behavior and cask response in accidents.

  13. Synergy effect in accident simulation

    Accidental breaking of PWR coolant canalization would entail water vaporization into confinement enclosure. Equipments would be simultaneously subjected to temperature and pressure increase, chemical spray, and radiation action of reactor core products. Some equipments have to work after accident in order to stop reactor running and blow out water calories. Usually, in France, accident simulation tests are carried out sequentialy: irradiation followed by thermodynamical and chemical tests. Equipments working is essentially due to those polymer materials behaviour. Is the polymers behaviour the same when they are either subjected to sequential test, or an accident (simultaneous action of irradiation and thermodynamical and chemical sequence). In order to answer to this question, nine polymer materials were subjected to simultaneous and sequential test in CESAR cell. Experiments were carried out in CESAR device with thermodynamical chocks and a temperature and pressure decrease profil in presence or without irradiation. So, the test is either simultaneous or sequential. Mechanical properties change are determined for the following polymeric materials. Two polyamide-imide varnishes used in motors and coils; one epoxydic resin, glass fiber charged (electrical insulating); polyphenylene sulfide, glass fiber charged, the Ryton R4 (electrical insulating); three elastomeric materials: Hypalon, fire proof by bromine or by alumina EPDM (cables jacket); VAMAC which is a polyethylene methyl polymethacrylate copolymer; then a silicon thermoset material glass fiber charged (electrical insulating). After test, usually, mechanical and electrical properties change of polymer materials show sequential experiment is more severe than simultaneous test however, Hypalon does not follow this law. For this polymer simultaneous test appears more severe than sequential experiment

  14. Graphite Oxidation Simulation in HTR Accident Conditions

    El-Genk, Mohamed

    2012-10-19

    Massive air and water ingress, following a pipe break or leak in steam-generator tubes, is a design-basis accident for high-temperature reactors (HTRs). Analysis of these accidents in both prismatic and pebble bed HTRs requires state-of-the-art capability for predictions of: 1) oxidation kinetics, 2) air helium gas mixture stratification and diffusion into the core following the depressurization, 3) transport of multi-species gas mixture, and 4) graphite corrosion. This project will develop a multi-dimensional, comprehensive oxidation kinetics model of graphite in HTRs, with diverse capabilities for handling different flow regimes. The chemical kinetics/multi-species transport model for graphite burning and oxidation will account for temperature-related changes in the properties of graphite, oxidants (O2, H2O, CO), reaction products (CO, CO2, H2, CH4) and other gases in the mixture (He and N2). The model will treat the oxidation and corrosion of graphite in geometries representative of HTR core component at temperatures of 900°C or higher. The developed chemical reaction kinetics model will be user-friendly for coupling to full core analysis codes such as MELCOR and RELAP, as well as computational fluid dynamics (CFD) codes such as CD-adapco. The research team will solve governing equations for the multi-dimensional flow and the chemical reactions and kinetics using Simulink, an extension of the MATLAB solver, and will validate and benchmark the model's predictions using reported experimental data. Researchers will develop an interface to couple the validated model to a commercially available CFD fluid flow and thermal-hydraulic model of the reactor , and will perform a simulation of a pipe break in a prismatic core HTR, with the potential for future application to a pebble-bed type HTR.

  15. Radioactive waste transportation accident: are you prepared

    Tennessee Valley Authority (TVA) now has in operation, under construction, or in the design stage a total of 8 nuclear plants comprised of 17 units in the 1100 to 1300 MWe range. These plants are expected to generate a total of 234,000 cubic feet of low-level radioactive waste per year by 1986. The management, transportation, and ultimate disposal of this waste in an economical and environmentally safe manner is of primary importance to TVA. Since October 1973, approximately 300,000 miles have been logged by truck drivers hauling low-level radioactive wastes from TVA's Browns Ferry Nuclear Plant; and by 1986, transportation of low-level wastes from TVA nuclear power facilities will exceed 600,000 miles annually. With the knowledge that a transportation accident can occur and in the effort to be prepared when it occurs, TVA formulated and in conjunction with Alabama state and local officials implemented a plan in July 1977 to test the Radiological Emergency Plans of both TVA and the state of Alabama. It was decided that a transportation drill would be conducted and that this drill would involve those most likely to come into contact with this type of situation. For the interest of realism, no participant in the drill would know the exact place, date, or time; and furthermore, simulated radiological hazard problems would be involved. Simulation of the radiological accident occurred August 29, 1977, and initiated an action by local law officials, a local civil defense team, Alabama state radiological health personnel, a TVA radiological team, and the news media. The drill was termed a complete success. The TVA-REP had been tested and proven to be adequate in the event of a real emergency. Local and state civil defense organizations and state and local law enforcement authorities are revamping their radiological emergency training programs

  16. Injuries associated with cycle rickshaws accidents

    Meena, Sanjay; Barwar, Nilesh; Rastogi, Devarshi; Sharma, Vineet

    2014-01-01

    Context: Cycle rickshaw is an important means of transportation in Urban India. Pedestrians, rickshaw users, rickshaw pullers, two wheeled vehicle users and cyclists are among the most vulnerable road user groups in terms of injuries and fatalities resulting from road traffic accidents in India. Our objectives were to study characteristics of crashes and nature of injuries associated with cycle rickshaw. Patients and Methods: Between August 2008 to July 2009, a hospital based observational study was done of patients who presented to King George medical college trauma center with injury sustained due to cycle rickshaw in emergency department. Age, time of trauma, mode of trauma, contributing factors and type of injury were recorded. Results: The mean age of the patient was 32.1. Seventeen patients were rickshaw pullers and the rest were occupants of the rickshaw. Overloading with more than two passengers was found in 24 cases (28.5%). Most common cause of injury was collision with a moving vehicle (56 patients, %) followed by fall from rickshaw. The most common contributing factor was the overloading of rickshaw. On arrival to the hospital, the mean Injury severity score (ISS) was 3.5 ± 2.2 and the mean Glasgow coma scale (GCS) was 13.4 ± 4.3. Nine patients were admitted to ICU (Intensive care unit). The median ICU stay was 4 (1-24 days). Six of the ICU admitted patients had head injury. Conclusion: Rickshaw pullers and occupants are vulnerable to road traffic accidents. Urgent preventive measures targeted towards this group are needed to reduce the morbidity and mortality resulting from injuries involving rickshaws. The need for improved understanding of the risk characteristics of cycle rickshaw is emphasized. PMID:24812450

  17. Road Traffic Accident Victims’ Experiences of Return to Normal Life: A Qualitative Study

    Pashaei Sabet, Fatemeh; Norouzi Tabrizi, Kian; Khankeh, Hamid Reza; Saadat, Soheil; Abedi, Heidar Ali; Bastami, Alireza

    2016-01-01

    Background Road traffic accident (RTA) victims also suffer from different types of injuries and disabilities, which can affect their quality of life. They usually face with various physical, mental, and social problems. Most traffic accident victims had difficulty to return to normal life. Objectives This study aimed to understand the experiences of return to normal life in RTA victims. Patients and Methods This qualitative study with content analysis approach was conducted on 18 Iranian pati...

  18. Accidents leading to over-exertion back injuries among nursing personnel

    Engkvist, Inga-Lill

    1999-01-01

    The overall aim of the present thesis was to contribute to the knowledge of occupational accidents leading to over-exertion back injuries among nursing personnel, which can be used for developing effective preventive strategies. Different combinations of factors and events were assumed to determine the type of accident process leading to an over-exertion injury. The first study used the Swedish Occupational Injury Register (ISA) to investigate the occurrence of reported ...

  19. Estimates of early containment loads from core melt accidents. Draft report for comment

    The thermal-hydraulic processes and corium debris-material interactions that can result from core melting in a severe accident have been studied to evaluate the potential effect of such phenomena on containment integrity. Pressure and temperature loads associated with representative accident sequences have been estimated for the six various LWR containment types used within the United States. Summaries distilling the analyses are presented and an interpretation of the results provided. 13 refs., 68 figs., 39 tabs

  20. Preliminary assessment of the accident probabilities of a NERVA derivative reactor for space power applications

    Gas cooled, solid core graphite reactors based on the Nuclear Engine Rocket Vehicle Application (NERVA) technology are attractive space nuclear power sources for SDI multimegawatt applications. A reactor of this type is called a NERVA Derivative Reactor (NDR). A simplified accident probability analysis of a NDR reactor for space power mission was carried out. The objective of the analysis was to identify the worst case accident and critical reactor design areas where the incorporation of appropriate design features may reduce the risks involved

  1. Accidents with tractors and agricultural machinery in public transport of Republic of Serbia without provinces

    Gliogrevic, Kosta; Oljaca, Mico; Ruzicic, Lazar; Dimitrovski, Zoran

    2012-01-01

    Working processes in agriculture nowadays cannot be imagined without the use of modern agricultural mechanization, especially primary power unit, tractor. Along with the tractor unit development and the benefits induced by its application, according to the author’s research, these machines are one of the main causes of accidents with different types of violations of the participants, and the tragic consequences. The great number of those accidents with tractors and other agricultural machiner...

  2. Estimates of early containment loads from core melt accidents. Draft report for comment

    None

    1985-12-01

    The thermal-hydraulic processes and corium debris-material interactions that can result from core melting in a severe accident have been studied to evaluate the potential effect of such phenomena on containment integrity. Pressure and temperature loads associated with representative accident sequences have been estimated for the six various LWR containment types used within the United States. Summaries distilling the analyses are presented and an interpretation of the results provided. 13 refs., 68 figs., 39 tabs.

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

    Funnemark, E. [Det Norske Veritas Industry AS, (Norway); Young, E. [Health and Safety Executive, (United Kingdom)

    2003-07-01

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

  4. Guidance on accidents involving radioactivity

    This booklet sets out United Kingdom government policy on the management of the effects of radioactivity accidents by the Health Service. Monitoring of persons affected will be undertaken by hospital staff in order to assess damage levels for the whole population as well as treat individuals, while general practitioners will disseminate information from the Department of Health. The National Response Plan is set out, covering incidents connected with the use or transport of radioactive substances, and emergency plans for incidents in civil nuclear installations. (UK)

  5. The radiological accident in Goiania

    The report is based on a meeting held in Brazil, 19-27 July 1988. It describes how the accident occurred, examines how it was managed and how its consequences were contained, and sets out observations and recommendations based upon lessons learned. Many people received large doses of radiation, due to both external and internal exposure. Four of the casualties ultimately died and 28 people suffered radiation burns. Residences and public places were contaminated. The decontamination necessitated the demolition of seven residences and various other buildings, and the removal of the topsoil from large areas. In total 3,500 m3 of radioactive waste was generated. Refs, figs, tabs and photographs

  6. The Tokay-Mura accident

    On the 30. september 1999 occurred a criticality accident in the fuel fabrication plant of Tokai-Mura in Japan. 49 persons were irradiated but we present the case of the most seriously injured three workers. The radiation doses that would have been received by the three operators near the incriminated container have been evaluated to 17, 10 and 3 Grays. For the operators situated at five meters from the container and that has received three Grays, the first peak of criticality has been estimated at 2.1017 fissions. The number of fissions posterior to the first peak has been estimated between 4.1017 and 5.1018. In the three cases, the dose received by the organism has been attributed for about 40% to the neutrons and 60% to gamma radiations. The first operator presented an initial intense phase of acute irradiation syndrome. He received a graft of hematopoietic cells given by a sister of him on the sixth day, he was still alive 29 days later during the visit of the Commission, but he was in a coma and died shortly afterwards. The second victim has been equally reached by an acute irradiation syndrome, accompanied by a severe myeloid depression. At the ninth day, he received a blood graft coming from umbilical cord. He recovered a part of his own marrow, platelets excepted. He suffers from intense pains. A survival chance exists. The third victim was in an adjoining room, at about five meters far from the accident. He has been reached, but in a lower extent, by the acute irradiation syndrome and a low myeloid depression, that has decreased after a growth factors treatment. The prognosis is optimist in his case. The fact that patients have survived for the first time such a long time has revealed a very particular pathology of neutrons-gamma mixed irradiation, with an appearance of new medical problems due to the multiple failure of organs. To notice, the week before the accident, stood at Paris the 6. International conference devoted to the control of criticality

  7. Interventions after serious reactor accidents

    Manifold and promising approaches to active measures to be taken during accidents were studied hypothetically at the HTR which already has outstanding inherent safety properties in respect of afterheat removal. Based on incident scenarios prepared for hypothetical air inleakage incidents, in particular into the core of the HTR module reactor, many and various peripheral conditions for intervention possibilities could be studied. In addition, intervention possibilities appropriate for the respective incidents were examined as to their feasibility and consequences to be expected after their application. From these studies suggestions were derived for verifying experiments. (orig./HP) With 66 refs., 24 tabs., 79 figs

  8. Probabilistic accident sequence recovery analysis

    Recovery analysis is a method that considers alternative strategies for preventing accidents in nuclear power plants during probabilistic risk assessment (PRA). Consideration of possible recovery actions in PRAs has been controversial, and there seems to be a widely held belief among PRA practitioners, utility staff, plant operators, and regulators that the results of recovery analysis should be skeptically viewed. This paper provides a framework for discussing recovery strategies, thus lending credibility to the process and enhancing regulatory acceptance of PRA results and conclusions. (author)

  9. Design basis accident calculation problems

    Sudden failures of the primary circuit is the design basis accident of pressurized water reactors, being liable to affect the other two barriers separating the fission products from the environment. The calculation of the thermohydraulic behavior of the core and primary circuit is at present based, for the CEA, on the RELAP 4 code. However a second-generation code, POSEIDON, is being developed by the CEA, EDF and FRAMATOME to obtain a better description of the physical phenomena and a better estimate of safety margins. Other difficult problems arise in connection with the calculation of structural stresses and the behavior of the vessel during decompression

  10. Industrial Safety and Accidents Prevention

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

  11. The Role of Countermeasures in Mitigating the Radiological Consequences of Nuclear Power Plant Accidents

    During the Fukushima accident the mitigation actions played an important role to decrease the consequences of the accident. The countermeasures are the actions that should be taken after the occurrence of a nuclear accident to protect the public against the associated risk. The actions may be represented by sheltering, evacuation, distribution of stable iodine tablets and/or relocation. This study represents a comprehensive probabilistic study to investigate the role of the adoption of the countermeasures in case of a hypothetical accident of type LOCA for a nuclear power plant of PWR (1000 Mw) type. This work was achieved through running of the PC COSYMA(1) code. The effective doses in different organs, short and long term health effects, and the associated risks were calculated with and without countermeasures. In addition, the overall costs of the accident and the costs of countermeasures are estimated which represent our first trials to know how much the postulated accident costs. The source term of a hypothetical accident is determined by knowing the activity of the core inventory. The meteorological conditions around the site in addition to the population distribution were utilized as input parameters. The stability conditions and the height of atmospheric boundary layers ABL of the concerned site were determined by developing a computer program utilizing Pasquill-Gifford atmospheric stability conditions. The results showed that, the area around the site requires early and late countermeasures actions after the accident especially in the downwind sectors. For late countermeasures, the duration of relocation ranged from about two to 10 years. The adoption of the countermeasures increases the costs of emergency planning by 40% but reduces the risk associated with the accident. (author)

  12. The cost of nuclear accidents in France

    IRSN has produced estimates for costs of possible nuclear accidents on French PWRs. This paper outlines the strong differences between severe accidents, which feature a core melt but more or less controlled radioactive releases, and major accidents implying massive releases. In the first case, crisis managers would be faced with a mainly 'economic' accident, the larger part of costs being borne in a diffused fashion by the economy at large (image costs and impacts on electricity production). In the second case, authorities would be faced with the challenges of a full-scale radiological crisis involving sizeable areas of contaminated territories and large numbers of radiological refugees. (author)

  13. Medical experience: Chernobyl and other accidents

    A radiation accident can be defined as an involuntary relevant exposure of man to ionising radiation or radioactive material. Provided one of the ensuing criteria is met with at least one person involved in an excursion of ionising radiation and or radioactive material, the respective incident can be considered a radiation accident in accordance with ICRP, NCRP (US), and WHO: ≥0.25 Sv total body irradiation with lesions of the rapidly dividing tissues; ≥6 Sv cutaneous and local irradiation; ≥0.4 Sv local irradiation of other organ systems through external sources; incorporation equal to or in excess of more than half of the maximum permissible organ burden; and medical accidents meeting one of the above criteria. Several actions have been taken to categorise radiation accidents in order to learn from previous accidents in terms of both managerial and medical experience. For this presentation three approaches will be discussed concerning their relevance to the individual treatment and risk management. This will be obtained by applying three classification schemes to all known radiation accidents: 1. classification with respect to the accident mechanism, 2. classification concerning the radiation injury, and 3. classification concerning the extent of the accident. In a fourth chapter the efficacy of bone marrow transplantation will briefly be commented on based on the accumulated experience of about 400 radiation accidents world-wide. (author)

  14. Systematics of Reconstructed Process Facility Criticality Accidents

    Pruvost, N.L.; McLaughlin, T.P.; Monahan, S.P.

    1999-09-19

    The systematics of the characteristics of twenty-one criticality accidents occurring in nuclear processing facilities of the Russian Federation, the United States, and the United Kingdom are examined. By systematics the authors mean the degree of consistency or agreement between the factual parameters reported for the accidents and the experimentally known conditions for criticality. The twenty-one reported process criticality accidents are not sufficiently well described to justify attempting detailed neutronic modeling. However, results of classic hand calculations confirm the credibility of the reported accident conditions.

  15. Review of specific radiological accident considerations

    Specific points of guidance provided in the forthcoming document A Guide to Radiological Accident Considerations for Siting and Design of Nonreactor Nuclear Facilities are discussed. Of these, the following are considered of particular interest to analysts of hypothetical accidents: onsite dose limits; population dose, public health effects, and environmental contamination as accident consequences which should be addressed; risk analysis; natural phenomena as accident initiators; recommended dose models; multiple organ equivalent dose; and recommended methods and parameters for source terms and release amount calculations. Comments are being invited on this document, which is undergoing rewrite after the first stage of peer review

  16. Genetic effects of the Chernobyl accident

    Genetic radiation effects resulted from the Chernobyl accident were considered for the population of Russia, Ukraine and Belarus. Techniques of the assessment of genetic risk of exposure of a man was discussed. Results of cytogenetic examination of the population were presented as well as health state of pregnants and newborns following the Chernobyl accident. Elevated level of chromosomal aberrations in lymphocytes of peripheric blood in participants of the Chernobyl accident response and in population of contaminated zones. This fact testifies on the real genetic injury in cells due to accident. Growth of intrauterine losses in pregnancy, congenital anomalies, hereditary diseases in descendants of exposed parents. 17 figs

  17. Development of severe accident training support system

    In order for appropriate decision-making during plant operation and management, the professional knowledge, expert's opinion, and previous experiences as well as information for current status are utilized. The operation support systems such as training simulators have been developed to assist these decision-making process, and most of them cover from normal operation to emergency operation because of the very low frequency of severe accident and of uncertaintics included in severe accident phenomena and scenarios. However, the architectures for severe accident management are being established based on severe accident management guidelines in some developed countries. Recentrly, in Korea, as teh severe accident management guideline was developed, the basis for establishing severe accident management architecture is prepared and this leads to the development of tool for systematic education and training for personnel related to severe accident management. The severe accident taining support system thus is developed to assist decision-making during execution of severe accident management guidelines by providing plant status information, prefessional knowledge for phenomena and scenarios, expected behavior for strategy execution, and so on

  18. 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.

  19. Chernobylsk NPP accident and its medical effects

    Medical effects of the Chernobyl accident for various groups of people engaged in liquidation of the accident aftereffects and residents of the regions affected are assessed. Specific medical and social recommendations for each of the five groups of patients are made. Special attention is paid to the health of children who were exposed to external radiation in combination with intake of iodine isotopes. Extremely unfavourable influence of the mass media on the health of people involved in the Chernobyl accident is painted out. The necessity of adequate rehabilitation measures for various categories of patients involved in a large-scale accident is emphasized

  20. Accident Analysis and Countermeasures of the Enterprises Involved in Ammonia%涉氨企业事故分析与对策

    卢均臣; 王延平

    2015-01-01

    从事故发生环节、事故类型、事故设备、事故原因等几个方面分析了2005年-2014年全国涉氨企业发生的事故。分析表明:储存和使用环节事故最多;事故主要类型事故泄漏和中毒;主要发生在食品厂、肉类加工厂、冷饮厂、水产公司、果蔬公司、制药厂的制冷车间;主要发生在管道、储罐、阀门、法兰等部位;材料失效事故占比最高。最后,提出了预防此类事故的建议措施。%Accidents occurred in 2005-2014 in our country were analyzed from the aspects of the accident link, accident type, accident equipment, accident cause. Analysis showed that accidents in links of the storage and use were the most, the main types of accidents were leakage and poisoning, accidents mainly occured in food factory, meat processing factory, beverage factory, etc, accidents mainly occured in pipeline, storage tanks, valves, flanges, etc, the amount of accidents caused by material failure was the largest. Suggestions for preventing such accidents were put forward.

  1. Construction of a technique plan repository and evaluation system based on AHP group decision-making for emergency treatment and disposal in chemical pollution accidents

    Highlights: • Different chemical pollution accidents were simplified using the event tree analysis. • Emergency disposal technique plan repository of chemicals accidents was constructed. • The technique evaluation index system of chemicals accidents disposal was developed. • A combination of group decision and analytical hierarchy process (AHP) was employed. • Group decision introducing similarity and diversity factor was used for data analysis. - Abstract: The environmental pollution resulting from chemical accidents has caused increasingly serious concerns. Therefore, it is very important to be able to determine in advance the appropriate emergency treatment and disposal technology for different types of chemical accidents. However, the formulation of an emergency plan for chemical pollution accidents is considerably difficult due to the substantial uncertainty and complexity of such accidents. This paper explains how the event tree method was used to create 54 different scenarios for chemical pollution accidents, based on the polluted medium, dangerous characteristics and properties of chemicals involved. For each type of chemical accident, feasible emergency treatment and disposal technology schemes were established, considering the areas of pollution source control, pollutant non-proliferation, contaminant elimination and waste disposal. Meanwhile, in order to obtain the optimum emergency disposal technology schemes as soon as the chemical pollution accident occurs from the plan repository, the technique evaluation index system was developed based on group decision-improved analytical hierarchy process (AHP), and has been tested by using a sudden aniline pollution accident that occurred in a river in December 2012

  2. Mapping patterns and characteristics of fatal road accidents in Israel

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

    2010-01-01

    without a priori assumptions about the expected outcome of the study. Kohonen neural networks reveal five accident patterns: (i) single-vehicle accidents of young drivers; (ii) multiple-vehicle accidents between young drivers; (iii) accidents involving either motorcycles or bicycles; (iv) accidents where...

  3. 41 CFR 101-39.407 - Accident records.

    2010-07-01

    ... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Accident records. 101-39...-INTERAGENCY FLEET MANAGEMENT SYSTEMS 39.4-Accidents and Claims § 101-39.407 Accident records. If GSA's records of vehicle accidents indicate that a particular activity has had an unusually high accident...

  4. 22 CFR 102.17 - Reports on accident.

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Reports on accident. 102.17 Section 102.17... Accidents Abroad Foreign Aircraft Accidents Involving United States Persons Or Property § 102.17 Reports on accident. When an accident occurs to a foreign aircraft in the district of a Foreign Service post...

  5. Simulation of severe accident in reactor core for training and accident management

    An Advanced Real-time Severe Accident Simulation (ARTSAS) train reactor operators and accident management teams for scenarios simulating severe accidents in nuclear reactors. The code has been integrated with the real-time tools and the RAINBO graphic package to provide training and analysis tools on workstations as well as on full-scope simulators. (orig.) (4 refs., 1 fig.)

  6. Unconventional sources of plant information for accident management

    An essential element to accident management is having as clear a picture as is practical of the plant status and thus of the accident and its progress. Effective, appropriate decisions to control and mitigate an accident are dependent on making this assessment of the accident. The objective of this paper is to stimulate consideration of unconventional plant information sources through discussion of specific examples. A plant's condition during an accident can be characterized by plant parameters such as temperatures and pressures and by plant system operational status. For example, core damage is associated with increasing temperatures, pressures, and radiation levels in many different systems and plant areas. Reg. Guide 1.97 instrumentation exists to provide information to allow operators to take specified manual actions (Type A), to indicate whether plant safety functions are being accomplished (Type B), to indicate the potential for breach of barriers to fission product release (Type C), to indicate operability of individual safety systems (Type D), and to indicate the magnitude of radioactive material releases (Type E). Reg. Guide 1.97 instrument range requirements, with the exception of pressure instruments, address conditions up to design basis conditions. Pressure instrument range requirements exceed design basis conditions. During a severe accident, some instruments may not see conditions beyond their design basis. Effective accident management includes the ability to establish a consistent picture of the accident by accumulating information from as many sources as is practical. Operability of systems and components, and non-safety related temperature, radiation, pressure, and water-level indication can be used to directly indicate, measure, or infer plant parameters which confirm, augment or replace those otherwise available. Innovative uses of information sources thus serve to increase the diversity and flexibility of accident data available. Both the

  7. CANDU safety under severe accidents

    The characteristics of the CANDU reactor relevant to severe accidents are set first by the inherent properties of the design, and second by the Canadian safety/licensing approach. The pressure-tube concept allows the separate, low-pressure, heavy-water moderator to act as a backup heat sink even if there is no water in the fuel channels. Should this also fail, the calandria shell itself can contain the debris, with heat being transferred to the water-filled shield tank around the core. Should the severe core damage sequence progress further, the shield tank and the concrete reactor vault significantly delay the challenge to containment. Furthermore, should core melt lead to containment overpressure, the containment behaviour is such that leaks through the concrete containment wall reduce the possibility of catastrophic structural failure. The Canadian licensing philosophy requires that each accident, together with failure of each safety system in turn, be assessed (and specified dose limits met) as part of the design and licensing basis. In response, designers have provided CANDUs with two independent dedicated shutdown systems, and the likelihood of Anticipated Transients Without Scram is negligible. Probabilistic safety assessment studies have been performed on operating CANDU plants, and on the 4 x 880 MW(e) Darlington station now under construction; furthermore a scoping risk assessment has been done for a CANDU 600 plant. They indicate that the summed severe core damage frequency is of the order of 5 x 10-6/year. 95 refs, 3 tabs

  8. CANDU safety under severe accidents

    The characteristics of the CANDU reactor relevant to severe accidents are set first by the inherent properties of the design, and second by the Canadian safety/licensing approach. Probabilistic safety assessment studies have been performed on operating CANDU plants, and on the 4 x 880 MW(e) Darlington station now under construction; furthermore a scoping risk assessment has been done for a CANDU 600 plant. They indicate that the summed severe core damage frequency is of the order of 5 x 10-6/year. CANDU nuclear plant designers and owner/operators share information and operational experience nationally and internationally through the CANDU Owners' Group (COG). The research program generally emphasizes the unique aspects of the CANDU concept, such as heat removal through the moderator, but it has also contributed significantly to areas generic to most power reactors such as hydrogen combustion, containment failure modes, fission product chemistry, and high temperature fuel behaviour. Abnormal plant operating procedures are aimed at first using event-specific emergency operating procedures, in cases where the event can be diagnosed. If this is not possible, generic procedures are followed to control Critical Safety Parameters and manage the accident. Similarly, the on-site contingency plans include a generic plan covering overall plant response strategy, and a specific plan covering each category of contingency

  9. 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

  10. Severe Accident Research Program plan update

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

  11. Severities of transportation accidents involving large packages

    The study was undertaken to define in a quantitative nonjudgmental technical manner the abnormal environments to which a large package (total weight over 2 tons) would be subjected as the result of a transportation accident. Because of this package weight, air shipment was not considered as a normal transportation mode and was not included in the study. The abnormal transportation environments for shipment by motor carrier and train were determined and quantified. In all cases the package was assumed to be transported on an open flat-bed truck or an open flat-bed railcar. In an earlier study, SLA-74-0001, the small-package environments were investigated. A third transportation study, related to the abnormal environment involving waterways transportation, is now under way at Sandia Laboratories and should complete the description of abnormal transportation environments. Five abnormal environments were defined and investigated, i.e., fire, impact, crush, immersion, and puncture. The primary interest of the study was directed toward the type of large package used to transport radioactive materials; however, the findings are not limited to this type of package but can be applied to a much larger class of material shipping containers

  12. Severities of transportation accidents involving large packages

    Dennis, A.W.; Foley, J.T. Jr.; Hartman, W.F.; Larson, D.W.

    1978-05-01

    The study was undertaken to define in a quantitative nonjudgmental technical manner the abnormal environments to which a large package (total weight over 2 tons) would be subjected as the result of a transportation accident. Because of this package weight, air shipment was not considered as a normal transportation mode and was not included in the study. The abnormal transportation environments for shipment by motor carrier and train were determined and quantified. In all cases the package was assumed to be transported on an open flat-bed truck or an open flat-bed railcar. In an earlier study, SLA-74-0001, the small-package environments were investigated. A third transportation study, related to the abnormal environment involving waterways transportation, is now under way at Sandia Laboratories and should complete the description of abnormal transportation environments. Five abnormal environments were defined and investigated, i.e., fire, impact, crush, immersion, and puncture. The primary interest of the study was directed toward the type of large package used to transport radioactive materials; however, the findings are not limited to this type of package but can be applied to a much larger class of material shipping containers.

  13. Solid waste accident analysis in support of the Savannah River Waste Management Environmental Impact Statement

    The potential for facility accidents and the magnitude of their impacts are important factors in the evaluation of the solid waste management addressed in the Environmental Impact Statement. The purpose of this document is to address the potential solid waste management facility accidents for comparative use in support of the Environmental Impact Statement. This document must not be construed as an Authorization Basis document for any of the SRS waste management facilities. Because of the time constraints placed on preparing this accident impact analysis, all accident information was derived from existing safety documentation that has been prepared for SRS waste management facilities. A list of facilities to include in the accident impact analysis was provided as input by the Savannah River Technology Section. The accident impact analyses include existing SRS waste management facilities as well as proposed facilities. Safety documentation exists for all existing and many of the proposed facilities. Information was extracted from this existing documentation for this impact analysis. There are a few proposed facilities for which safety analyses have not been prepared. However, these facilities have similar processes to existing facilities and will treat, store, or dispose of the same type of material that is in existing facilities; therefore, the accidents can be expected to be similar

  14. Management of a radiological emergency. Experience feedback and post-accident management

    In France, the organization of crisis situations and the management of radiological emergency situations are regularly tested through simulation exercises for a continuous improvement. Past severe accidents represent experience feedback resources of prime importance which have led to deep changes in crisis organizations. However, the management of the post-accident phase is still the object of considerations and reflections between the public authorities and the intervening parties. This document presents, first, the nuclear crisis exercises organized in France, then, the experience feedback of past accidents and exercises, and finally, the main aspects to consider for the post-accident management of such events: 1 - Crisis exercises: objectives, types (local, national and international exercises), principles and progress, limits; 2 - Experience feedback: real crises (major accidents, other recent accidental situations or incidents), crisis exercises (experience feedback organization, improvements); 3 - post-accident management: environmental contamination and people exposure, management of contaminated territories, management of populations (additional protection, living conditions, medical-psychological follow up), indemnification, organization during the post-accident phase; 4 - conclusion and perspectives. (J.S.)

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

    Evans, Joni K.

    2013-01-01

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

  16. Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

    According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident

  17. The Chernobyl reactor accident source term: Development of a consensus view

    In August 1986, scientists from the former Soviet Union provided the nuclear safety community with an impressively detailed account of what was then known about the Chernobyl accident. This included assessments of the magnitudes, rates, and compositions of radionuclide releases during the ten days following initiation of the accident. A summary report based on the Soviet report, the oral presentations, and the discussions with scientists from various countries was issued by the International Atomic Energy Agency shortly thereafter. Ten years have elapsed since the reactor accident at Chernobyl. A great deal more data is now available concerning the events, phenomena, and processes that took place. The purpose of this document is to examine what is known about the radioactive materials released during the accident. The accident was peculiar in the sense that radioactive materials were released, at least initially, in an exceptionally energetic plume and were transported far from the reactor site. Release of radioactivity from the plant continued for about ten days. A number of more recent publications and results from scientists in Russia and elsewhere have significantly improved our understanding of the Chernobyl source term. Because of the special features of the reactor design and the pecularities of the Chernobyl accident, the source term for the Chernobyl accident is of limited applicability of the safety analysis of other types of reactors

  18. Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

    Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T. [KAIST, Daejeon (Korea, Republic of); Lee, So I. [KHNP CRI, Daejeon (Korea, Republic of)

    2014-10-15

    According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident.

  19. The Chernobyl reactor accident source term: development of a consensus view

    Ten years after the reactor accident at Chernobyl, a great deal more data is available concerning the events, phenomena, and processes that took place. The purpose of this document is to examine what is known about the radioactive materials released during the accident, a task that is substantially more difficult than it might first appear to be. The Chernobyl station, like other nuclear power plants, was not instrumented to characterize a disastrous accident. The accident was peculiar in the sense that radioactive materials were released, at least initially, in an exceptionally energetic plume and were transported far from the reactor site. Release of radioactivity from the plant continued for several days. Characterization of the contamination caused by the releases of radioactivity has had a much lower priority than remediation of the contamination. Consequently, an assessment of the Chernobyl accident source term must rely to a significant extent on inferential evidence. The assessment presented here begins with an examination of the core inventories of radioactive materials. In subsequent sections of the report, the magnitude and timing of the releases of radioactivity are described. Then, the composition, chemical forms, and physical forms of the releases are discussed. A number of more recent publications and results from scientists in Russia and elsewhere have significantly improved the understanding of the Chernobyl source term. Because of the special features of the reactor design and the peculiarities of the Chernobyl accident, the source term for the Chernobyl accident is of limited applicability to the safety analysis of other types of reactors

  20. Development of transmitter with hybrid-IC for Post-accident monitoring instrumentation

    After the TMI accident, Post-accident Monitoring (PAM) Instrumentation based on the U.S. Guideline (R.G.1.97) was applied to Japanese PWRs. And we have back-fitted the PAM Instrumentation to old plants step by step. Recently, new type transmitters arrive on the market. They have better accuracy, and stability than old type. However, they cannot be applied as the PAM instrumentation, because new type are insufficient in a qualification for the PAM instrumentation and a modification to endure in-containment accident conditions. Hence, Japanese PWR utilities and Mitsubishi Heavy Industries are developing a new type transmitter for PAM instrumentation to improve accuracy and stability in the period of 1994 through 1996. This paper describes nowadays results in this development of a new PAM transmitter. (author). 8 figs, 3 tabs