Sample records for accident management

  1. Accident Management in VVER-1000

    F. D'Auria


    Full Text Available The present paper deals with the investigation study on accident management in VVER-1000 reactor type conducted in the framework of a European Commission funded project. The mentioned study involved both experimental and computational fields. The purpose of this paper is to summarize the main findings from the execution of a wide-range analysis focused on AM in VVER-1000 with main regard to the qualification of computational tools and the proposal for an optimal AM strategy for this kind of NPP.

  2. [Practical management of CPB accident].

    Depoix, J-P; Fenet, L; Provenchere, S


    Accident of CPB is a reality. It is important to be prepared for discussion with the family, with the hospital administration, eventually with the justice. But we have also to support perfusionnist and anesthetic team in charge of the patient during accident.

  3. Accident knowledge and emergency management

    Rasmussen, B.; Groenberg, C.D.


    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.

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

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


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

  5. Development of severe accident management and training support system

    Jeong, Kwang Sub; Kim, Ko Ryo; Jung, Won Dae; Ha, Jae Joo


    Recently, the overall severe accident management strategy is under development according to the logical flow of severe accident management guidelines in some foreign countries. In Korea, the basis of severe accident management strategy is established due to the development of Korean severe accident guideline. In the straining system, the professional information as well as the general information for severe accident should be provided to the related personnel and the function of prior simulation for plant behavior according to strategy execution should be required. Korean severe accident management guideline is chosen as the basis logic for development of support system for decision-support and training related with execution of severe accident strategy. The training simulator is developed for prior expectation of plant behavior and the severe accident computer code, MELCOR, is utilized as the engine, and it is possible to operate equipments necessary for execution of severe accident management guidelines. And also, the graphical interface is developed to provide the plant status and provide status change of major equipments dynamically.

  6. Summary of a workshop on severe accident management for BWRs

    Kastenberg, W.E. [ed.; Apostolakis, G.; Jae, M.; Milici, T.; Park, H.; Xing, L.; Dhir, V.K.; Lim, H.; Okrent, D.; Swider, J.; Yu, D. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering


    Severe accident management can be defined as the use of existing and/or alternative resources, systems and actions to prevent or mitigate a core-melt accident. For each accident sequence and each combination of strategies there may be several options available to the operator; and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrument behavior during an accident. During the period September 26--28, 1990, a workshop was held at the University of California, Los Angeles, to address these uncertainties for Boiling Water Reactors (BWRs). This report contains a summary of the workshop proceedings.

  7. Applying Functional Modeling for Accident Management of Nuclear Power Plant

    Lind, Morten; Zhang, Xinxin


    The paper investigate applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow...

  8. Applying Functional Modeling for Accident Management of Nucler Power Plant

    Lind, Morten; Zhang, Xinxin


    The paper investigates applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow...... for information sharing and decision support in accidents beyond design basis is also indicated. A modelling example demonstrating the application of Multilevel Flow Modelling and reasoning for a PWR LOCA is presented....

  9. Development of Parameter Network for Accident Management Applications

    Pak, Sukyoung; Ahemd, Rizwan; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of); Kim, Jung Taek; Park, Soo Yong; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    When a severe accident happens, it is hard to obtain the necessary information to understand of internal status because of the failure or damage of instrumentation and control systems. We learned the lessons from Fukushima accident that internal instrumentation system should be secured and must have ability to react in serious conditions. While there might be a number of methods to reinforce the integrity of instrumentation systems, we focused on the use of redundant behavior of plant parameters without additional hardware installation. Specifically, the objective of this study is to estimate the replaced value which is able to identify internal status by using set of available signals when it is impossible to use instrumentation information in a severe accident, which is the continuation of the paper which was submitted at the last KNS meeting. The concept of the VPN was suggested to improve the quality of parameters particularly to be logged during severe accidents in NPPs using a software based approach, and quantize the importance of each parameter for further maintenance. In the future, we will continue to perform the same analysis to other accident scenarios and extend the spectrum of initial conditions so that we are able to get more sets of VPNs and ANN models to predict the behavior of accident scenarios. The suggested method has the uncertainty underlain in the analysis code for severe accidents. However, In case of failure to the safety critical instrumentation, the information from the VPN would be available to carry out safety management operation.

  10. Applying Functional Modeling for Accident Management of Nuclear Power Plant

    Lind, Morten; Zhang Xinxin [Harbin Engineering University, Harbin (China)


    The paper investigate applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow Modeling is given and a detailed presentation of the foundational means-end concepts is presented and the conditions for proper use in modelling accidents are identified. It is shown that Multilevel Flow Modeling can be used for modelling and reasoning about design basis accidents. Its possible role for information sharing and decision support in accidents beyond design basis is also indicated. A modelling example demonstrating the application of Multilevel Flow Modelling and reasoning for a PWR LOCA is presented.

  11. Development of Integrated Evaluation System for Severe Accident Management

    Kim, Dong Ha; Kim, K. R.; Park, S. H.; Park, S. Y.; Park, J. H.; Song, Y. M.; Ahn, K. I.; Choi, Y


    The objective of the project is twofold. One is to develop a severe accident database (DB) for the Korean Standard Nuclear Power plant (OPR-1000) and a DB management system, and the other to develop a localized computer code, MIDAS (Multi-purpose IntegrateD Assessment code for Severe accidents). The MELCOR DB has been constructed for the typical representative sequences to support the previous MAAP DB in the previous phase. The MAAP DB has been updated using the recent version of MAAP 4.0.6. The DB management system, SARD, has been upgraded to manage the MELCOR DB in addition to the MAAP DB and the network environment has been constructed for many users to access the SARD simultaneously. The integrated MIDAS 1.0 has been validated after completion of package-wise validation. As the current version of MIDAS cannot simulate the anticipated transient without scram (ATWS) sequence, point-kinetics model has been implemented. Also the gap cooling phenomena after corium relocation into the RPV can be modeled by the user as an input parameter. In addition, the subsystems of the severe accident graphic simulator are complemented for the efficient severe accident management and the engine of the graphic simulator was replaced by the MIDAS instead of the MELCOR code. For the user's convenience, MIDAS input and output processors are upgraded by enhancing the interfacial programs.

  12. Use of decision trees for evaluating severe accident management strategies in nuclear power plants

    Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of). Dept. of Nuclerar Engineering; Lee, Yongjin; Jerng, Dong Wook [Chung-Ang Univ., Seoul (Korea, Republic of). School of Energy Systems Engineering


    Accident management strategies are defined to innovative actions taken by plant operators to prevent core damage or to maintain the sound containment integrity. Such actions minimize the chance of offsite radioactive substance leaks that lead to and intensify core damage under power plant accident conditions. Accident management extends the concept of Defense in Depth against core meltdown accidents. In pressurized water reactors, emergency operating procedures are performed to extend the core cooling time. The effectiveness of Severe Accident Management Guidance (SAMG) became an important issue. Severe accident management strategies are evaluated with a methodology utilizing the decision tree technique.

  13. Accident Precursor Analysis and Management: Reducing Technological Risk Through Diligence

    Phimister, James R. (Editor); Bier, Vicki M. (Editor); Kunreuther, Howard C. (Editor)


    Almost every year there is at least one technological disaster that highlights the challenge of managing technological risk. On February 1, 2003, the space shuttle Columbia and her crew were lost during reentry into the atmosphere. In the summer of 2003, there was a blackout that left millions of people in the northeast United States without electricity. Forensic analyses, congressional hearings, investigations by scientific boards and panels, and journalistic and academic research have yielded a wealth of information about the events that led up to each disaster, and questions have arisen. Why were the events that led to the accident not recognized as harbingers? Why were risk-reducing steps not taken? This line of questioning is based on the assumption that signals before an accident can and should be recognized. To examine the validity of this assumption, the National Academy of Engineering (NAE) undertook the Accident Precursors Project in February 2003. The project was overseen by a committee of experts from the safety and risk-sciences communities. Rather than examining a single accident or incident, the committee decided to investigate how different organizations anticipate and assess the likelihood of accidents from accident precursors. The project culminated in a workshop held in Washington, D.C., in July 2003. This report includes the papers presented at the workshop, as well as findings and recommendations based on the workshop results and committee discussions. The papers describe precursor strategies in aviation, the chemical industry, health care, nuclear power and security operations. In addition to current practices, they also address some areas for future research.

  14. Market-oriented management method of coalmine accident hidden dangers

    LIU Zhao-xia; LI Xing-dong; LU Ying; REN Da-wei


    By analyzing the problems which exist currently in the accident hidden dangers management of the coal mine, this paper proposed a new kind of management method-"simulating the market", in which an operation pattern of simulating the market to transact hidden troubles was constructed. This method introduces "Market Mechanism"into safe management, and adopts measurable value to describe the hidden dangers such as" human behavior, technique, environment, equipments etc.". It regards the hidden dangers as "the goods produced by labor" which are found out by the safety managers and the security inspectors, then sells as "commodity". By the process of disposing, counterchecking, re-selling, and redisposing. It forms a set of market-oriented closed-form management pattern of coalmine accident hidden dangers. This kind of management method changes the past traditional methods in which the wageworkers treat safety management passively, but to encourage and restrict them to participate in the check-up and improvement of the hidden dangers.

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

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


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

  16. Improvement of Severe Accident Analysis Computer Code and Development of Accident Management Guidance for Heavy Water Reactor

    Park, Soo Yong; Kim, Ko Ryu; Kim, Dong Ha; Kim, See Darl; Song, Yong Mann; Choi, Young; Jin, Young Ho


    The objective of the project is to develop a generic severe accident management guidance(SAMG) applicable to Korean PHWR and the objective of this 3 year continued phase is to construct a base of the generic SAMG. Another objective is to improve a domestic computer code, ISAAC (Integrated Severe Accident Analysis code for CANDU), which still has many deficiencies to be improved in order to apply for the SAMG development. The scope and contents performed in this Phase-2 are as follows: The characteristics of major design and operation for the domestic Wolsong NPP are analyzed from the severe accident aspects. On the basis, preliminary strategies for SAM of PHWR are selected. The information needed for SAM and the methods to get that information are analyzed. Both the individual strategies applicable for accident mitigation under PHWR severe accident conditions and the technical background for those strategies are developed. A new version of ISAAC 2.0 has been developed after analyzing and modifying the existing models of ISAAC 1.0. The general SAMG applicable for PHWRs confirms severe accident management techniques for emergencies, provides the base technique to develop the plant specific SAMG by utility company and finally contributes to the public safety enhancement as a NPP safety assuring step. The ISAAC code will be used inevitably for the PSA, living PSA, severe accident analysis, SAM program development and operator training in PHWR.

  17. Consideration of Command and Control Performance during Accident Management Process at the Nuclear Power Plant

    Ahmed, Nisrene M. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Kim, Sok Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)


    The accident at the Fukushima Daiichi nuclear power plants shifted the nuclear safety paradigm from risk management to on-site management capability during a severe accident. The kernel of on-site management capability during an accident at a nuclear power plant is situation awareness and agility of command and control. However, little consideration has been given to accident management. After the events of September 11, 2001 and the catastrophic Fukushima nuclear disaster, agility of command and control has emerged as a significant element for effective and efficient accident management, with many studies emphasizing accident management strategies, particularly man-machine interface, which is considered a key role in ensuring nuclear power plant safety during severe accident conditions. This paper proposes a conceptual model for evaluating command and control performance during the accident management process at a nuclear power plant. Communication and information processing while responding to an accident is one of the key issues needed to mitigate the accident. This model will give guidelines for accurate and fast communication response during accident conditions.

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

    Ahn, Kwang Il; Kim, Dong Ha


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

  19. Developement of integrated evaluation system for severe accident management

    Kim, Dong Ha; Kim, H. D.; Park, S. Y.; Kim, K. R.; Park, S. H.; Choi, Y.; Song, Y. M.; Ahn, K. I.; Park, J. H


    The scope of the project includes four activities such as construction of DB, development of data base management tool, development of severe accident analysis code system and FP studies. In the construction of DB, level-1,2 PSA results and plant damage states event trees were mainly used to select the following target initiators based on frequencies: LLOCA, MLOCA, SLOCA, station black out, LOOP, LOFW and SGTR. These scenarios occupy more than 95% of the total frequencies of the core damage sequences at KSNP. In the development of data base management tool, SARD 2.0 was developed under the PC microsoft windows environment using the visual basic 6.0 language. In the development of severe accident analysis code system, MIDAS 1.0 was developed with new features of FORTRAN-90 which makes it possible to allocate the storage dynamically and to use the user-defined data type, leading to an efficient memory treatment and an easy understanding. Also for user's convenience, the input (IEDIT) and output (IPLOT) processors were developed and implemented into the MIDAS code. For the model development of MIDAS concerning the FP behavior, the one dimensional thermophoresis model was developed and it gave much improvement to predict the amount of FP deposited on the SG U-tube. Also the source term analysis methodology was set up and applied to the KSNP and APR1400.

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



    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.)

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

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


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

  2. CATHARE Assessment of PACTEL LOCA Experiments with Accident Management

    Luben Sabotinov


    Full Text Available This paper summarizes the analysis results of three PACTEL experiments, carried out with the advanced thermal-hydraulic system computer CATHARE 2 code as a part of the second work package WP2 (analytical work of the EC project “Improved Accident Management of VVER nuclear power plants” (IMPAM-VVER. The three LOCA experiments, conducted on the Finnish test facility PACTEL (VVER-440 model, represent 7.4% cold leg breaks with combination of secondary bleed and primary bleed and feed and different actuation modes of the passive safety injection. The code was used for both defining and analyzing the experiments, and to assess its capabilities in predicting the associated complex VVER-related phenomena. The code results are in reasonable agreement with the measurements, and the important physical phenomena are well predicted, although still further improvement and validation might be necessary.

  3. Influence diagrams and decision trees for severe accident management

    Goetz, W.W.J.


    A review of relevant methodologies based on Influence Diagrams (IDs), Decision Trees (DTs), and Containment Event Trees (CETs) was conducted to assess the practicality of these methods for the selection of effective strategies for Severe Accident Management (SAM). The review included an evaluation of some software packages for these methods. The emphasis was on possible pitfalls of using IDs and on practical aspects, the latter by performance of a case study that was based on an existing Level 2 Probabilistic Safety Assessment (PSA). The study showed that the use of a combined ID/DT model has advantages over CET models, in particular when conservatisms in the Level 2 PSA have been identified and replaced by fair assessments of the uncertainties involved. It is recommended to use ID/DT models complementary to CET models. (orig.).

  4. A preliminary study for the implementation of general accident management strategies

    Yang, Soo Hyung; Kim, Soo Hyung; Jeong, Young Hoon; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)


    To enhance the safety of nuclear power plants, implementation of accident management has been suggested as one of most important programs. Specially, accident management strategies are suggested as one of key elements considered in development of the accident management program. In this study, generally applicable accident management strategies to domestic nuclear power plants are identified through reviewing several accident management programs for the other countries and considering domestic conditions. Identified strategies are as follows; 1) Injection into the Reactor Coolant System, 2) Depressurize the Reactor Coolant System, 3) Depressurize the Steam Generator, 4) Injection into the Steam Generator, 5) Injection into the Containment, 6) Spray into the Containment, 7) Control Hydrogen in the Containment. In addition, the systems and instrumentation necessary for the implementation of each strategy are also investigated. 11 refs., 3 figs., 3 tabs. (Author)

  5. Development of the Severe Accident Analysis DB for the Severe Accident Management Expert System (I)

    Park, Soo Yong; Ahn, Kwang Il [KAERI, Daejeon (Korea, Republic of)


    This report contains analysis methodologies and calculation results of 5 initiating events of the severe accident analysis database system. The Ulchin 3,4 NPP has been selected as reference plants. Based on the probabilistic safety analysis of the corresponding plant, 54 accident scenarios, which was predicted to have more than 10-10 /ry occurrence frequency, have been analyzed as base cases for the Large loss of Coolant sequence database. The functions of the severe accident analysis database system will be to make a diagnosis of the accident by some input information from the plant symptoms, to search a corresponding scenario, and finally to provide the user phenomenological information based on the pre-analyzed results. The MAAP 4.06 calculation results in this report will be utilized as input data to develop the database system

  6. Chernobyl post-accident management: the ETHOS project.

    Dubreuil, G H; Lochard, J; Girard, P; Guyonnet, J F; Le Cardinal, G; Lepicard, S; Livolsi, P; Monroy, M; Ollagnon, H; Pena-Vega, A; Pupin, V; Rigby, J; Rolevitch, I; Schneider, T


    ETHOS is a pilot research project supported by the radiation protection research program of the European Commission (DG XII). The project provides an alternative approach to the rehabilitation of living conditions in the contaminated territories of the CIS in the post-accident context of Chernobyl. Initiated at the beginning of 1996, this 3-y project is currently being implemented in the Republic of Belarus. The ETHOS project involves an interdisciplinary team of European researchers from the following institutions: the Centre d'etude sur l'Evaluation de la Protection dans le domaine Nucleaire CEPN (radiological protection, economics), the Institute National d'Agronomie de Paris-Grignon INAPG (agronomy, nature & life management), the Compiegne University of Technology (technological and industrial safety, social trust), and the Mutadis Research Group (sociology, social risk management), which is in charge of the scientific co-ordination of the project. The Belarussian partners in the ETHOS project include the Ministry of Emergencies of Belarus as well as the various local authorities involved with the implementation site. The ETHOS project relies on a strong involvement of the local population in the rehabilitation process. Its main goal is to create conditions for the inhabitants of the contaminated territories to reconstruct their overall quality of life. This reconstruction deals with all the day-to-day aspects that have been affected or threatened by the contamination. The project aims at creating a dynamic process whereby acceptable living conditions can be rebuilt. Radiological security is developed in the ETHOS project as part of a general improvement in the quality of life. The approach does not dissociate the social and the technical dimensions of post-accident management. This is so as to avoid radiological risk assessment and management being reduced purely to a problem for scientific experts, from which local people are excluded, and to take into

  7. Comparison of Management Oversight and Risk Tree and Tripod-Beta in Excavation Accident Analysis



    Full Text Available Background Accident investigation programs are a necessary part in identification of risks and management of the business process. Objectives One of the most important features of such programs is the analysis technique for identifying the root causes of accidents in order to prevent their recurrences. Analytical Hierarchy Process (AHP was used to compare management oversight and risk tree (MORT with Tripod-Beta in order to determine the superior technique for analysis of fatal excavation accidents in construction industries. Materials and Methods MORT and Tripod-Beta techniques were used for analyzing two major accidents with three main steps. First, these techniques were applied to find out the causal factors of the accidents. Second, a number of criteria were developed for the comparison of the techniques and third, using AHP, the techniques were prioritized in terms of the criteria for choosing the superior one. Results The Tripod-Beta investigation showed 41 preconditions and 81 latent causes involved in the accidents. Additionally, 27 root causes of accidents were identified by the MORT analysis. Analytical hierarchy process (AHP investigation revealed that MORT had higher priorities only in two criteria than Tripod-Beta. Conclusions Our findings indicate that Tripod-Beta with a total priority of 0.664 is superior to MORT with the total priority of 0.33. It is recommended for future research to compare the available accident analysis techniques based on proper criteria to select the best for accident analysis.

  8. Initial medical management of criticality accident victim; Conduite a tenir aux victimes d'un accident de criticite

    Miele, A.; Bebaron-Jacobs, L


    The extremely severe criticality accidents known to this day, and the subsequent deaths recorded (Sarov 1997 and Tokai Mura 1999), demonstrate the need for sustained surveillance and constant adapted training for the teams in charge of irradiated and/or contaminated victims. The aim of this work group, composed of occupational health services and associated medical biology laboratories, is to present, in leaflet format, the essential data on the documentation and the conduct to be held when facing the victims of a criticality accident. The studies of this work group confirm the difficulties involved in managing this type of accident, both from the dosimetric evaluation point of view and from the therapeutic management point of view. That is why several research themes and perspectives are developed. During the different phases of victim triage, the recommendations given on these leaflets describe the operational conducts to be held. This work will have to be updated according to the evolution in knowledge and means: short and long term effects of exposure to neutrons, multi-competence hospital cooperation, expertise networks related to dosimetric reconstitution. (authors)

  9. Study on virtual redundancy among process parameters for accident management applications

    Ahmed, Rizwan; Pak, Sukyoung; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of); Kim, Jungtaek; Park, Soo Yong; Ahn, Kwangil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    The research at this point can be divided into three streams, focused on the development of self powered sensors and instrumentation, developing intelligent systems that can diagnose and accident type and developing indirect ways that is, methods to assess the safety critical parameters from other statistically related parameters. This first approach is quite expensive, second approach suffers from the limitation that infinite number of accident scenarios cannot be simulated. However, the only way to access the parameters during severe accidents is through simulation codes. Even-though, the process parameters data contain uncertainty, this is the only thing to start with severe accident management. International Nuclear Energy Research Initiative (Inert) project has started research to address various aspects of safety management during severe accidents. As a part of Inert team, we are investigating correlations among process parameters in such a way that safety critical information could be secured by means of other non-safety or virtual parameters during a severe accident. This is known as virtual redundancy of information. This will improve the availability of information in case one channel for information is lost. In this paper, we will discuss methodology, preliminary results and directions for further study. We found that several process parameters exhibit distinct variation pattern for a particular accident and several other parameters can also have the similar trends which strengthens the possibility of having virtual redundancy of information.

  10. Challenge Identification for the Objective Provision Tree Application to the Effectiveness Evaluation for the Accident Management Guidelines

    Yang, Huichang [TUEV Rheinland Korea Ltd., Seoul (Korea, Republic of); Kim, Hanchul; Lee, Sunghan [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)


    As a part of the OPT application for the effectiveness evaluation of the accident management guidelines, challenges which could threaten the safety functions required to maintain the safety, were identified. The identification of detailed provisions in terms of the accident management guidelines is being performed and the visualizing the identified elements of OPT is also under performance. With this logical structure of OPT, the provision of useful tool to evaluate the effectiveness of accident management guideline framework, is expected. The OPT method is a highly logical and top-down approach to identify the vulnerable aspect of the framework which includes the accident management guidelines, such as Emergency Operating Procedures (EOPs), Severe Accident Management Guides (SAMGs) and even Extensive Damage Mitigating Guidelines and FLEX guides. In virtue of this logical tool, the evaluation for the framework of the accident management guidelines was tried in this study.

  11. Causal Factors and Adverse Events of Aviation Accidents and Incidents Related to Integrated Vehicle Health Management

    Reveley, Mary S.; Briggs, Jeffrey L.; Evans, Joni K.; Jones, Sharon M.; Kurtoglu, Tolga; Leone, Karen M.; Sandifer, Carl E.


    Causal factors in aviation accidents and incidents related to system/component failure/malfunction (SCFM) were examined for Federal Aviation Regulation Parts 121 and 135 operations to establish future requirements for the NASA Aviation Safety Program s Integrated Vehicle Health Management (IVHM) Project. Data analyzed includes National Transportation Safety Board (NSTB) accident data (1988 to 2003), Federal Aviation Administration (FAA) incident data (1988 to 2003), and Aviation Safety Reporting System (ASRS) incident data (1993 to 2008). Failure modes and effects analyses were examined to identify possible modes of SCFM. A table of potential adverse conditions was developed to help evaluate IVHM research technologies. Tables present details of specific SCFM for the incidents and accidents. Of the 370 NTSB accidents affected by SCFM, 48 percent involved the engine or fuel system, and 31 percent involved landing gear or hydraulic failure and malfunctions. A total of 35 percent of all SCFM accidents were caused by improper maintenance. Of the 7732 FAA database incidents affected by SCFM, 33 percent involved landing gear or hydraulics, and 33 percent involved the engine and fuel system. The most frequent SCFM found in ASRS were turbine engine, pressurization system, hydraulic main system, flight management system/flight management computer, and engine. Because the IVHM Project does not address maintenance issues, and landing gear and hydraulic systems accidents are usually not fatal, the focus of research should be those SCFMs that occur in the engine/fuel and flight control/structures systems as well as power systems.

  12. Support calculations for management of PRISE leakage accidents

    Matejovic, P.; Vranka, L. [Nuclear Power Plants Research Inst. Vuje, Trnava (Slovakia)


    Accidents involving primary-to-secondary leakage (PRISE) caused by rupture of one or a few tubes are well known design basis events in both, western and VVER NPPs. Operating experience and in-service inspections of VVER-440 units have demonstrated also the potential for large PRISE leaks in the case of the steam generator (SG) primary collector cover lift-up (Rovno NPP). Without performing any countermeasure for limitation of SG collector cover lift-up, a full opening results in PRISE leak with an equivalent diameter 107 mm. Although this accident was not considered in the original design, this event is usually analysed as DBA too. Different means are available for detection and mitigation of PRISE leakage in NPPs currently in operation (J.Bohunice V-1 and V-2) or under construction (Mochovce) in Slovakia. 8 refs.

  13. Management, administrative and operational causes of the accident: Chernobyl nuclear power station

    Anastas, G. [California State Univ., Sacramento, CA (United States)


    The Chernobyl accident, which occurred in April 1986, was the result of management, administrative, operational, technical and design flaws. The accident released millions of curies of mixed fission products including 70-100 PBq of {sup 137}Cs. At the time of the accident, science, engineering and safety in the former Soviet Union were dominated by an atmosphere of politics, group think and `dingoes tending the sheep`. This corrupted safety culture exacerbated the poor design of the reactor. The results of this study strongly suggest that the cultural, political, managerial and operational attributes of the Soviet `system` performed in a synergistic manner to significantly contribute to the initiation of the accident. (authors). 16 refs.

  14. Development of accident management technology and computer codes -A study for nuclear safety improvement-

    Park, Chang Kyu; Jae, Moo Sung; Jo, Young Gyun; Park, Rae Jun; Kim, Jae Hwan; Ha, Jae Ju; Kang, Dae Il; Choi, Sun Young; Kim, Si Hwan [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)


    We have surveyed new technologies and research results for the accident management of nuclear power plants. And, based on the concept of using the existing plant capabilities for accident management, both in-vessel and ex-vessel strategies were identified and analyzed. When assessing accident management strategies, their effectiveness, adverse effects, and their feasibility must be considered. We have developed a framework for assessing the strategies with these factors in mind. We have applied the developed framework to assessing the strategies, including the likelihood that the operator correctly diagnoses the situation and successfully implements the strategies. Finally, the cavity flooding strategy was assessed by applying it to the station blackout sequence, which have been identified as one of the major contributors to risk at the reference plant. The thermohydraulic analyses with sensitivity calculations have been performed using MAAP 4 computer code. (Author).

  15. Communicating worst-case scenarios: neighbors' views of industrial accident management.

    Johnson, Branden B; Chess, Caron


    The prospect of industrial accidents motivated the U.S. Congress to require in the Clean Air Act of 1990 that manufacturing facilities develop Risk Management Plans (RMP) to submit to the U.S. Environmental Protection Agency (USEPA) by July 1999. Industry worried that the requirement to communicate to the public a "worst-case scenario" would arouse unnecessary and counterproductive fears among industry neighbors. We report here the results of focus groups and surveys with such neighbors, focusing particularly upon their reactions to messages about a hypothetical worst-case scenario and management of these risks by industry, government, and other parties. Our findings confirmed our hypotheses that citizens would be skeptical of the competence and trustworthiness of these managers and that this stance would color their views of industrial-facility accident risks. People with job ties to industry or who saw industrial benefits to the community as exceeding its risks had more positive views of industrial risks, but still expressed great concern about the risk and doubt about accident management. Notwithstanding these reactions, overall respondents welcomed this and other related information, which they wanted their local industries to supply. Respondents were not more reassured by additional text describing management of accidents by government and industry. However, respondents did react very positively to the concept of community oversight to review plant safety. Claims about the firm's moral obligation or financial self-interest in preventing accidents were also received positively. Further research on innovative communication and management of accident risks is warranted by these results, even before recent terrorist attacks made this topic more salient.

  16. iROCS: Integrated accident management framework for coping with beyond-design-basis external events

    Kim, Jaewhan; Park, Soo-Yong; Ahn, Kwang-Il, E-mail:; Yang, Joon-Eon


    Highlights: • An integrated mitigating strategy to cope with extreme external events, iROCS, is proposed. • The strategy aims to preserve the integrity of the reactor vessel as well as core cooling. • A case study for an extreme damage state is performed to assess the effectiveness and feasibility of candidate mitigation strategies under an extreme event. - Abstract: The Fukushima Daiichi accident induced by the Great East Japan earthquake and tsunami on March 11, 2011, poses a new challenge to the nuclear society, especially from an accident management viewpoint. This paper presents a new accident management framework called an integrated, RObust Coping Strategy (iROCS) to cope with beyond-design-basis external events (BDBEEs). The iROCS approach is characterized by classification of various plant damage conditions (PDCs) that might be impacted by BDBEEs and corresponding integrated coping strategies for each of PDCs, aiming to maintain and restore core cooling (i.e., to prevent core damage) and to maintain the integrity of the reactor pressure vessel if it is judged that core damage may not be preventable in view of plant conditions. From a case study for an extreme damage condition, it showed that candidate accident management strategies should be evaluated from the viewpoint of effectiveness and feasibility against accident scenarios and extreme damage conditions of the site, especially when employing mobile or portable equipment under BDBEEs within the limited time available to achieve desired goals such as prevention of core damage as well as a reactor vessel failure.

  17. Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident.

    Sugiyama, Daisuke; Hattori, Takatoshi


    In environmental remediation after nuclear accidents, radioactive wastes have to be appropriately managed in existing exposure situations with contamination resulting from the emission of radionuclides by such accidents. In this paper, a framework of radiation protection from radioactive waste management in existing exposure situations for application to the practical and reasonable waste management in contaminated areas, referring to related ICRP recommendations was proposed. In the proposed concept, intermediate reference levels for waste management are adopted gradually according to the progress of the reduction in the existing ambient dose in the environment on the basis of the principles of justification and optimisation by taking into account the practicability of the management of radioactive waste and environmental remediation. It is essential to include the participation of relevant stakeholders living in existing exposure situations in the selection of reference levels for the existing ambient dose and waste management.

  18. Mental health effects from radiological accidents and their social management

    Brenot, J.; Charron, S.; Verger, P. [Institute for Protection and Nuclear Safety, Fontenay-aux-Roses Cedex (France)


    Mental health effects resulting from exposure to radiation have been identified principally in the context of large radiological accidents. They cover an extended scope of manifestations in relation with the notion of stress: increase of some hormones, modifications in mental concentration, symptoms of anxiety and depression, psycho-somatic diseases, deviation behaviours, and, on the long term, a possible post-traumatic stress disorder (PTSD). The main results come from the Three Mile Island, Goiania, and Chernobyl accidents and several modifying factors have been identified. Considering those facts, diverse social responses can be brought to reduce the detriment to affected individuals and communities. Medical treatments are necessary for persons who suffer from pathological diseases. In most cases, a structured public health follow-up is required to establish the seriousness of the health problems, to forecast the extent of medical and psychological assistance, and to inform people who express fears and worries. Social assistance is always valuable under various forms: financial compensations, preferential medical care, and particular advantages concerning working and living conditions. If this social assistance is necessary and helpful, it also induces a loss in personal adjustment capability and initiative capacity. To overcome those negative impacts, some guidelines to authorities' action can be set up. But the best approach, not excluding the previous ones, remains problem solving at the local level through community responsibilization; some instructive examples come from the Chernobyl experience. (author)

  19. [Initial medical management in radiological accidents and nuclear disaster].

    Tanigawa, Koichi


    Major radiological emergencies include criticality in nuclear power plants or terrorist attacks using dirty bombs or nuclear device detonation. Because irradiation itself does not cause any immediate death of the victims, and there is a minimum risk of secondary irradiation to medical personnel during decontamination procedures, lifesaving treatments should be prioritized. When a major radiological accident occurs, information is scarce and/or becomes intricate. We might face with significant difficulties in determining the exact culprits of the event, i.e., radiological or chemical or others. Therefore, it is strongly recommended for the national and local governments, related organizations and hospitals to develop comprehensive systems to cope with all hazards(chemical, biological, radiation, nuclear, and explosion) under the common incident command system.

  20. Fukushima nuclear power plant accident and comprehensive health risk management-global radiocontamination and information disaster.

    Yamashita, Shunichi


    The Great East Japan Earthquake on March 11, 2011, besides further studying the appropriateness of the initial response and post-countermeasures against the severe Fukushima nuclear accident, has now increased the importance of the epidemiological study in comprehensive health risk management and radiation protection; lessons learnt from the Chernobyl accident should be also implemented. Therefore, since May 2011, Fukushima Prefecture has started the "Fukushima Health Management Survey Project" for the purpose of long-term health care administration and early diagnosis/treatment for the prefectural residents. Basic survey is under investigation on a retrospective estimation of external exposure of the first four months. As one of the four detailed surveys, the thyroid ultrasound examination has clarified the increased detection rate of childhood thyroid cancers as a screening effect in the past three years and so thyroid cancer occurrence by Fukushima nuclear power plant accident, especially due to radioactive iodine will be discussed despite of difficult challenge of accurate estimation of low dose and low-dose rate radiation exposures. Through the on-site valuable experience and a difficult challenge for recovery, we should learn the lessons from this severe and large-scale nuclear accident, especially how to countermeasure against public health emergency at the standpoint of health risk and also social risk management.

  1. Regulatory Research of the PWR Severe Accident. Information Needs and Instrumentation for Hydrogen Control and Management

    Park, Gun Chul; Suh, Kune Y.; Lee, Jin Yong; Lee, Seung Dong [Seoul Nat' l Univ., Seoul (Korea, Republic of)


    The current research is concerned with generation of basic engineering data needed in the process of developing hydrogen control guidelines as part of accident management strategies for domestic nuclear power plants and formulating pertinent regulatory requirements. Major focus is placed on identification of information needs and instrumentation methods for hydrogen control and management in the primary system and in the containment, development of decision-making trees for hydrogen management and their quantification, the instrument availability under severe accident conditions, critical review of relevant hydrogen generation model and phenomena In relation to hydrogen behavior, we analyzed the severe accident related hydrogen generation in the UCN 3{center_dot}4 PWR with modified hydrogen generation model. On the basis of the hydrogen mixing experiment and related GASFLOW calculation, the necessity of 3-dimensional analysis of the hydrogen mixing was investigated. We examined the hydrogen control models related to the PAR(Passive Autocatalytic Recombiner) and performed MAAP4 calculation in relation to the decision tree to estimate the capability and the role of the PAR during a severe accident.

  2. Motor vehicle accidents: How should cirrhotic patients be managed?

    Takumi Kawaguchi; Eitaro Taniguchi; Michio Sata


    Motor vehicle accidents (MVAs) are serious social issues worldwide and driver illness is an important cause of MVAs.Minimal hepatic encephalopathy (MHE) is a complex cognitive dysfunction with attention deficit,which frequently occurs in cirrhotic patients independent of severity of liver disease.Although MHE is known as a risk factor for MVAs,the impact of diagnosis and treatment of MHE on MVA-related societal costs is largely unknown.Recently,Bajaj et al demonstrated valuable findings that the diagnosis of MHE by rapid screening using the inhibitory control test (ICT),and subsequent treatment with lactulose could substantially reduce the societal costs by preventing MVAs,Besides the ICT and lactulose,there are various diagnostic tools and therapeutic strategies for MHE.In this commentary,we discussed a current issue of diagnostic tools for MHE,including neuropsychological tests.We also discussed the advantages of the other therapeutic strategies for MHE,such as intake of a regular breakfast and coffee,and supplementation with zinc and branched chain amino acids,on the MVA-related societal costs.

  3. Developing a Minimum Data Set for an Information Management System to Study Traffic Accidents in Iran

    Mohammadi, Ali; Ahmadi, Maryam; Gharagozlu, Alireza


    Background: Each year, around 1.2 million people die in the road traffic incidents. Reducing traffic accidents requires an exact understanding of the risk factors associated with traffic patterns and behaviors. Properly analyzing these factors calls for a comprehensive system for collecting and processing accident data. Objectives: The aim of this study was to develop a minimum data set (MDS) for an information management system to study traffic accidents in Iran. Materials and Methods: This descriptive, cross-sectional study was performed in 2014. Data were collected from the traffic police, trauma centers, medical emergency centers, and via the internet. The investigated resources for this study were forms, databases, and documents retrieved from the internet. Forms and databases were identical, and one sample of each was evaluated. The related internet-sourced data were evaluated in their entirety. Data were collected using three checklists. In order to arrive at a consensus about the data elements, the decision Delphi technique was applied using questionnaires. The content validity and reliability of the questionnaires were assessed by experts’ opinions and the test-retest method, respectively. Results: An (MDS) of a traffic accident information management system was assigned to three sections: a minimum data set for traffic police with six classes, including 118 data elements; a trauma center with five data classes, including 57 data elements; and a medical emergency center, with 11 classes, including 64 data elements. Conclusions: Planning for the prevention of traffic accidents requires standardized data. As the foundation for crash prevention efforts, existing standard data infrastructures present policymakers and government officials with a great opportunity to strengthen and integrate existing accident information systems to better track road traffic injuries and fatalities. PMID:27247791

  4. Generalities on nuclear accidents and their short-dated and middle-dated management; Generalites sur les accidents nucleaires et leur gestion a court terme et a long terme



    All the nuclear activities present a radiation risk. The radiation exposure of the employees or the public, may occur during normal activity or during an accident. The IRSN realized a document on this radiation risk and the actions of protection. The sanitary and medical aspects of a radiation accident are detailed. The actions of the population protection during an accident and the post accident management are also discussed. (A.L.B.)

  5. Comprehensive Health Risk Management after the Fukushima Nuclear Power Plant Accident.

    Yamashita, S


    Five years have passed since the Great East Japan Earthquake and the subsequent Fukushima Daiichi Nuclear Power Plant accident on 11 March 2011. Countermeasures aimed at human protection during the emergency period, including evacuation, sheltering and control of the food chain were implemented in a timely manner by the Japanese Government. However, there is an apparent need for improvement, especially in the areas of nuclear safety and protection, and also in the management of radiation health risk during and even after the accident. Continuous monitoring and characterisation of the levels of radioactivity in the environment and foods in Fukushima are now essential for obtaining informed consent to the decisions on living in the radio-contaminated areas and also on returning back to the evacuated areas once re-entry is allowed; it is also important to carry out a realistic assessment of the radiation doses on the basis of measurements. Until now, various types of radiation health risk management projects and research have been implemented in Fukushima, among which the Fukushima Health Management Survey is the largest health monitoring project. It includes the Basic Survey for the estimation of external radiation doses received during the first 4 months after the accident and four detailed surveys: thyroid ultrasound examination, comprehensive health check-up, mental health and lifestyle survey, and survey on pregnant women and nursing mothers, with the aim to prospectively take care of the health of all the residents of Fukushima Prefecture for a long time. In particular, among evacuees of the Fukushima Nuclear Power Plant accident, concern about radiation risk is associated with psychological stresses. Here, ongoing health risk management will be reviewed, focusing on the difficult challenge of post-disaster recovery and resilience in Fukushima.

  6. Medical and psychological aspects of crisis management during a nuclear accident

    Drottz-Sjoeberg, B.M.


    Crisis handling in most kinds of disasters is affected by e.g. the information situation, prior experience and preparedness, availability of resources, efficiency of leadership and coordination, and type of disaster. A nuclear accident creates a situation which differs from many `normal` disasters and natural catastrophes, for example with respects to the invisible nature of radiation and radioactive contamination and thus the dependence on access to specific technical equipment and expertise, and to information about the radiation situation. The scope of the accident, and the existing levels of radiation, define subsequent actions; information policies and existing channels of communication lay the foundation for public reactions. The present paper explores some examples of public reactions, and crisis handling of some previous radiation accidents on the basis of two dimensions, i.e. degree of information availability and degree of impact or `environmental damage`. The examples include the radiation accidents in the Chelyabinsk region in the southern Urals, at Three Mile Island, USA, at Chernobyl in the Ukraine, and in Goiania, Brazil. It is concluded that public reactions differ as a function of existing expectations, and the crisis handling is more affected by the existing organizational and social structures than by needs and reactions of potential victims. Another conclusion is that pre-disaster preparedness regarding public information, and organization of countermeasures, are crucial to the outcome of a successful crisis handling and for enhancing public trust in crisis management. 39 refs, 2 figs.

  7. Combining Neural Methods and Knowledge-Based Methods in Accident Management

    Miki Sirola


    Full Text Available Accident management became a popular research issue in the early 1990s. Computerized decision support was studied from many points of view. Early fault detection and information visualization are important key issues in accident management also today. In this paper we make a brief review on this research history mostly from the last two decades including the severe accident management. The author’s studies are reflected to the state of the art. The self-organizing map method is combined with other more or less traditional methods. Neural methods used together with knowledge-based methods constitute a methodological base for the presented decision support prototypes. Two application examples with modern decision support visualizations are introduced more in detail. A case example of detecting a pressure drift on the boiling water reactor by multivariate methods including innovative visualizations is studied in detail. Promising results in early fault detection are achieved. The operators are provided by added information value to be able to detect anomalies in an early stage already. We provide the plant staff with a methodological tool set, which can be combined in various ways depending on the special needs in each case.

  8. Discussion on Attempted Accidents Management "%关于做好未遂事件管理的探讨



    The definition of attempted accident is explained, the problems in attempted accidents management are analyzed, and the advices for attempted accidents management are proposed as well.%在阐释了未遂事件定义、做好未遂事件管理的基础上,分析了开展未遂事故管理中遇到的问题,从转变发展方式,提升RSE管理水平的高度,就如何做好未遂事件管理进行了探讨,提出了建议。

  9. Identification and initial assessment of candidate BWR late-phase in-vessel accident management strategies

    Hodge, S.A.


    Work sponsored by the United States Nuclear Regulatory Commission (USNRC) to identify and perform preliminary assessments of candidate BWR (boiling water reactor) in-vessel accident management strategies was completed at Oak Ridge National Laboratory (ORNL) during fiscal year 1990. Mitigative strategies for containment events have been the subject of a companion study at Brookhaven National Laboratory. The focus of this Oak Ridge effort was the development of new strategies for mitigation of the late phase events, that is, the events that would occur in-vessel after the onset of significant core damage. The work began with an investigation of the current status of BWR in-vessel accident management procedures and proceeded through a preliminary evaluation of several candidate new strategies. The steps leading to the identification of the candidate strategies are described. The four new candidate late-phase (in-vessel) accident mitigation strategies identified by this study and discussed in the report are: (1) keep the reactor vessel depressurized; (2) restore injection in a controlled manner; (3) inject boron if control blade damage has occurred; and (4) containment flooding to maintain core and structural debris in-vessel. Additional assessments of these strategies are proposed.

  10. Accident Management & Risk-Based Compliance With 40 CFR 68 for Chemical Process Facilities

    O`Kula, K.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Taylor, R.P. Jr.; Ashbaugh, S.G. [Innovative Technology Solutions, Albuquerque, NM (United States)


    A risk-based logic model is suggested as an appropriate basis for better predicting accident progression and ensuing source terms to the environment from process upset conditions in complex chemical process facilities. Under emergency conditions, decision-makers may use the Accident Progression Event Tree approach to identify the best countermeasure for minimizing deleterious consequences to receptor groups before the atmospheric release has initiated. It is concluded that the chemical process industry may use this methodology as a supplemental information provider to better comply with the Environmental Protection Agency`s proposed 40 CFR 68 Risk Management Program rule. An illustration using a benzene-nitric acid potential interaction demonstrates the value of the logic process. The identification of worst-case releases and planning for emergency response are improved through these methods, at minimum. It also provides a systematic basis for prioritizing facility modifications to correct vulnerabilities.

  11. Safety culture and accident analysis--a socio-management approach based on organizational safety social capital.

    Rao, Suman


    One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, the key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization--seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly.

  12. Evaluating the Effectiveness of Alternate Entry Condition into the Severe Accident Management Guidance

    Yoon, Hyung Seok; Lee, Su Won [FNC Technology Co. Ltd., Yongin (Korea, Republic of); Min, Shin Jung [Korea Hydro and Nuclear Power Co. Ltd. Central Research Institute, Daejeon (Korea, Republic of)


    In this study, the effectiveness of the CA as an alternate means is evaluated quantitatively by utilizing the Modular Accident Analysis Program (MAAP) 5 computer code including the MAAP5-DOSE module, which can analyze the radiation level inside the containment. The effectiveness of the CA has been investigated by utilizing the MAAP5 code including the MAAP5- DOSE. The onset of core damage is considered to be a core (fuel rod cladding) condition at the time when the core exit temperature reaches the value prescribed for transition to Severe Accident Management Guidance (SAMG), which is 1200 .deg. F. However, during a shutdown state, the core exit thermocouples measurements are unavailable after lifting reactor vessel head. Thus, an alternate means to detect the onset of core damage is necessary to cover all plant operating states. In order for that, a Computational Aid (CA), 'Radiation Level as a Functional of Time after Shutdown,' has been developed. The upper containment radiation instrumentation is a gross gamma monitor, and has a reliable instrumentation range during severe accidents. It can be used for detecting onset of core damage. Thus, the radiation level can be used as alternative means of the entry condition into the SAMG. It has been shown that the SAMG entry timings determined by using the core exit thermocouple measurements and by the radiation monitoring with the CA would not be differentiated. The time difference estimates entering SAMG would be less 15 min which would not influence the operator action significantly.

  13. Workshop proceedings of ISAMM 2009: Implementation of severe accident management measures

    Guentay, S. (ed.) [Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department, Laboratory for Thermal Hydraulics, ViIligen (Switzerland)


    This comprehensive report published by the Paul Scherrer Institute (PSI) in Switzerland reports on a conference and workshop held in Switzerland in October 2009 dealing with Severe Accidents Management (SAM) in nuclear power stations. The workshop provided an update on the status of severe accident management measures and their implications since the OECD/CSNI workshop held in 2001 at the PSI in Switzerland. Since the 2001 workshop, additional work has been performed to integrate emergency procedures and SAM measures into risk assessments in order to better reflect operator responses to recover a plant from a damaged state. The major focus of the workshop was to address SAM measures for both operational plants and new plant designs. Also, the integration of SAM measures into contemporary/future probabilistic risk assessments was discussed. 41 papers were presented in 8 sessions. The papers addressed the following areas: 1) Current status and insights of SAM (2 sessions); 2) Probabilistic Safety Assessment (PSA) modelling issues; 3) code analysis for supporting Serious Accident Management Guidance (SAMG, 2 sessions); 4) decision making, tools, training, risk-targets and entrance to SAM; 5) design modifications for implementation of SAM; 6) physical phenomena. The last part of the workshop was devoted to the presentation of the most striking highlights of the papers in the above areas, followed by two panellists giving presentations on human and organisational aspects of SAM, their importance in relation to technical issues and the effectiveness of current SAMG implementation. The question of how consequence analyses can be used to improve the effectiveness of SAM is discussed. The contributions were presented by representatives from Austria, Germany, Japan, France, the USA, Korea, Switzerland, Finland, Hungary, Belgium, Canada, Sweden, the Czech republic, the United kingdom, the Netherlands, Spain, Slovenia and Russia. The authors state that the overall picture

  14. Optimization of the Severe Accident Management Strategy for Domestic Plants and Validation Experiments

    Kim, S. B.; Kim, H. D.; Koo, K. M.; Park, R. J.; Hong, S. H.; Cho, Y. R.; Kim, J. T.; Ha, K. S.; Kang, K. H


    nuclear power plants, a technical basis report and computational aid tools were developed in parallel with the experimental and analytical works for the resolution of the uncertain safety issues. ELIAS experiments were carried out to quantify the boiling heat removal rate at the upper surface of a metallic layer for precise evaluations on the effect of a late in-vessel coolant injection. T-HERMES experiments were performed to examine the two-phase natural circulation phenomena through the gap between the reactor vessel and the insulator in the APR1400. Detailed analyses on the hydrogen control in the APR1400 containment were performed focused on the effect of spray system actuation on the hydrogen burning and the evaluation of the hydrogen behavior in the IRWST. To develop the technical basis report for the severe accident management, analyses using SCDAP/RELAP5 code were performed for the accident sequences of the OPR1000. Based on the experimental and analytical results performed in this study, the computational aids for the evaluations of hydrogen flammability in the containment, criteria of the in-vessel corium cooling, criteria of the external reactor vessel cooling were developed. An ASSA code was developed to validate the signal from the instrumentations during the severe accidents and to process the abnormal signal. Since ASSA can perform the signal processing from the direct input of the nuclear power plant during the severe accident, it can be platform of the computational aids. In this study, the ASSA was linked with the computaional aids for the hydrogen flammability.

  15. Management of a severe accident on a pressurised water reactor in France; La gestion d'un accident grave sur un reacteur a eau sous pression en France



    This brief document defines what a severe accident is on a nuclear reactor, indicates the different failure modes which have been defined (vapour explosion in the reactor vessel, hydrogen explosion, and so on). It describes the management of a core fusion accident for pressurized water reactors, for which a guide has been designed, the GIAG (intervention guide for a severe accident situation). The principles of such an intervention are described, and then the approach for an EPR reactor

  16. Decision support system for emergency management of oil spill accidents in the Mediterranean Sea

    Liubartseva, Svitlana; Coppini, Giovanni; Pinardi, Nadia; De Dominicis, Michela; Lecci, Rita; Turrisi, Giuseppe; Cretì, Sergio; Martinelli, Sara; Agostini, Paola; Marra, Palmalisa; Palermo, Francesco


    This paper presents an innovative web-based decision support system to facilitate emergency management in the case of oil spill accidents, called WITOIL (Where Is The Oil). The system can be applied to create a forecast of oil spill events, evaluate uncertainty of the predictions, and calculate hazards based on historical meteo-oceanographic datasets. To compute the oil transport and transformation, WITOIL uses the MEDSLIK-II oil spill model forced by operational meteo-oceanographic services. Results of the modeling are visualized through Google Maps. A special application for Android is designed to provide mobile access for competent authorities, technical and scientific institutions, and citizens.


    Farfan, E.; Jannik, T.


    Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures

  18. Regulatory research of the PWR severe accident information needs and instrumentation availability for hydrogen control and management

    Park, Jae-Hong; Park, Gun-Chul; Suh, Kune Y.; Kang, Yun-Moon; Lee, Un-Jang; Oh, Se-Chul; Lee, Jin-Yong [Seoul Nationl Univ., Seoul (Korea, Republic of)


    During the current research period, we have set forth the methodology for identification of a severe accident, developed a framework for hydrogen management decision trees, and analyzed the literature on hydrogen management and experimental data for hydrogen bum. Specifically, we have summarized me results for information needs in a severe accident obtained in the U.S. and other countries, and applied the methodology to the reference plant YGN 3 and 4 as part of severe accident management. We have also examined the existing instruments in terms of their availability and survivability during a severe accident, and identified additionally needed information needs and instruments. We have identified dominant accident sequences for me reference plant YGN 3 and 4 to construct decision trees, and extracted available data from the IPE study of the plant. Based upon the data we have performed preliminary study on the decision tree and decision node. Last, we have examined various mechanisms for hydrogen generation and reIevant experimental data to predict me amount of hydrogen generation and governing factors in me process. We have also reviewed the hydrogen generation related models in the severe accident analysis.

  19. 我国事故管理研究现状%Research review on unexpected accident management in China

    王臣; 高俊山


    对我国近15年来事故管理领域的研究进行了评述.信息统计和个案研究是事故管理的基础,案例库建设对未来事故的评估预防有借鉴作用.行业安全体系建设在国内越来越受到重视.重大安全事故的预测、评估、处理的理论发展和应用实践水平迅速提高.事故的定量安全评估、事故预防、更加实用的应急救援和疏散方法等是研究的热点.%The present paper intends to make a detailed review on unexpected accident management in China in recent years. As is known, China, a country pursuing its peaceful rising, is now staying at a stage of vigorous social transition and in turn comes along with lots of unexpected accidents in production, transportation, and all other fields, which makes it imperative to improve the accident management in the country. Funded by the National Science and Technology Infrastructure Project, this paper would like to offer a comprehensive review over the accidents that took place with a detailed analysis based on s general survey and statistics in this way in the past 15 years. In doing so, first of all, we have noticed that the governments and departments concerned have been paying more and more close attention to the improvement of the industrial production safety systems and facilities all over the country. Statistical analysis of the information and data of the conspicuous safety and security accidents by a few production safety accident research institutions can serve as an available database for our study of the geographical distributions and pursue of the fuzzy inference regularities of such accidents. The samples we quote here for the successful handling of such accidents in the past decades should have played an important role in the decision-making process of a new emergent accident. And some of them have been developed into backbone units in the field of environmental protection. For detailed study of such safety accidents, the safety and

  20. The Design of PSB-VVER Experiments Relevant to Accident Management

    Nevo, Alessandro Del; D'Auria, Francesco; Mazzini, Marino; Bykov, Michael; Elkin, Ilya V.; Suslov, Alexander

    Experimental programs carried-out in integral test facilities are relevant for validating the best estimate thermal-hydraulic codes(1), which are used for accident analyses, design of accident management procedures, licensing of nuclear power plants, etc. The validation process, in fact, is based on well designed experiments. It consists in the comparison of the measured and calculated parameters and the determination whether a computer code has an adequate capability in predicting the major phenomena expected to occur in the course of transient and/or accidents. University of Pisa was responsible of the numerical design of the 12 experiments executed in PSB-VVER facility (2), operated at Electrogorsk Research and Engineering Center (Russia), in the framework of the TACIS 2.03/97 Contract 3.03.03 Part A, EC financed (3). The paper describes the methodology adopted at University of Pisa, starting form the scenarios foreseen in the final test matrix until the execution of the experiments. This process considers three key topics: a) the scaling issue and the simulation, with unavoidable distortions, of the expected performance of the reference nuclear power plants; b) the code assessment process involving the identification of phenomena challenging the code models; c) the features of the concerned integral test facility (scaling limitations, control logics, data acquisition system, instrumentation, etc.). The activities performed in this respect are discussed, and emphasis is also given to the relevance of the thermal losses to the environment. This issue affects particularly the small scaled facilities and has relevance on the scaling approach related to the power and volume of the facility.

  1. Safety culture and accident analysis-A socio-management approach based on organizational safety social capital

    Rao, Suman [Risk Analyst (India)]. E-mail:


    One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, Key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization-seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly.

  2. An Examination of Commercial Aviation Accidents and Incidents Related to Integrated Vehicle Health Management

    Reveley, Mary S.; Briggs, Jeffrey L.; Thomas, Megan A.; Evans, Joni K.; Jones, Sharon M.


    The Integrated Vehicle Health Management (IVHM) Project is one of the four projects within the National Aeronautics and Space Administration's (NASA) Aviation Safety Program (AvSafe). The IVHM Project conducts research to develop validated tools and technologies for automated detection, diagnosis, and prognosis that enable mitigation of adverse events during flight. Adverse events include those that arise from system, subsystem, or component failure, faults, and malfunctions due to damage, degradation, or environmental hazards that occur during flight. Determining the causal factors and adverse events related to IVHM technologies will help in the formulation of research requirements and establish a list of example adverse conditions against which IVHM technologies can be evaluated. This paper documents the results of an examination of the most recent statistical/prognostic accident and incident data that is available from the Aviation Safety Information Analysis and Sharing (ASIAS) System to determine the causal factors of system/component failures and/or malfunctions in U.S. commercial aviation accidents and incidents.

  3. Main post-accident management stakes: IRSN's point of view

    Andre Oudiz [Institut de Radioprotection et de Surete Nucleaire (France)


    Full text of publication follows: Off site management of a radiological crisis covers two phases which need to be clearly distinguished even if there are links between them: emergency phase and recovery phase (also called late or post-accident phase). The presentation will deal with the latter, rather neglected up until recently, but conveying special attention from now on in France and at the international level. It is clear now that the long term management of a radiological or nuclear crisis cannot be reduced to merely site decontamination. Actually, environmental decontamination considerations would be only one amongst other essential economical, social, health, psychological, cultural, and symbolical concerns. This is why off site management of a radiological crisis requires innovative governance, in order to challenge such a complexity. This need for challenge led IRSN to have on the go technical developments and new governance modes reflection. 1) Technical developments: they deal with implementing an organisation, a set of methods, a platform of technical tools which would allow the stakeholders to carry out efficiently their mission during the recovery phase. For example, countermeasures for agricultural and urban rehabilitation are developed within the framework of the 6. PCRDT EURANOS programme. Teams from several countries are involved in common elaboration of rehabilitation strategies based on the best available knowledge. Besides this, simple operational decision aiding tools for the stakeholders (local administration, elected representatives, professional agricultural groups, etc.) are currently developed by IRSN within the framework of the nuclear post-accident exercises. IRSN is also involved in doctrinal reflections about the respective roles of radioactive measurements in the environment and radiological consequences calculation during emergency and recovery phases. Criteria for emergency countermeasures withdrawal are also currently under

  4. Do accident and emergency senior house officers know the British guidelines on the management of acute asthma?

    Ulahannan, T; Hardern, R D; Hamer, D W


    Avoidable deaths from asthma continue, even in hospital. Since the management of acute severe asthma is often initiated in the Accident and Emergency department, it is crucial that staff there have adequate knowledge. An anonymous questionnaire, containing items based on chart 6 of the UK guidelines, was completed by 66 Accident and Emergency Senior House Officers from the Yorkshire region. The study aim was to establish these doctors' levels of knowledge about the recommended management of acute asthma in Accident and Emergency. The median score was 10 (out of a possible 24) and the interquartile range 8-13. Further efforts are required to implement these guidelines so that the best patient outcomes can be achieved.

  5. With safety more safe. An intelligent data management reduces the risk of accidents and supports the accident management; Mit Sicherheit sicherer. Intelligentes Datenmanagement minimiert das Stoerfallrisiko und unterstuetzt das Stoerfallmanagement

    Wegg, Dirk [Siemens Industry Software GmbH and Co KG, Essen (Germany)


    It was not always possible to avoid accidents in industrial plants. Unfortunately, there will be no absolute security. Newest technologies, innovative solutions and effective safety concepts allow a significant reduction of the risk especially for critical applications. An intelligent data management system is an important tool for this reduction of risk.

  6. Complication of improper management of sodium hypochlorite accident during root canal treatment.

    Faras, Fatemah; Abo-Alhassan, Fawaz; Sadeq, Abdullah; Burezq, Hisham


    Sodium Hypochlorite (NaOCl) is a common irrigation solution used in root canal treatment. It has strong antibacterial and tissue dissolving properties. Nevertheless, it has some serious complications, some of which are life-threatening. A young male presented with severe chemical burn of the right infraorbital area and partial necrosis of the hard palate resulting from extrusion of NaOCl during root canal treatment of the upper right 2(nd) molar tooth. The patient had a facial scar, and mucosal damage healed nearly completely. Several precautions must be taken during NaOCl use to prevent the spread of the solution into surrounding tissues. Early recognition of NaOCl accident and proper immediate management are important to achieve the best possible outcome.

  7. Information and communication technologies, a tool for risk prevention and accident management on sea ice

    Elise Lépy


    Full Text Available Marine ice melting topic is a repetitive phenomenon in alarmist speeches on climate change. The present positive evolution of air temperatures has in all probability many impacts on the environment and more or less directly on societies. Face to the temperature elevation, the ice pack is undergone to an important temporal variability of ice growth and melting. Human populations can be exposed to meteorological and ice hazards engendering a societal risk. The purpose of this paper is to better understand how ICT get integrated into the risk question through the example of the Bay of Bothnia in the northern extremity of the Baltic Sea. The study deals with the way that Finnish society, advanced in the ICT field, faces to new technology use in risk prevention and accident management on sea ice.

  8. Development of a taxonomy of performance influencing factors for human reliability assessment of accident management tasks and its application

    Kim, Jae Whan; Jung, Won Dae; Kang, Dae Il; Ha, Jae Joo


    In this study, a new PIF taxonomy for HRA of the tasks during emergency operation and accident management situations. We collected the existing PIF taxonomies as many as possible. Then, we analyzed the trend in the selection of PIFs, the frequency of use between PIFs in HRA methods, and the level of definition of PIFs, in order to reflect these characteristics into the development of a new PIF taxonomy. Next, we analyzed the principal task context during accident management to draw the context specific PIFs. Afterwards, we established several criteria for the selection of the appropriate PIFs for HRA under emergency operation and accident management situations. Finally, the final PIF taxonomy containing the subitems for assessing each PIF was constructed based on the results of the previous steps and the selection criteria. The final result ofthis study is the new PIF taxonomy for HRA of the tasks during emergency operation and accident management situations. The selected 11 PIFs in the study are as follows: training and experience, availability and quality of information, status and trend of critical parameters, status of safety system/component, time pressure, working environment features, team cooperation and communication, plant policy and safety culture. (author). 35 refs., 23 tabs.

  9. Quality assurance in military medical research and medical radiation accident management.

    Hotz, Mark E; Meineke, Viktor


    The provision of quality radiation-related medical diagnostic and therapeutic treatments cannot occur without the presence of robust quality assurance and standardization programs. Medical laboratory services are essential in patient treatment and must be able to meet the needs of all patients and the clinical personnel responsible for the medical care of these patients. Clinical personnel involved in patient care must embody the quality assurance process in daily work to ensure program sustainability. In conformance with the German Federal Government's concept for modern departmental research, the international standard ISO 9001, one of the relevant standards of the International Organization for Standardization (ISO), is applied in quality assurance in military medical research. By its holistic approach, this internationally accepted standard provides an excellent basis for establishing a modern quality management system in line with international standards. Furthermore, this standard can serve as a sound basis for the further development of an already established quality management system when additional standards shall apply, as for instance in reference laboratories or medical laboratories. Besides quality assurance, a military medical facility must manage additional risk events in the context of early recognition/detection of health risks of military personnel on deployment in order to be able to take appropriate preventive and protective measures; for instance, with medical radiation accident management. The international standard ISO 31000:2009 can serve as a guideline for establishing risk management. Clear organizational structures and defined work processes are required when individual laboratory units seek accreditation according to specific laboratory standards. Furthermore, international efforts to develop health laboratory standards must be reinforced that support sustainable quality assurance, as in the exchange and comparison of test results within

  10. Radiation management during restoration works after fire and explosion accident of Asphalt Solidification Facility (ASP)

    Miyabe, Kenjiro; Ninomiya, Kazushige; Imakuma, Yoshikazu (and others)


    A fire broke out at 10:06 a.m. March 11 in 1997 in asphalt filling up room of Asphalt Solidification Processing Facility (ASP) in Japan Nuclear Cycle Development Institute (JNC), and an explosion occurred at 8:04 p.m. on the same day. A large number of installations and equipment in the facility were damaged by the accident. As the containment function of the facility were lost, radioactive materials were released to outside of the facility. Thirty seven workers (thirty four workers inside the ASP building at fire, and three workers near the ASP at explosion) suffered internal exposures. Effective dose equivalent for each worker which was estimated based on the intake of radioactive materials, was below the record level for internal exposure management (2msv). Restoration works of the ASP including repairs of broken windows, shutters, doors, ventilation exhaust systems, radiation control and management equipment, and decontamination, were completed on July 31 in 1998. The radiation management during the restoration are described in this report. (Suetake, M.)

  11. Radioactive waste management in the Chernobyl exclusion zone: 25 years since the Chernobyl nuclear power plant accident.

    Oskolkov, Boris Y; Bondarkov, Mikhail D; Zinkevich, Lubov I; Proskura, Nikolai I; Farfán, Eduardo B; Jannik, G Timothy


    Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities in the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste-related problems in Ukraine and the Chernobyl Exclusion Zone and, in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program.

  12. Tenth Warren K. Sinclair keynote address-the Fukushima nuclear power plant accident and comprehensive health risk management.

    Yamashita, Shunichi


    Just two years have passed since the Tokyo Electric Power Company-Fukushima Daiichi Nuclear Power Plant (NPP) accident, a multidimensional disaster that combined to destroy the local infrastructure on which the safety system depended and gave a serious impact to the world. Countermeasures including evacuation, sheltering, and control of the food chain were implemented in a timely manner by the Japanese government. However, there is a clear need for improvement, especially in the areas of nuclear safety and protection and also in the management of the radiation health risk during and even after the accident. To date there have been no acute radiation injuries. The radiation-related physical health consequences to the general public, including evacuees, are likely to be much lower than those arising from the Chernobyl nuclear reactor accident, because the radiation fallout and the subsequent environmental contamination were much more limited. However, the social, psychological, and economic impacts of the Fukushima NPP accident are expected to be considerable. Currently, continued monitoring and characterization of the levels of radioactivity in the environment and foods in Fukushima are vital for obtaining informed consent to the decisions on living in the areas already radiocontaminated and returning back to the evacuated areas once re-entry is permitted; it is also important to perform a realistic assessment of the radiation doses on the basis of measurements. We are currently implementing the official plans of the Fukushima Health Management Survey, which includes a basic survey for the estimation of the external doses that were received during the first 4 mo after the accident and four more detailed surveys (thyroid ultrasound examination, comprehensive health check-up, mental health and life-style survey, and survey of pregnant women and nursing mothers), with the aim to take care of the health of all of the residents of the Fukushima Prefecture for a long time

  13. 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


    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.

  14. Decision-making guide for management of agriculture in the case of a nuclear accident; Guide d'aide a la decision pour la gestion du milieu agricole en cas d'accident nucleaire

    Reales, N. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Fourrie, L. [Association De Coordination Technique Agricole, 75 - Paris (France); Quinio, C.; Grastilleur, Ch. [Ministere de l' Agriculture et de la Peche, 75 - Paris (France). Direction Generale de l' Alimentation


    For several years, agricultural and nuclear professionals in France have been working on how to manage the agricultural situation in the event of a nuclear accident. This work resulted in measures at both the national (Aube nuclear safety exercises in 2003, INEX3 in 2005) and international levels (EURATOM Programmes). Following on from the European FARMING (FP5) and EURANOS (FP6) works, ACTA', IRSN and six agricultural technical institutes which are specialized in agricultural production and processing network (arable crop [especially cereals, maize, pulses, potatoes and forage crops], fruits and vegetables, vine and wine, livestock farming [cattle, sheep, goats, pigs, poultry]), created a resource adapted to the French context: the Decision-aiding Tool for the Management of Agriculture in case of a Nuclear Accident. Devised for the Ministry of Agriculture services supporting state officials in a radiation emergency, this manual focuses on the early phase following the accident when the state of emergency would make discussion on countermeasures with a large stakeholder panel impossible. Supported by the Ministry of Agriculture and Fisheries and the French Nuclear Safety Authority, this project increased knowledge of post-accident management strategies and made an important contribution to the national think tank set up within the framework of the French Steering Committee for managing the post-event phase of a nuclear accident (CODIRPA). This article describes how the manual evolved throughout the project and the development of new resources. (authors)

  15. A local perspective to asthma management in the accident and emergency department in Malta

    Caroline Gouder


    Full Text Available Aim: This study was performed to assess the management of adult patients presenting to the Mater Dei Hospital Accident and Emergency (A&E department with acute asthma. Subjects and Methods: Asthmatic patients age 14 or older who presented to A&E department between January and October 2010 with asthma exacerbations were included. Data were collected from the clinical notes and analyzed. Results: A total of 244 patients (67.2% females were included, 126 (51.6% were admitted, 97 (39.8% discharged and 21 (8.6% discharged themselves against medical advice. There was a decline in the presentations between January and July, followed by an upward trend until October (P = 0.42. Pulse oximetry was performed in 207 patients (84.8%, arterial blood gases in 133 (54.5%, peak expiratory flow rate in 106 (43.4% and chest radiography in 206 (84.4% patients. The respiratory rate was documented in 151 (61.8%, heart rate in 204 (83.6% and ability to complete sentences in 123 (50.4% patients. One hundred and ninety six patients (80.3% were given nebulized bronchodilators, 103 (42.2% intravenous corticosteroids, 7 (2.87% oral corticosteroids, 109 (44.7% oxygen, 28 (11.5% antibiotics and 9 (3.69% magnesium. Systemic corticosteroids and antibiotics were more commonly prescribed to patients admitted (P < 0.001. Conclusion: Management of acute asthma in Malta requires optimization in order to compare with international guidelines.

  16. General radiation management situation at the first stage of accident occurrence. Fire and explosion of asphalt solidification processing facility

    Noda, Kimio; Shimizu, Takehiko; Ishiguro, Shuji [Health and Safety Division, Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan)


    Fire accident in the cell of Asphalt Solidification Processing Facility (ASP) in PNC took placed at 10:06 a.m., March 11, 1997. Explosion accident occurred subsequently in the ASP at 8:04 p.m. of the day about 10 hours later. The accident which included loss of confinement function of the cell, release of radioactive materials to the working environment, evacuation of many workers, radioactive materials intake of the workers, alarm of many radiation monitoring system, diffusion of radiation materials to off-site, required the radiation management division to take a prompt and wide-ranging protective action. No one was inflicted an external injury by the accident. The workers who inhaled a few radioactive materials, such as Cs-137, were 37 in number. The maximum committed effective dose equivalent or a person was estimated 0.4-1.6 mSv, taking account of the effects of alpha-ray emission nuclides. Radioactive materials were released outside through the raptured windows of the facility. Radioactive nuclides, such as Cs, Sr, Pu, and Am were detected in site by the environmental monitoring. A small quantity of Cs was detected in the aerosols of Oarai area, where is located at about 20 km south-south-west distant from the accidental site. The total amount of effluent throughout the accident was estimated about 1-4 GBq for {beta}-ray emission nuclides, excluding C-14, and about 1x10{sup -4}-4 x 10{sup -3} GBq for {alpha}-ray emission nuclides. The maximum committed effective dose equivalent for the general public was estimated about 1x10{sup -3}-2 x 10{sup -2} mSv. (M. Suetake)

  17. Discussion about Accident Management Methods of Power Supply Enterprises%供电企业事故管理方法探讨



    本文对供电企业事故管理方法进行了探讨,提出了包括事故报告、督导、调查、整改、统计分析与预警、信息沟通与回顾、检查与考核在内的七项事故管理内容,明确了事故的管理程序。%Accident management methods management aspects are put forward in statistical analysis and early warning, evaluation of accidents, with management of power supply enterprises are discussed and 7 accident terms of reports, supervision, investigation, rectification, information communication and review, inspection and procedures of accidents defined.

  18. Radiation management at the occurrence of accident and restoration works. Fire and explosion of asphalt solidification processing facility

    Miyabe, Kenjiro; Jin, K.; Namiki, A.; Mizutani, K.; Horiuchi, N.; Saruta, J. [Power Reactor and Nuclear Fuel Development Corp., Health and Safety Division, Tokai, Ibaraki (Japan); Ninomiya, Kazushige [Power Reactor and Nuclear Fuel Development Corp., Tsuruga, Fukui (Japan). Monju Construction Office


    Fire and explosion accident in the cell of Asphalt Solidification Processing Facility(ASP) in PNC took placed at March 11 in 1997. Following to the alarm of many radiation monitoring system in the facility, some of workers inhale radioactive materials in their bodies. Indication values of an exhaust monitor installed in the first auxiliary exhaust stack increased suddenly. A large number of windows, doors, and shutters in the facility were raptured by the explosion. A lot of radioactive materials blew up and were released to the outside of the facility. Reinforcement of radiation surveillance function, nose smearing test for the workers and confirmation of contamination situation were implemented on the fire. Investigation of radiation situation, radiation management on the site, exposure management for the workers, surveillance of exhaustion, and restoration works of the damaged radiation management monitoring system were carried out after the explosion. The detailed data of radiation management measures taken during three months after the accident are described in the paper. (M. Suetake)

  19. Simulation technology for training in the management of severe accidents in nuclear power; Tecnologia de simulacion para entrenamiento en gestion de accidentes severos en centrales nucleares

    Gil Moya, E.; Ruiz Martin, J. A.


    The objective of the project consists of the development of a module of severe accident based on the code Thermo-hydraulic MAAP and their integration in a Spanish CN training Simulator. Currently, stimulated the tools designed by Tecnatom aimed at training and assistance in the management of emergencies, complemented by the development of a dynamic interactive guides of severe accidents, thus constituting a set of aid for the operation.

  20. Guide update Severe Accident Management (SAMG) of CN. Almaraz post Fukushima; Actualizacion de las Guias de Gestion de Accidente Severo (GGAS) de CN. Almaraz post Fukushima

    Martinez Fanegas, R.; Aguado Miquel, F.; Tanarro Onrubia, A.; Uruburu Rodriguez, A.


    The work is part of the activities carried out by CN. Almaraz in applying lessons learned from the Fukushima accident. The achievement of this objective requires a substantial change in the Guidelines Severe Accident Management (SAMG), starting with the adaptation of the Revision 2 of the Generic Guidelines (SAMG) Owners Group (PWROG, January 2013), which is the work is the fundamental part of this paper. (Author)

  1. 福岛第一核电厂严重事故管理研究%Research on severe accident management in Fukushima Daiichi Nuclear Power Plant

    刘凯; 王炜


    The accident of Fukushima Nuclear Power Plant led to a severe accident of core meltdown, and its process of emergency management exposed various defects which raised great concern about severe accident management in nuclear power plants. In this paper, the specifications of severe accident management that issued by IAEA and Japan were overviewed. Based on Japan specifications, the analysis of sequences and management strategies were presented on severe accident in Fukushima Daiichi Nuclear Power Plant. Following identification of defects on severe accident management, possible corrective measures for current and future plants were discussed. Finally , an approach and a frame model for severe accident management were presented, which may improve nuclear safety in current and future plants.%日本福岛核事故造成了堆芯熔毁的严重事故,应急处置过程暴露出严重事故管理的种种不足,引起对核电厂严重事故管理的关注.简述了国际原子能机构和日本关于核电厂严重事故管理的规范要求,分析了福岛第一核电厂事故序列和严重事故管理策略,讨论了严重事故管理存在的问题及其可能的改进措施,最后提出了改进核电厂严重事故管理的框架模型和方法.

  2. Emergency Management and Radiation Moni-toring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

    Lahtinen, J. [Radiation and Nuclear Safety Authority (STUK) (Finland)


    In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

  3. Safety Implementation of Hydrogen Igniters and Recombiners for Nuclear Power Plant Severe Accident Management

    XIAO Jianjun; ZHOU Zhiwei; JING Xingqing


    Hydrogen combustion in a nuclear power plant containment building may threaten the integrity of the containment. Hydrogen recombiners and igniters are two methods to reduce hydrogen levels in containment buildings during severe accidents. The purpose of this paper is to evaluate the safety implementation of hydrogen igniters and recombiners. This paper analyzes the risk of deliberate hydrogen ignition and investigates three mitigation measures using igniters only, hydrogen recombiners only or a combination of recombiners and igniters. The results indicate that steam can effectively control the hydrogen flame acceleration and the deflagration-to-detonation transition.

  4. Stake-holder involvement in the management of rural areas after an accident

    Nisbet, A.F. [National Radiological Protection Board (NRPB), Oxon (United Kingdom)


    Widespread contamination of the food chain following a nuclear accident could have considerable consequences for European farming and food industries. For the purposes of contingency planning it is important to bring together the many and diverse stakeholders who would be involved in intervention so that strategies can be developed for maintaining agricultural production and food safety. This type of approach has been successfully implemented in the UK through the setting up of the Agriculture and Food Countermeasures Working Group. Building on this initiative, the European Commission under the auspices of its 5. Framework Programme is funding a thematic network in which similar stakeholder groups are being established in four other Member States. These national groups contain individuals involved in making policy decisions within government departments and agencies, regulatory authorities, the water, milk and farming industries, the retail trade and consumer groups, as well as individuals with specialist expertise. The stakeholder network will provide a European focus for tackling future nuclear accidents and assist in the harmonization of policies and strategies between Member States. This paper gives an overview of the approaches being adopted and discusses the achievements and expected benefits of stakeholder engagement. (author)

  5. Managing the identification of the mortal victims run over by a train in the Castelldefels railway accident (Barcelona).

    Barbería, Eneko; Martin-Fumadó, Carles; Galtés, Ignasi; Subirana-Domenech, Mercé; Puigbarraca-Sol, Lourdes; Vidal-Gutiérrez, Claudina; Valverde-Villarreal, Juan Luis; Castellà-García, Josep; Medallo-Muñiz, Jordi


    The identification of disaster victims is the formal, organized process of identifying multiple bodies after an incident with multiple victims. The appropriate management of these incidents, particularly of the bodies, is one of the most crucial aspects of disaster response and its importance has led to the evolution of the concept of Disaster Victim Management. The aim of this study is to report how the process of identifying the 12 mortal victims of a railway accident in June 2010 in Castelldefels (Barcelona) was managed. The methodology used complied with the National Protocol for medical forensic and scientific police response to mass casualty incidents. The family assistance center also served as an ante mortem (AM) office. Despite the fragmentation of the bodies, all the victims were identified satisfactorily. The main problems observed during the management of the disaster were due to the state of the bodies, which raised many doubts as to the number of fatalities. The experience prompted a proposal to establish some recommendations on limiting the number of fragments to be analyzed genetically. We would like to stress the importance of setting up a Data Integration Center which brought together all the participating institutions, and collected and supervised all the different identification reports in a single comprehensive text addressed to the competent legal authority.

  6. 抓好班组管理,做好事故预防%Clutching Well Team Management,Doing Well Prevention of Accident



    Team management has important significance for safe production. This paper firstly analyzes the inevitable link between the team management and prevention of accident, discusses the effective countermeasures for strengthening team safety management, preventing accidents from two aspects of the"five simultaneous"of team safety management and management responsibilities.%班组管理对于安全生产意义重大。本文首先分析班组管理与事故预防之间的必然联系,从班组安全管理“五同时”和管理责任两方面探讨强化班组安全管理,预防安全事故的有效对策。

  7. Agricultural land management options after the Chernobyl and Fukushima accidents: The articulation of science, technology, and society.

    Vandenhove, Hildegarde; Turcanu, Catrinel


    The options adopted for recovery of agricultural land after the Chernobyl and Fukushima accidents are compared by examining their technical and socio-economic aspects. The analysis highlights commonalities such as the implementation of tillage and other types of countermeasures and differences in approach, such as preferences for topsoil removal in Fukushima and the application of K fertilizers in Chernobyl. This analysis shows that the recovery approach needs to be context-specific to best suit the physical, social, and political environment. The complex nature of the decision problem calls for a formal process for engaging stakeholders and the development of adequate decision support tools. Integr Environ Assess Manag 2016;12:662-666. © 2016 SETAC.

  8. In-vessel melt retention as a severe accident management strategy for the Loviisa Nuclear Power Plant

    Kymaelaeinen, O.; Tuomisto, H. [IVO International Ltd., Vantaa (Finland); Theofanous, T.G. [Univ. of California, Santa Barbara, CA (United States)


    The concept of lower head coolability and in-vessel retention of corium has been approved as a basic element of the severe accident management strategy for IVO`s Loviisa Plant (VVER-440) in Finland. The selected approach takes advantage of the unique features of the plant such as low power density, reactor pressure vessel without penetrations at the bottom and ice-condenser containment which ensures flooded cavity in all risk significant sequences. The thermal analyses, which are supported by experimental program, demonstrate that in Loviisa the molten corium on the lower head of the reactor vessel is coolable externally with wide margins. This paper summarizes the approach and the plant modifications being implemented. During the approval process some technical concerns were raised, particularly with regard to thermal loadings caused by contact of cool cavity water and hot corium with the reactor vessel. Resolution of these concerns is also discussed.

  9. Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.


    This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

  10. Laryngeal Fracture after Blunt Cervical Trauma in Motorcycle Accident and Its Management

    Carneiro Sousa, Pedro; Abreu Pereira, Diogo; Azevedo, Paula; Duarte, Delfim


    Laryngeal fracture is a rare traumatic injury, potentially fatal, with an estimated incidence of 1 in 30,000 patients admitted to severe trauma centers. Because of the rarity of this injury, physician may be not aware of its existence, leading to a late diagnosis of this entity. We report a case of a 59-year-old woman admitted to the emergency room after a motorcycle accident with cervical trauma. The patient presented with dysphonia, hemoptysis, cervical subcutaneous emphysema, and increasing respiratory distress that led to the intubation of the patient. CT-scan demonstrated displaced fracture of the cricoid and thyroid cartilage. The patient was submitted to tracheostomy and the fracture was surgically repaired. Tracheostomy was removed in third postoperative month. The patient presented a good recovery, reporting only hoarseness but without swallowing or breathing problems at 6-month follow-up.

  11. Laryngeal Fracture after Blunt Cervical Trauma in Motorcycle Accident and Its Management

    Nuno Ribeiro-Costa


    Full Text Available Laryngeal fracture is a rare traumatic injury, potentially fatal, with an estimated incidence of 1 in 30,000 patients admitted to severe trauma centers. Because of the rarity of this injury, physician may be not aware of its existence, leading to a late diagnosis of this entity. We report a case of a 59-year-old woman admitted to the emergency room after a motorcycle accident with cervical trauma. The patient presented with dysphonia, hemoptysis, cervical subcutaneous emphysema, and increasing respiratory distress that led to the intubation of the patient. CT-scan demonstrated displaced fracture of the cricoid and thyroid cartilage. The patient was submitted to tracheostomy and the fracture was surgically repaired. Tracheostomy was removed in third postoperative month. The patient presented a good recovery, reporting only hoarseness but without swallowing or breathing problems at 6-month follow-up.

  12. Simulation analysis of environmental risk accident and management of high-sulfur gas field development in complex terrain

    Xiao WANG; Fanghua HAO; Xuan ZHANG; Wen SUN; Hongguang CHENG


    Environmental risk of high sulfur gas field exploitation has become one of the hot spots of envir-onmental management studies. Severe gas H2S blowout accidents in recent years have shown that poor under-standing and estimates of the poisonous gas movement could lead to dangerous evacuation delays. It is important to evaluate the real concentration of H2S, especially in complex terrain. Traditional experiential models are not valid in the case of rough terrain, especially in low-lying areas where the gas accumulates. This study, using high sulfur content gas field of Sichuan "Pu Guang gas field" as study object and adopting objective diagnosis of wind field of land following coordinate three dimensions, applied Lagrangian Puff Model and breaking up tech-nique of puffs to simulate the H2S diffusion condition of blowout accidents produced in the high sulfur content gas field of complex terrain area. The results showed that the H2S distribution did not occur mainly in low wind dir-ection, and due to the obstruction of the mountain's body, it accumulated in front of mountain on produced turn over, flowed around submitted jumping type distribution. The mountain waist near the hilltop and low hollow river valley site rapture points simulating contrast showed that the higher the rapture point, the better the diffusing con-dition of pollutant, the distribution of risk sensitive point decided piping rupture environmental risk size combining the H2S diffusion result and residential area dispersing in the study area, synthetic judge located in the high rapture point environmental risk was smaller than the low hollow point, thus it was suggested to carryout laying of lining build of equal high line of higher terrain. According to simulation results, the environmental risk management measures aimed at putting down adverse effects were worked out.

  13. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    Weiss, A. J. [comp.


    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately.

  14. Bicycle accidents.

    Lind, M G; Wollin, S


    Information concerning 520 bicycle accidents and their victims was obtained from medical records and the victims' replies to questionnaires. The analyzed aspects included risk of injury, completeness of accident registrations by police and in hospitals, types of injuries and influence of the cyclists' age and sex, alcohol, fatigue, hunger, haste, physical disability, purpose of cycling, wearing of protective helmet and other clothing, type and quality of road surface, site of accident (road junctions, separate cycle paths, etc.) and turning manoeuvres.

  15. Tools for improving safety management in the Norwegian Fishing Fleet occupational accidents analysis period of 1998-2006.

    Aasjord, Halvard L


    Reporting of human accidents in the Norwegian Fishing Fleet has always been very difficult because there has been no tradition in making reports on all types of working accidents among fishermen, if the accident does not seem to be very serious or there is no economical incentive to report. Therefore reports are only written when the accidents are serious or if the fisherman is reported sick. Reports about an accident are sent to the insurance company, but another report should also be sent to the Norwegian Maritime Directorate (NMD). Comparing of data from one former insurance company and NMD shows that the real numbers of injuries or serious accidents among Norwegian fishermen could be up to two times more than the numbers reported to NMD. Special analyses of 1690 accidents from the so called PUS-database (NMD) for the period 1998-2002, show that the calculated risk was 23.6 accidents per 1000 man-years. This is quite a high risk level, and most of the accidents in the fishing fleet were rather serious. The calculated risks are highest for fishermen on board the deep sea fleet of trawlers (28.6 accidents per 1000 man-years) and also on the deep sea fleet of purse seiners (28.9 accidents per 1000 man-years). Fatal accidents over a longer period of 51.5 years from 1955 to 2006 are also roughly analysed. These data from SINTEF's own database show that the numbers of fatal accidents have been decreasing over this long period, except for the two periods 1980-84 and 1990-94 where we had some casualties with total losses of larger vessels with the loss of most of the crew, but also many others typical work accidents on smaller vessels. The total numbers of registered Norwegian fishermen and also the numbers of man-years have been drastically reduced over the 51.5 years from 1955 to 2006. The risks of fatal accidents have been very steady over time at a high level, although there has been a marked risk reduction since 1990-94. For the last 8.5-year period of January 1998


    Hüdayim BAŞAK


    Full Text Available In this study, it is aimed to investigate operationally risky areas by analyzing dangers which can arise during the maintenance and flight activities of Unmanned Air Vehicles (UAVs. For this purpose, a risk analysis methodology was introduced and then within the framework of the application, a sample of risk management model was developed. During the development of the model, personal experiences in the area of UAVs were benefited and a risk management technique consisting of five steps used by pioneering international aviation companies in fliht safety was utilized.

  17. Severe accident recriticality analyses (SARA)

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


    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 ...

  18. 车集矿实施站位管理预防安全事故%Location Management Is Implemented to Prevent Safety Accident in Cheji Colliery



    零打碎敲事故是矿井安全管理的重点和难点,本文提出了站位管理法,即通过规范职工在各项作业过程中所处的位置,以规避可能存在的风险,避免发生人身伤害事故。%Piecemeal accident is important and difficult for safety management of coal mine .The paper introduces the location management method ,w hich can avoid possible risk and personal injured accident by the specification of workers'location in various work processes .

  19. 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...

  20. Sports Accidents



    Le Docteur Kiebel, chirurgien à Genève, est aussi un grand ami de sport et de temps en temps médecin des classes genevoises de ski et également médecin de l'équipe de hockey sur glace de Genève Servette. Il est bien qualifié pour nous parler d'accidents de sport et surtout d'accidents de ski.

  1. European consensus on the medical management of acute radiation syndrome and analysis of the radiation accidents in Belgium and Senegal.

    Gourmelon, Patrick; Benderitter, Marc; Bertho, Jean Marc; Huet, Christelle; Gorin, Norbert Claude; De Revel, Patrick


    A European consensus concerning the medical management of mass radiation exposure was obtained in 2005 during a conference held by the European Group for Blood and Bone Marrow Transplantation, the Institute of Radioprotection and Nuclear Safety, and the University of Ulm. At the conference, a two-step triage strategy to deal with large masses of radiation-exposed patients was designed. The first step of this strategy concerns the first 48 h and involves scoring the patients exclusively on the basis of their clinical symptoms and biological data. This allows the non-irradiated bystanders and outpatient candidates to be identified. The remaining patients are hospitalized and diagnosis is confirmed after the first 48-h period according to the METREPOL (Medical Treatment Protocols for radiation accident victims) scale. This grades the patients according to the severity of their symptoms. It was also agreed that in the case of acute radiation syndrome (ARS), emergency hematopoietic stem cell (HSC) transplantation is not necessary. Instead, cytokines that promote hematological reconstruction should be administered as early as possible for 14-21 d. Crucial tests for determining whether the patient has residual hematopoiesis are physical dose reconstructions combined with daily blood count analyses. It was agreed that HSC transplantation should only be considered if severe aplasia persists after cytokine treatment. Two recent cases of accidental radiation exposure that were managed successfully by following the European consensus with modification are reviewed here. Thus, a European standard for the evaluation and treatment of ARS victims is now available. This standard may be suitable for application around the world.

  2. Hindsight Bias in Cause Analysis of Accident

    Atsuo Murata; Yasunari Matsushita


    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.

  3. Optimization of the Severe Accident Management Strategy for Domestic Plants and Validation Experiments

    Kim, S. B.; Park, R. J.; Kim, H. D.; Koo, K. M.; Cho, Y. R.; Kim, J. T.; Ha, K. S.; Kang, K. H.; Hong, S. H.; Kim, H. Y


    Main components and structures in nuclear power plants generally use materials having superior resistance to corrosion.Since the damages related to corrosion have become a menace to the safety of NPPs as well as economical loss and the steam generator tubing forming a boundary between the primary and secondary sides of NPPs is one of the main components that are most damaged by corrosion, it is strongly required to verify the mechanisms of the steam generator tubing degradations, to develop remedial techniques for the degradations, to manage the damages, and to develop techniques for the extension of the plant's life. In this study, the PWSCC characteristics of the archived steam generator tube materials in the domestic NPPs were evaluated and the databases of the obtained results were established. Also, the PWSCC characteristics of the welding material, Alloy 182, for Alloy 600, were evaluated. To verify the damage mechanisms of the circumferential SCC occurring in the expansion transition region of the tubes in the Korean standard NPPS, the evaluation technique for the residual stresses in the expanded region was acquired. A procedure of the inhibition technique for the SCC occurring in the secondary side of steam generators and a model for estimating the safety of damaged tubes by the structural leakage were developed, by which the fundamental technologies for the safe operations of NPPs, the management of the damages, and the expansion of the plant life were acquired. The material improvement technique for the integrity enhancement of tubes was developed. Along with the development of the Ni-coating technique the evaluation of the properties such as mechanical and SCC properties of the coated film was performed.

  4. Human factors engineering in healthcare systems: the problem of human error and accident management.

    Cacciabue, P C; Vella, G


    This paper discusses some crucial issues associated with the exploitation of data and information about health care for the improvement of patient safety. In particular, the issues of human factors and safety management are analysed in relation to exploitation of reports about non-conformity events and field observations. A methodology for integrating field observation and theoretical approaches for safety studies is described. Two sample cases are discussed in detail: the first one makes reference to the use of data collected in the aviation domain and shows how these can be utilised to define hazard and risk; the second one concerns a typical ethnographic study in a large hospital structure for the identification of most relevant areas of intervention. The results show that, if national authorities find a way to harmonise and formalize critical aspects, such as the severity of standard events, it is possible to estimate risk and define auditing needs, well before the occurrence of serious incidents, and to indicate practical ways forward for improving safety standards.

  5. Inter-laboratory comparison to validate the dicentric assay as a cytogenetic triage tool for medical management of radiation accidents

    Beinke, Christina, E-mail: [Bundeswehr Institute of Radiobiology Affiliated to the University of Ulm, Neuherbergstrasse 11, 80937 Munich (Germany); Oestreicher, Ursula [Federal Office for Radiation Protection, Neuherberg (Germany); Riecke, Armin [Department for Internal Medicine, Federal Armed Forces Hospital, Ulm (Germany); Kulka, Ulrike [Federal Office for Radiation Protection, Neuherberg (Germany); Meineke, Viktor [Bundeswehr Institute of Radiobiology Affiliated to the University of Ulm, Neuherbergstrasse 11, 80937 Munich (Germany); Romm, Horst [Federal Office for Radiation Protection, Neuherberg (Germany)


    Radiation accidents with exposure of human beings can assume huge dimensions concerning occurring health impairments and essential medical resources such as personnel, patient care management and appropriate medical facilities. Particularly in mass-casualty events, a rapid sorting and allocation of victims to treatment is needed and their classification in medical treatment groups has to be conducted as fast as possible. For triage purposes several approaches can be considered. Clinical signs and symptoms are extremely helpful in estimating radiation effects on an organ-based level, whereas the assessment of radiation effects based on cytogenetic biodosimetry tools is the alternative approach. For both systems there are pros and cons with respect to the usefulness for specific applications, such as individual cases versus mass-casualty screening or whole- versus partial-body exposures. Among the biodosimetry tools the dicentric chromosome assay (DCA) is considered as the 'gold standard' for biodosimetry after an acute radiation exposure. Recently, steady progress in standardization and harmonization of the DCA has occurred, in order to enable the validated performance of the DCA in the frame of cooperative response of biodosimetry networks during a large scale radiological scenario. Using the DCA in triage mode which allows the stratification of radiation exposed victims into broad 1.0 Gy categories only 20-50 metaphase cells per subject are scored instead of the 500-1000 scored for routine analysis. Our data show that there are significant differences between the dicentric yields after 1.0 Gy and 3.0 Gy {gamma}-ray ex vivo exposure of blood suggesting this assay as suitable for the distinction between high and low dosed exposed individuals. These preliminary findings indicate the usefulness of the DCA also for therapeutic decision making.

  6. An Entry Point of the Emergency Response Robot for Management of Severe Accident of the Nuclear Power Plant

    Cho, Jaiwan; Jeong, Kyungmin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    In this paper, from the view point of DID (defense-in depth), we discuss the entry point of the nuclear emergency response robot to cope with a nuclear disaster. A Japanese nuclear disaster preparedness robot system was developed, after the JCO criticality accident in 1999, to cope with INES (International Nuclear and Radiological Event Scale) Level 3 serious incidents. INES Level 3 means the loss of DID (defense-in-depth) functions. It also indicates that ESF (engineered safety features) and ECCS (emergency core cooling system) resources, which are used to prevent serious incidents from escalating to severe accidents (core melt-down), have been almost exhausted. In the unit 1 reactor accident of Fukushima Daiichi Nuclear Power Plant, escalation from INES Level 1 (Out of Limiting Condition for Operation) to INES Level 5 (serious core melting-down) took less than two hours. Major facts are briefly described here in based on data gathered immediately after the tsunami over Fukushima Daiichi Nuclear Power Plant. Ο 15:35 on March 11, 2nd tsunami arrived. - 15:37, SBO (station black out) Ο 15:42, Interprets as a SBO (INES Level 1) - Loss of DC power for Instrumentation (Unknown of reactor water level) Ο 16:36, Loss of ECCS function (INELS Level 5) (Entry into a BDBA status) The Moni ROBO-A robot of the Japan Nuclear Safety Technology Center (NUSTEC) was a nuclear disaster preparedness robot developed after the JCO criticality accident. It was the only robot that had been steadily maintained and was available at the time of the Fukushima Daiichi Nuclear Power Plant accident. However, it was not helpful in mitigating the accident because it is assumed to have arrived at J-Village after the accident had been escalated to INES Level 5 or higher. Based on the paper by S. Kawatsuma of JAEA and response data gathered immediately after the tsunami, it is estimated that the NUSTEC's Moni ROBO-A arrived at J-Village after the designed entry point for INES Level 3

  7. Evaluation of an accident management strategy of emergency water injection using fire engines in a typical pressurized water reactor

    Park, Soo Yong; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    Following the Fukushima accident, a special safety inspection was conducted in Korea. The inspection results show that Korean nuclear power plants have no imminent risk for expected maximum potential earthquake or coastal flooding. However long- and short-term safety improvements do need to be implemented. One of the measures to increase the mitigation capability during a prolonged station blackout (SBO) accident is installing injection flow paths to provide emergency cooling water of external sources using fire engines to the steam generators or reactor cooling systems. This paper illustrates an evaluation of the effectiveness of external cooling water injection strategies using fire trucks during a potential extended SBO accident in a 1,000 MWe pressurized water reactor. With regard to the effectiveness of external cooling water injection strategies using fire engines, the strategies are judged to be very feasible for a long-term SBO, but are not likely to be effective for a short-term SBO.

  8. A B C分类管理方法在海事安全管理中的应用%ABC Classification in Waterborne Traffic Accidents Safety Management



    将仓储管理ABC分类法引入海事的安全管理中,以便于安全管理部门针对不同水域的海事发生频率、危险程度,制定不同的安全管理对策,并能够充分利用有限的管理资源以提高海事安全管理水平.%If the ABC classification is applied to the management of the waterborne traffic safety,it is convenient for the safety management department to establish different management countermeasures according to the different frequency and criticality of waterborne traffic accidents in different shipping area,shipping company,etc,and to make full use the best of the limited resources in order to improve the management level of waterborne traffic safety.

  9. Accident management information needs

    Hanson, D.J.; Ward, L.W.; Nelson, W.R.; Meyer, O.R. (EG and G Idaho, Inc., Idaho Falls, ID (USA))


    The tables contained in this Appendix A describe the information needs for a pressurized water reactor (PWR) with a large, dry containment. To identify these information needs, the branch points in the safety objective trees were examined to decide what information is necessary to (a) determine the status of the safety functions in the plant, i.e., whether the safety functions are being adequately maintained within predetermined limits, (b) identify plant behavior (mechanisms) or precursors to this behavior which indicate that a challenge to plant safety is occurring or is imminent, and (c) select strategies that will prevent or mitigate this plant behavior and monitor the implementation and effectiveness of these strategies. The information needs for the challenges to the safety functions are not examined since the summation of the information needs for all mechanisms associated with a challenge comprise the information needs for the challenge itself.

  10. Review of current severe accident management approaches in Europe and identification of related modelling requirements for the computer code ASTEC V2.1

    Hermsmeyer, S. [European Commission JRC, Petten (Netherlands). Inst. for Energy and Transport; Herranz, L.E.; Iglesias, R. [CIEMAT, Madrid (Spain); and others


    The severe accident at the Fukushima-Daiichi nuclear power plant (NPP) has led to a worldwide review of nuclear safety approaches and is bringing a refocussing of R and D in the field. To support these efforts several new Euratom FP7 projects have been launched. The CESAM project focuses on the improvement of the ASTEC computer code. ASTEC is jointly developed by IRSN and GRS and is considered as the European reference code for Severe Accident Analyses since it capitalizes knowledge from the extensive Euro-pean R and D in the field. The project aims at the code's enhancement and extension for use in Severe Accident Management (SAM) analysis of the NPPs of Generation II-III presently under operation or foreseen in the near future in Europe, spent fuel pools included. The work reported here is concerned with the importance, for the further development of the code, of SAM strategies to be simulated. To this end, SAM strategies applied in the EU have been compiled. This compilation is mainly based on the public information made available in the frame of the EU ''stress tests'' for NPPs and has been complemented by information pro-vided by the different CESAM partners. The context of SAM is explained and the strategies are presented. The modelling capabilities for the simulation of these strategies in the current production version 2.0 of ASTEC are discussed. Furthermore, the requirements for the next version of ASTEC V2.1 that is supported in the CESAM project are highlighted. They are a necessary complement to the list of code improvements that is drawn from consolidating new fields of application, like SFP and BWR model enhancements, and from new experimental results on severe accident phenomena.

  11. Using Numerical Models in the Development of Software Tools for Risk Management of Accidents with Oil and Inert Spills

    Fernandes, R.; Leitão, P. C.; Braunschweig, F.; Lourenço, F.; Galvão, P.; Neves, R.


    The increasing ship traffic and maritime transport of dangerous substances make it more difficult to significantly reduce the environmental, economic and social risks posed by potential spills, although the security rules are becoming more restrictive (ships with double hull, etc.) and the surveillance systems are becoming more developed (VTS, AIS). In fact, the problematic associated to spills is and will always be a main topic: spill events are continuously happening, most of them unknown for the general public because of their small scale impact, but with some of them (in a much smaller number) becoming authentic media phenomena in this information era, due to their large dimensions and environmental and social-economic impacts on ecosystems and local communities, and also due to some spectacular or shocking pictures generated. Hence, the adverse consequences posed by these type of accidents, increase the preoccupation of avoiding them in the future, or minimize their impacts, using not only surveillance and monitoring tools, but also increasing the capacity to predict the fate and behaviour of bodies, objects, or substances in the following hours after the accident - numerical models can have now a leading role in operational oceanography applied to safety and pollution response in the ocean because of their predictive potential. Search and rescue operation, oil, inert (ship debris, or floating containers), and HNS (hazardous and noxious substances) spills risk analysis are the main areas where models can be used. Model applications have been widely used in emergency or planning issues associated to pollution risks, and contingency and mitigation measures. Before a spill, in the planning stage, modelling simulations are used in environmental impact studies, or risk maps, using historical data, reference situations, and typical scenarios. After a spill, the use of fast and simple modelling applications allow to understand the fate and behaviour of the spilt

  12. Emergency monitoring strategy and radiation measurements document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    Lahtinen, J. [Radiation and Nuclear Safety Authority (STUK) (Finland)


    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  13. Accident: Reminder


    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

  14. RENEB accident simulation exercise

    Brzozowska, Beata; Ainsbury, Elizabeth; Baert, Annelot; Beaton-Green, Lindsay; Barrios, Leonardo; Barquinero, Joan Francesc; Bassinet, Celine; Beinke, Christina; Benedek, Anett; Beukes, Philip; Bortolin, Emanuela; Buraczewska, Iwona; Burbidge, Christopher; De Amicis, Andrea; De Angelis, Cinzia


    Purpose: The RENEB accident exercise was carried out in order to train the RENEB participants in coordinating and managing potentially large data sets that would be generated in case of a major radiological event. Materials and methods: Each participant was offered the possibility to activate the network by sending an alerting email about a simulated radiation emergency. The same participant had to collect, compile and report capacity, triage categorization and exposure scenario results ob...

  15. SCAP: a new methodology for safety management based on feedback from credible accident-probabilistic fault tree analysis system.

    Khan, F I; Iqbal, A; Ramesh, N; Abbasi, S A


    As it is conventionally done, strategies for incorporating accident--prevention measures in any hazardous chemical process industry are developed on the basis of input from risk assessment. However, the two steps-- risk assessment and hazard reduction (or safety) measures--are not linked interactively in the existing methodologies. This prevents a quantitative assessment of the impacts of safety measures on risk control. We have made an attempt to develop a methodology in which risk assessment steps are interactively linked with implementation of safety measures. The resultant system tells us the extent of reduction of risk by each successive safety measure. It also tells based on sophisticated maximum credible accident analysis (MCAA) and probabilistic fault tree analysis (PFTA) whether a given unit can ever be made 'safe'. The application of the methodology has been illustrated with a case study.

  16. PTSD in post-road traffic accident patients requiring hospitalization in Indian subcontinent: A review on magnitude of the problem and management guidelines.

    Undavalli, Chaitanya; Das, Piyush; Dutt, Taru; Bhoi, Sanjeev; Kashyap, Rahul


    Traumatic events after a road traffic accident (RTA) can be physical and/or psychological. Posttraumatic stress disorder (PTSD) is one of the major psychological conditions which affect accident victims. Psychological issues may not be addressed in the emergency department(ED) immediately. There have been reports about a mismatch between the timely referrals from ED to occupational or primary care services for these issues. If left untreated, there may be adverse effects on quality of life (QOL) and work productivity. Hospital expenses, loss of income, and loss of work could create a never ending cycle for financial difficulties and burden in trauma victims. The aim of our review is to address the magnitude of PTSD in post-RTA hospitalized patients in Indian subcontinent population. We also attempted to emphasis on few management guidelines. A comprehensive search was conducted on major databases with Medical Subject Headings (MeSH) term 'PTSD or post-traumatic stress' and Emergency department and vehicle or road or highway or automobile or car or truck or trauma and India. Out of 120 studies, a total of six studies met our inclusion criteria and were included in the review. Our interpretation of the problem is that; hospital expenditure due to trauma, time away from work during hospitalization, and reduction in work performance, are three major hits that can lead RTA victims to financial crisis. Proposed management guidelines are; establish a coordinated triage, implementing a screening tool in the ED, and provide psychological counseling.

  17. PTSD in post-road traffic accident patients requiring hospitalization in Indian subcontinent: A review on magnitude of the problem and management guidelines

    Chaitanya Undavalli


    Full Text Available Traumatic events after a road traffic accident (RTA can be physical and/or psychological. Posttraumatic stress disorder (PTSD is one of the major psychological conditions which affect accident victims. Psychological issues may not be addressed in the emergency department(ED immediately. There have been reports about a mismatch between the timely referrals from ED to occupational or primary care services for these issues. If left untreated, there may be adverse effects on quality of life (QOL and work productivity. Hospital expenses, loss of income, and loss of work could create a never ending cycle for financial difficulties and burden in trauma victims. The aim of our review is to address the magnitude of PTSD in post-RTA hospitalized patients in Indian subcontinent population. We also attempted to emphasis on few management guidelines. A comprehensive search was conducted on major databases with Medical Subject Headings (MeSH term ′PTSD or post-traumatic stress′ and Emergency department and vehicle or road or highway or automobile or car or truck or trauma and India. Out of 120 studies, a total of six studies met our inclusion criteria and were included in the review. Our interpretation of the problem is that; hospital expenditure due to trauma, time away from work during hospitalization, and reduction in work performance, are three major hits that can lead RTA victims to financial crisis. Proposed management guidelines are; establish a coordinated triage, implementing a screening tool in the ED, and provide psychological counseling.

  18. Analysis of accident sequences and source terms at waste treatment and storage facilities for waste generated by U.S. Department of Energy Waste Management Operations, Volume 3: Appendixes C-H

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J. [and others


    This report contains the Appendices for the Analysis of Accident Sequences and Source Terms at Waste Treatment and Storage Facilities for Waste Generated by the U.S. Department of Energy Waste Management Operations. The main report documents the methodology, computational framework, and results of facility accident analyses performed as a part of the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies are assessed, and the resultant radiological and chemical source terms are evaluated. A personal computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for calculation of human health risk impacts. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also provide discussion of specific accident analysis data and guidance used or consulted in this report.

  19. Severe Psychological Distress of Evacuees in Evacuation Zone Caused by the Fukushima Daiichi Nuclear Power Plant Accident: The Fukushima Health Management Survey.

    Yasuto Kunii

    Full Text Available Following the Great East Japan Earthquake on March 11, 2011, the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant has continued to affect the mental health status of residents in the evacuation zone. To examine the mental health status of evacuee after the nuclear accident, we conducted the Mental Health and Lifestyle Survey as part of the ongoing Fukushima Health Management Survey.We measured mental health status using the Kessler 6-item psychological distress scale (K6 in a total of 73,569 (response rate: 40.7% evacuees aged 15 and over who lived in the evacuation zone in Fukushima Prefecture. We then dichotomized responders using a 12/13 cutoff on the K6, and compared the proportion of K6 scores ≥13 and ≤12 in each risk factor including demographic information, socioeconomic variables, and disaster-related variables. We also performed bivariate analyses between mental health status and possible risk factors using the chi-square test. Furthermore, we performed multivariate regression analysis using modified Poisson regression models.The median K6 score was 5 (interquartile range: 1-10. The number of psychological distress was 8,717 (14.6%. We found that significant differences in the prevalence of psychological distress by almost all survey items, including disaster-related risk factors, most of which were also associated with increased Prevalence ratios (PRs. Additionally, we found that psychological distress in each evacuation zone was significantly positively associated with the radiation levels in their environment (r = 0.768, p = 0.002.The earthquake, tsunami and subsequent nuclear accident likely caused severe psychological distress among residents in the evacuation zone in Fukushima Prefecture. The close association between psychological distress and the radiation levels shows that the nuclear accident seriously influenced the mental health of the residents, which might be exacerbated by increased risk perception. To

  20. Severe Psychological Distress of Evacuees in Evacuation Zone Caused by the Fukushima Daiichi Nuclear Power Plant Accident: The Fukushima Health Management Survey

    Kunii, Yasuto; Suzuki, Yuriko; Shiga, Tetsuya; Yabe, Hirooki; Yasumura, Seiji; Maeda, Masaharu; Niwa, Shin-ichi; Otsuru, Akira; Mashiko, Hirobumi; Abe, Masafumi


    Background Following the Great East Japan Earthquake on March 11, 2011, the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant has continued to affect the mental health status of residents in the evacuation zone. To examine the mental health status of evacuee after the nuclear accident, we conducted the Mental Health and Lifestyle Survey as part of the ongoing Fukushima Health Management Survey. Methods We measured mental health status using the Kessler 6-item psychological distress scale (K6) in a total of 73,569 (response rate: 40.7%) evacuees aged 15 and over who lived in the evacuation zone in Fukushima Prefecture. We then dichotomized responders using a 12/13 cutoff on the K6, and compared the proportion of K6 scores ≥13 and ≤12 in each risk factor including demographic information, socioeconomic variables, and disaster-related variables. We also performed bivariate analyses between mental health status and possible risk factors using the chi-square test. Furthermore, we performed multivariate regression analysis using modified Poisson regression models. Results The median K6 score was 5 (interquartile range: 1–10). The number of psychological distress was 8,717 (14.6%). We found that significant differences in the prevalence of psychological distress by almost all survey items, including disaster-related risk factors, most of which were also associated with increased Prevalence ratios (PRs). Additionally, we found that psychological distress in each evacuation zone was significantly positively associated with the radiation levels in their environment (r = 0.768, p = 0.002). Conclusion The earthquake, tsunami and subsequent nuclear accident likely caused severe psychological distress among residents in the evacuation zone in Fukushima Prefecture. The close association between psychological distress and the radiation levels shows that the nuclear accident seriously influenced the mental health of the residents, which might be exacerbated by

  1. Self-reported accidents

    Møller, Katrine Meltofte; Andersen, Camilla Sloth


    The main idea behind the self-reporting of accidents is to ask people about their traffic accidents and gain knowledge on these accidents without relying on the official records kept by police and/or hospitals.......The main idea behind the self-reporting of accidents is to ask people about their traffic accidents and gain knowledge on these accidents without relying on the official records kept by police and/or hospitals....

  2. Post-accident management: the point of view of the European Commission; Gestion post-accidentelle d'un accident nucleaire: apercu des activites de l'AIEA

    Amaral, E. [Agence International de l' Energie Atomique (AIEA), Div. de la Surete Radiologique et de la Surete du Transport et des Dechets, Vienna(Austria)


    This paper will present documents and activities developed and implemented by the IAEA regarding remediation activities. It will be also described the lessons learned from two accidents as outcomes of two important conferences organized by IAEA. (author)

  3. Lessons learned from post-accident management at Chernobyl: the P.a.r.e.x. project; Retour d'experience sur la gestion post-accidentelle de Tchernobyl: le projet Parex

    Heriard Dubreuil, G. [Mutadis Consultants, 75 - Paris (France); Lochard, J.; Bataille, C. [CEPN, 92 - Fontenay aux Roses (France); Ollagnon, H. [AgroParisTech, 75 - Paris (France); Baude, St. [Mutadis, 75 - Paris (France)


    Return of experience on Chernobyl post-accident management: the PAREX study Belarus is the country the most affected by the Chernobyl fallouts and is among the most significant experiences in the nuclear post-accident field. Despite specificities inherent to the political and social situation in Belarus, the experience of post-accidental management in this country holds a wealth of lessons in the perspective of preparation to a post-accidental situation in the French and European context. Through the PAREX project (2005-2006), the French Nuclear Safety Authority analysed the return of experience of Chernobyl post-accident management from 1986 to 2005 in order to draw its lessons in the perspective of a preparation policy. The study was led by a group of experts and involved the participation of a pluralistic group of about thirty participants (public authorities, local governments, NGOs, experts, operators). PAREX highlighted the complexity of a situation of long-lasting radioactive contamination (diversity of stakeholders and of dimensions at stake: health, environment, economy, society...). Beyond traditional public crisis management tools and frameworks, post-accident strategies also involves in the longer term a territorial and social response, which relies on local capacities of initiative. Preparation to such process requires experimenting new modes of operation that allow a diversity of local actors to take part to the response to a situation of contamination and to the surveillance system, with the support of public authorities. The conclusions of PAREX include a set of recommendations in this perspective. (authors)

  4. Risk Analysis of Security Accident Management in Chemical Enterprises%化工企业的安全事故管理隐患的探析



    本文从化工企业目前存在的安全管理隐患入手,阐述了其企业自身可能引发安全责任事故发生的人为隐患、物的隐患与管理上的隐患等,并给出了化工企业潜在安全管理隐患的定性与定量判识方法;并针对化工企业的行业特殊性,提出了排查、治理安全管理环节所存在的各种隐患的解决措施和相应的安全对策。%Some risks which may lead security responsibility accident including anthropogenic risks , physical risks and management risks , etc.were described , and some qualitative and quantitative diagnostic methods about potential security risk management were listed , according to the existing security management in chemical enterprises.Many solutions and appropriate measures were proposed for a variety of risks existed in the investigation , control work , etc.and for the chemical industry enterprises particularity.

  5. 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)


    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.

  6. 化工机械设备故障与事故管理的建议%Suggestion on Chemical Machinery Equipment Failure and Accident Management



    Because chemical industry is an important industry in national economy, and the chemical machinery and equipment is also an indispensable important part of modern machinery manufacturing industry. Because of long time operation and other factors, different degree of fault caused in the chemical machinery equipment, and the larger potential safety hazard are caused. In this paper, it will discuss chemical machinery equipment failure and accident management from three aspects of the type, causes and management measures, hoping to provide reference for everyone.%化工行业作为国民经济中的重要行业,化工机械设备也是现代机械制造业不可或缺的重要部分,化工机械设备由于长时间的运作等影响因素发生了不同程度的故障,带来了较大的安全隐患。文章将从发生故障的类型、原因与管理措施三方面来探讨化工机械设备故障与事故管理,希望能为大家提供借鉴。

  7. Comparative analysis on emergency management for leakage explosion accidents of urban oil and gas pipeline%城市油气管道泄漏爆炸重大案例应急管理对比研究

    李晶晶; 朱渊; 陈国明; 李修峰


    The extraordinary serious accident of Dongying-Huangdao oil pipeline leakage explosion in Qingdao , Shandong, has aroused public concern nationwide about urban oil and gas pipeline safety .In recent years, acci-dents in urban oil and gas pipeline frequently occurred , which seriously indicate the major problems existed in se-curity management .Comparative analysis was carried out based on similar accident investigation , between sewer network explosion in Guadalajara Mexico and Dongying-Huangdao oil pipeline leakage explosion in Qingdao Shang-dong .According to the accident-causing theory , the developing trend of accident was explored and chain model was established .Combined the concept of emergency management , common issues were analyzed during the process from pre-warning and pre-control , emergency disposal , assessment and recovery .Control measures were proposed in each stage of emergency management , by learning from the lessons of accidents , in order to reduce the probabili-ty of accidents and enhance the capability of emergency manage .%青岛东黄输油管道泄漏爆炸特别重大事故,引起公众对城市油气管道安全的普遍关注。近年来,城市油气管道事故频繁发生,反映出我国在城市地下管道安全管理方面存在较大问题。基于国内外管道相似事故调研,选取墨西哥瓜达拉哈拉管道泄漏爆炸事故和青岛东黄输油管道泄漏爆炸事故进行对比分析。基于事故致因理论,探究事故发展模式,建立事故链模型。结合应急管理思想,从预警预控、应急处置、评估恢复角度分析事故应急管理过程的共性失误。最后,针对应急管理各阶段共性失误提出防范措施,对提高类似事故的应急管理能力具有一定的参考意义。


    王韶伟; 柴建设; 岳会国; 林权益; 晋宏博; 王红瑞


    Fukushima nuclear accident is reviewed. Laws and regulations of nuclear emergency management and nuclear emergency management system in China are presented in this paper. Nuclear emergency response, radiation environmental monitoring, radioactive consequence assessment, information publicity and public opinion control in China during Fukushima nuclear accident are introduced. Advices are given for promoting nuclear emergency management in China, based on experiences of Fukushima Nuclear Power Plant accident, international suggestions and recommended actions: enhanced recognition ability of nuclear accident risk, strengthened assessment ability of nuclear accident consequence, and positive and efficient response to public sentiment.%在简要回顾日本福岛核电站事故的基础上,阐述了我国现有的核应急管理法律法规和核应急管理体系,从应急响应、辐射环境监测、放射性后果评估、信息公开和舆论监控等方面介绍了我国在日本福岛核事故期间的应急管理.最后依据福岛核事故的经验,结合国际上相关国家的建议和推荐的行动计划,针对我国国情,从提高核事故风险认识能力,加强核事故后果评估能力,积极有效应对核事故舆情3个方面给出提升我国核事故应急管理水平的建议.

  9. 加强电力行业安全管理减少安全事故发生%Strengthening Safety Management of Electric Power Industry to Reduce Safety Accidents



    电力行业发展到今天,法律法规,规章制度,劳动纪律,技术规程,安全措施,已相当严密完善,但由于位于中心的“人”的失误造成事故仍时有发生,许多事故造成很惨痛的后果.事故的发生往往是猝不及防,有些事故不该发生,分析各种事故案例,发现大量事故都是由于事故责任人心存侥幸心理、冒险心理、麻痹心理,图快、图省事等原因造成违反规程,酿成惨祸.安全工作是一项只有起点没有终点的工作.安全事故的发生,与有关人员思想不重视、工作不落实、制度不坚持、责任不到位有很大关系.养成好的工作习惯,安全从点滴做起,从细节做起.%With the development of electric power industry, laws and regulations, rules and regulations, labor discipline, technical procedures, and safety measures have been sound. The accidents caused by human being mistake are increased, and many accidents are very disastrous. The accident is often sudden, and many accidents are avoidable. Through analyzing the accidents, the authors find that most of accidents are caused by the operator with fluke mind. Safety management work is constant. At last, the paper puts forward the measures such as developing good habit about work, be careful and serious about work.

  10. 基于事故致因理论的实验室安全管理体系的分析%Analysis on the Laboratory Management System Based on Accident-Cauring Theory

    韩雪; 宋旭梅; 景峰


    Compared with the other accidents, laboratory accidents are much emergent and complicated. The outcomes of laboratory accidents directly affect the construction and stability of the campus, therefore, the safety management is the top priority of every laboratory in every campus. Based on the laboratory management situation of Textile & Chemical Engineering Experimental Demonstration Center in Qiqihar University, the paper aims to provide some reference for the laboratory safety management of other universities by doing the following aspects in view of accident reason theory: to explore the potential reasons leading to the laboratory safety accident; to further improve the rules and strengthen the leadership as well as optimize the management in line with our own practices;to enhance the safety awareness and skills of the laboratory workers to avoid the accident and optimize safety management.%高校实验室事故的后果与其他事故相比,更具有突发性、复杂性等特点,直接影响高校建设与校园安定,故高校实验室的安全管理成为一个至关重要的问题。针对齐齐哈尔大学轻化工程实验示范中心的实验室管理现状,基于事故致因理论,探究了可能诱发实验室安全事故的原因,结合自身的管理实践,进一步完善规章制度、强化组织领导、优化管理流程、加强宣传教育,以及提高实验室人员的使用素质和安全意识等,以避免实验室事故的发生,优化安全管理,为其他高校实验室安全管理提供一定的借鉴。

  11. Analysis of Fukushima Daiichi Accident Using HFACS

    Mohamed, Saeed Almheiri [Korea Advanced Institue of Science and Technology, Daejeon (Korea, Republic of)


    The shadow of Fukushima Daiichi nuclear power plant (NPP) accident is still too big and will last long. On the other hand, it could still teach us lots of lessons to better design and operate nuclear power plants. In this paper, we will be focusing on the Fukushima Daiichi accident, especially on human organizational factors. We will analyze the accident using Human Factors Analysis and Classification System (HFACS) in order to better understand the organizational climate of TEPCO{sup 1} and NISA{sup 2} that led to Fukushima Daiichi Accident. HFACS was developed for the U. S. aviation industry and has been used at many industries like the rail and mining industries. We found that the HFACS to be greatly beneficial in investigating the latent and organizational causes for the accident. The application results show that the causes of Fukushima Daiichi accident were spread out from sharp end (i.e. Unsafe Act) to blunt end (i. e. Organizational Influences). This means that the corresponding countermeasures should cover from front line staff to management. Thus, we managed to develop a better understanding on how to prevent similar errors or violations. The incident and near-miss have a lot of helpful information because it may show the actual and latent deficiencies of complex systems. We applied the HFACS into Fukushima Daiichi accident to better locate the causes related to both sharp and blunt ends of operation of NPP. In order to derive useful lessons from the accident analysis, the analyst should try to find the similarities not differences from the incident. It is imperative that whatever accident/incident analysis systems we use, we should fully utilize the disastrous Fukushima accident.

  12. Improvements in emergency management in nuclear power plants after the Fukushima accident: ORE, CAE and CAGE; Mejoras en la gestion de emergencias en centrales nucleares tras el accidente de Fukushima: ORE, CAE y CAGE

    Gimenez Gonzalez, S.; Sanchez Lombardia, A.; Martin Calvarro, J. M.; Calvin Cuartero, M.


    After Fukushima accident European NPP safety was checked by means of homogenous stress test promoted by European council. At Spain CSN issued Technical instructions to confirm safety NPP margins were appropriate . As a result of this assessment licensees promoted improving NPP safety by strengthen ERO; a new Support Emergency center (CAE) and construction of a new alternative management centre (CAGE) at each site. European countries have been improving and reinforced NPP safety in a similar way to Spain. (Author)

  13. Waste management in the post-accident phase; La gestion des dechets en phase post-accidentelle

    Merle-Szeremeta, A.; Bodenez, Ph. [Autorite de Surete Nucleaire (ASN), Dir. des Installations de Recherche et des Dechets, 75 - Paris (France)


    Post-accidental waste management is an essential step to carry out strategies of reduction of contamination of a contaminated land and to carry out strategies of population protection. Different actions that have to be carried out have been identified: waste collection, waste packaging, waste transport, stabilisation of putrefying waste, treatments to reduce the volume of the wastes, storage and waste disposal. The volumes of post-accidental wastes (mainly very low activity wastes) could be large, for the first scenarios studied by the CODIRPA. The different constraints lead to recommend the building of waste treatment and elimination facilities as near as possible from the places where the wastes are produced. Although wastes will have to be taken care of as soon as the transition phase starts, it will take months to build waste treatment facilities and disposal repositories. Therefore, it seems necessary-to build storage facilities from the beginning of the transition phase. Anyway, in order to manage the wastes as quickly as possible, some actions have to be set up anticipatory. The work of the group will be carried on in 2008 and 2009 to go into detail concerning regulatory, organizational, health, technical and financial aspects related to the different treatment and disposal solutions identified. (authors)

  14. Post-accident management: the point of view of the European Commission; La gestion post-accidentelle: le point de vue de la Commission Europeenne

    Janssens, A.; Herzeele, M.; Tanner, V. [Commission Europeenne, DG Energie et Transports, Bruxelles (Belgium)


    This paper will present documents and activities developed and implemented by the IAEA regarding remediation activities. It will be also described the lessons learned from two accidents as outcomes of two important conferences organized by IAEA. (authors)


    L. N. Trapeznikova


    Full Text Available The article briefly presents the experience of the radiation-hygienic monitoring system creation in the territory contaminated with the radionuclides due to the Chernobyl accident and application of the radiation hygienic monitoring data for the assessment of protective measures efficiency. Radiation situation data for the territory of the Bryansk region after 25 years of Chernobyl accident and dynamics of the population average annual effective exposure dose are being presented.

  16. Developing techniques for cause-responsibility analysis of occupational accidents.

    Jabbari, Mousa; Ghorbani, Roghayeh


    The aim of this study was to specify the causes of occupational accidents, determine social responsibility and the role of groups involved in work-related accidents. This study develops occupational accidents causes tree, occupational accidents responsibility tree, and occupational accidents component-responsibility analysis worksheet; based on these methods, it develops cause-responsibility analysis (CRA) techniques, and for testing them, analyzes 100 fatal/disabling occupational accidents in the construction setting that were randomly selected from all the work-related accidents in Tehran, Iran, over a 5-year period (2010-2014). The main result of this study involves two techniques for CRA: occupational accidents tree analysis (OATA) and occupational accidents components analysis (OACA), used in parallel for determination of responsible groups and responsibilities rate. From the results, we find that the management group of construction projects has 74.65% responsibility of work-related accidents. The developed techniques are purposeful for occupational accidents investigation/analysis, especially for the determination of detailed list of tasks, responsibilities, and their rates. Therefore, it is useful for preventing work-related accidents by focusing on the responsible group's duties.

  17. The use of safety management systems to avoid accidents at the work; El uso de sistemas de administracion de seguridad para evitar accidentes en el trabajo

    Rios Garcia, Jose Manuel [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico)


    In accordance with a study of the International Organization of Work (OIT), to the year around 250 million labor accidents occur, most of them in non-developed or developing countries, and a smaller percentage occurs in the industrialized countries. Analyzing the reason for that difference, it is possible to say that it is mainly due to the fact that in developed countries a greater conscience for the safety has been taken, as much for the personnel as for the facilities within the company, and have developed what is known as the management of the safety systems (SAS), where the safety task no longer corresponds only to the safety department but to the entire personnel, from the direction to the last one of the workers. [Spanish] De acuerdo con un estudio de la Organizacion Internacional del Trabajo (OIT), al ano se producen alrededor de 250 millones de accidentes laborales. La mayoria de ellos se presentan en los paises no desarrollados o en vias de desarrollo, y un porcentaje menor se da en los paises industrializados. Analizando el porque de esa diferencia, se puede decir que se debe principalmente a que en los paises desarrollados se ha tomado una mayor conciencia por la seguridad, tanto del personal como de las instalaciones, dentro de las empresas y han desarrollado lo que se conoce como los sistemas de administracion de seguridad (SAS), en donde la tarea de seguridad ya no solo corresponde al departamento de seguridad si no a todo el personal, desde la direccion hasta el ultimo de los trabajadores.

  18. From the Statistical Analysis of Coal Mine Accident Point of View Human Factors Management in Future%从煤矿事故现状分析统计看未来人因管理

    崔宁; 田蜜蕊; 李涛; 刘婷婷


    Along with the increasing of China's coal mines, the theme of coal mine safety production is increasingly promi-nent, frequent coal mine accidents, through nearly ten years in China coal mine accident statistics and analysis, found that the process of coal production in China, there is a huge potential safety hazard, in which people due to factors of coal mine accident is the most direct, the most important reason, therefore, In order to ensure the safety of coal mine production, and one should enhance the safety management for the coal industry, especially for the management of human factors.%通过对我国近十几年煤矿事故的统计与分析,发现在我国的煤矿生产过程,存在巨大的安全隐患,其中人因因素是造成煤矿事故最直接、最重要的原因,为了保证煤矿的安全生产,提出了要加大对煤炭行业的安全管理,特别是对于人因因素管理的建议。

  19. Laser accidents: Being Prepared

    Barat, K


    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.

  20. Improvement of severe accident analysis method for KSNP

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


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

  1. [Accidents with the "paraglider"].

    Lang, T H; Dengg, C; Gabl, M


    With a collective of 46 patients we show the details and kinds of accidents caused by paragliding. The base for the casuistry of the accidents was a questionnaire which was answered by most of the injured persons. These were questions about the theoretical and practical training, the course of the flight during the different phases, and the subjective point of view of the course of the accident. The patterns of the injuries showed a high incidence of injuries of the spinal column and high risks for the ankles. At the end, we give some advice how to prevent these accidents.

  2. Psychological distress of residents in Kawauchi village, Fukushima Prefecture after the accident at Fukushima Daiichi Nuclear Power Station: the Fukushima Health Management Survey

    Koji Yoshida


    Full Text Available Background To shed light on the mental health of evacuees after the accident at Fukushima Daiichi Nuclear Power Station (FDNPS, we evaluate the results of the Fukushima Health Management Survey (FHMS of the residents at Kawauchi village in Fukushima, which is located less than 30 km from the FDNPS. Methods We conducted the cross-sectional study within the framework of the FHMS. Exposure values were “anorexia,” “subjective feelings about health,” “feelings about sleep satisfaction,” and “bereavement caused by the disaster,” confounding variables were “age” and “sex,” and outcome variables were “K6 points.” We collected data from the FHMS, and employed the Kessler Psychological Distress Scale (K6 and the posttraumatic stress disorder (PTSD Checklist Stressor-Specific Version (PCL-S to carry out the research. A total of 13 or greater was the cut-off for identifying serious mental illness using the K6 scale. The study subjects included residents (n = 542 of over 30 years of age from Kawauchi village, and data were used from the period of January 1, 2012 to October 31, 2012. Results A total of 474 residents (87.5% scored less than 13 points in the K6 and 68 (12.6% scored 13 points or more. The proportion of elderly residents (over 65 years old among people with K6 score above the cut-off was higher than that among people with K6 score below the cut-off (44.1 vs 31.0%, p < 0.05. In addition, the proportion of residents with anorexia and mental illness among people with K6 score above the cut-off was higher than among people with K6 score below the cut-off (p < 0.001 and p < 0.05, respectively. The amount of residents who scored 44 points or more in the PCL-S among people with K6 score above the cut-off was also considerably higher than among people with K6 score below the cut-off (79.4 vs 12.9%, p < 0.001. Interestingly, the proportion of residents who scored more than among people with K6 score above the cut-off and the

  3. Comparison of childhood thyroid cancer prevalence among 3 areas based on external radiation dose after the Fukushima Daiichi nuclear power plant accident: The Fukushima health management survey.

    Ohira, Tetsuya; Takahashi, Hideto; Yasumura, Seiji; Ohtsuru, Akira; Midorikawa, Sanae; Suzuki, Satoru; Fukushima, Toshihiko; Shimura, Hiroki; Ishikawa, Tetsuo; Sakai, Akira; Yamashita, Shunichi; Tanigawa, Koichi; Ohto, Hitoshi; Abe, Masafumi; Suzuki, Shinichi


    The 2011 Great East Japan Earthquake led to a subsequent nuclear accident at the Fukushima Daiichi Nuclear Power Plant. In its wake, we sought to examine the association between external radiation dose and thyroid cancer in Fukushima Prefecture. We applied a cross-sectional study design with 300,476 participants aged 18 years and younger who underwent thyroid examinations between October 2011 and June 2015. Areas within Fukushima Prefecture were divided into three groups based on individual external doses (≥1% of 5 mSv, accident and thyroid examination was not associated with thyroid cancer prevalence. There were no significant associations between individual external doses and prevalence of thyroid cancer. External radiation dose was not associated with thyroid cancer prevalence among Fukushima children within the first 4 years after the nuclear accident.

  4. Accident investigation of construction sites in Qom city using Pareto chart (2009-2012

    M. H. Beheshti


    .Conclusions: Employing Pareto charts as a method for analyzing and identification of accident causes can have an effective role in the management of work-related accidents, proper allocation of funds and time.

  5. Communication and industrial accidents

    As, Sicco van


    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

  6. Accidents - personal factors

    Zaitsev, S.L.; Tsygankov, A.V.


    This paper evaluates influence of selected personal factors on accident rate in underground coal mines in the USSR. Investigations show that so-called organizational factors cause from 80 to 85% of all accidents. About 70% of the organizational factors is associated with social, personal and economic features of personnel. Selected results of the investigations carried out in Donbass mines are discussed. Causes of miner dissatisfaction are reviewed: 14% is caused by unsatisfactory working conditions, 21% by repeated machine failures, 16% by forced labor during days off, 14% by unsatisfactory material supply, 16% by hard physical labor, 19% by other reasons. About 25% of miners injured during work accidents are characterized as highly professionally qualified with automatic reactions, and about 41% by medium qualifications. About 60% of accidents is caused by miners with less than a 3 year period of service. About 15% of accidents occurs during the first month after a miner has returned from a leave. More than 30% of accidents occurs on the first work day after a day or days off. Distribution of accidents is also presented: 19% of accidents occurs during the first 2 hours of a shift, 36% from the second to the fourth hour, and 45% occurs after the fourth hour and before the shift ends.

  7. Accident investigation and analysis

    Kampen, J. van; Drupsteen, L.


    Many organisations and companies take extensive proactive measures to identify, evaluate and reduce occupational risks. However, despite these efforts things still go wrong and unintended events occur. After a major incident or accident, conducting an accident investigation is generally the next ste

  8. Passive Transfer of HIV-1 Antibodies and Drug Resistant Virus during a Health Care Worker Accident: Implications for HCW Post-Exposure Management

    Carlos Fernando De Oliveira


    Full Text Available Problem statement: We studied in detail a case in which a nurse caring for an HIV-infected child suffered a deep-laceration accident with contaminated blood. Approach: The patient had been treated with zidovudine (ZDV and the nurse became infected despite prophylactic use of ZDV initiated 2 h after the accident. A reactive anti-HIV-1/2 EIA and an indeterminate western blot (gp120/160 reactivity were obtained from the nurse on the day of the accident, suggesting pre-exposure infection. However, a negative western blot and positive DNA PCR were documented 10 days after the accident and seroconversion occurred an additional two weeks later. Results: Phylogenetic analyses of HIV-1 tat and C2-C4-gp120 env regions confirmed that the nurse infected by two different HIV-1 strains present in the child. Strains present in both subjects revealed multi-nucleoside resistant HIV-1. Dilutional serological studies using 10 HIV-infected patients’ sera demonstrated that passive seroreactivity could occur with infusion of less than 1 uL of blood when highly sensitive assays are employed. Conclusion: This is the first well-documented case of passive HIV antibody detection after a percutaneous exposure. Reactive baseline serology should not be assumed to represent prior infection nor exclude prophylaxis. Transmission of drug-resistant HIV-1 corroborates the medical history and supports use of drug history and resistance testing to guide antiretroviral prophylaxis.

  9. Persistence of airline accidents.

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


    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.

  10. Accidents with sulfuric acid

    Rajković Miloš B.


    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.

  11. Severe accident risks from external events

    Randall O Gauntt


    This paper reviews the early development of design requirements for seismic events in USA early developing nuclear electric generating fleet.Notable safety studies,including WASH-1400,Sandia Siting Study and the NUREG-1150 probabilistic risk study,are briefly reviewed in terms of their relevance to extreme accidents arising from seismic and other severe accident initiators.Specific characteristic about the nature of severe accidents in nuclear power plant (NPP) are reviewed along with present day state-of-art analysis methodologies (methods for estimation of leakages and consequences of releases (MELCOR) and MELCOR accident consequence code system (MACCS)) that are used to evaluate severe accidents and to optimize mitigative and protective actions against such accidents.It is the aim of this paper to make nuclear operating nations aware of the risks that accompany a much needed energy resource and to identify some of the tools,techniques and landmark safety studies that serve to make the technology safer and to maintain vigilance and adequate safety culture for the responsible management of this valuable but unforgiving technology.

  12. Accident Tolerant Fuel Analysis

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


    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

  13. 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


    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

  14. 46 CFR 122.208 - Accidents to machinery.


    ... 46 Shipping 4 2010-10-01 2010-10-01 false Accidents to machinery. 122.208 Section 122.208 Shipping... Voyage Records § 122.208 Accidents to machinery. The owner, managing operator, or master shall report damage to a boiler, unfired pressure vessel, or machinery that renders further use of the item...

  15. 46 CFR 185.208 - Accidents to machinery.


    ... 46 Shipping 7 2010-10-01 2010-10-01 false Accidents to machinery. 185.208 Section 185.208 Shipping...) OPERATIONS Marine Casualties and Voyage Records § 185.208 Accidents to machinery. The owner, managing operator, or master shall report damage to a boiler, unfired pressure vessel, or machinery that...

  16. APRI-6. Accident Phenomena of Risk Importance

    Garis, Ninos; Ljung, J (eds.) (Swedish Radiation Safety Authority, Stockholm (Sweden)); Agrenius, Lennart (ed.) (Agrenius Ingenjoersbyraa AB, Stockholm (Sweden))


    Since the early 1980s, nuclear power utilities in Sweden and the Swedish Radiation Safety Authority (SSM) collaborate on the research in severe reactor accidents. In the beginning focus was mostly on strengthening protection against environmental impacts after a severe reactor accident, for example by develop systems for the filtered relief of the reactor containment. Since the early 90s, this focus has shifted to the phenomenological issues of risk-dominant significance. During the years 2006-2008, the partnership continued in the research project APRI-6. The aim was to show whether the solutions adopted in the Swedish strategy for incident management provides adequate protection for the environment. This is done by studying important phenomena in the core melt estimating the amount of radioactivity that can be released to the atmosphere in a severe accident. To achieve these objectives the research has included monitoring of international research on severe accidents and evaluation of results and continued support for research of severe accidents at the Royal Inst. of Technology (KTH) and Chalmers University. The follow-up of international research has promoted the exchange of knowledge and experience and has given access to a wealth of information on various phenomena relevant to events in severe accidents. The continued support to KTH has provided increased knowledge about the possibility of cooling the molten core in the reactor tank and the processes associated with coolability in the confinement and about steam explosions. Support for Chalmers has increased knowledge of the accident chemistry, mainly the behavior of iodine and ruthenium in the containment after an accident.

  17. Occupational Accidents: A Perspective of Pakistan Construction Industry

    Tauha Hussain Ali


    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

  18. Development of Database for Accident Analysis in Indian Mines

    Tripathy, Debi Prasad; Guru Raghavendra Reddy, K.


    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.

  19. Development of Database for Accident Analysis in Indian Mines

    Tripathy, Debi Prasad; Guru Raghavendra Reddy, K.


    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.

  20. 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...

  1. Accident resistant transport container

    Andersen, John A.; Cole, James 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.

  2. Accidents with sulfuric acid

    Rajković Miloš B.


    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 eigh...




    Background: The Fukushima Pregnancy and Birth Survey was launched to monitor pregnant mothers’ health after the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Plant (NPP) accident. Several lines of investigations have indicated that a disaster impacts maternal mental health with childbirth. However, there is no research regarding mental health of mothers with fetal loss after a disaster. In this report, we focus on those women immediately after the Great East Japan Earthquake...

  4. Immediate mental consequences of the great east Japan earthquake and Fukushima nuclear power Plant accident on mothers experiencing miscarriage, abortion, and stillbirth: the Fukushima health management survey

    YOSHIDA-KOMIYA, HIROMI; Goto, Aya; Yasumura, Seiji; FUJIMORI, KEIYA; Abe, Masafumi


    Background: The Fukushima Pregnancy and Birth Survey was launched to monitor pregnant mothers' health after the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Plant (NPP) accident. Several lines of investigations have indicated that a disaster impacts maternal mental health with childbirth. However, there is no research regarding mental health of mothers with fetal loss after a disaster. In this report, we focus on those women immediately after the Great East Japan Earthquake...

  5. Development of a system of computer codes for severe accident analyses and its applications

    Chang, Soon Hong; Cheon, Moon Heon; Cho, Nam jin; No, Hui Cheon; Chang, Hyeon Seop; Moon, Sang Kee; Park, Seok Jeong; Chung, Jee Hwan [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)


    The objectives of this study is to develop a system of computer codes for postulated severe accident analyses in Nuclear Power Plants. This system of codes is necessary to conduct individual plant examination for domestic nuclear power plants. As a result of this study, one can conduct severe accident assessments more easily, and can extract the plant-specific vulnerabilities for severe accidents and at the same time the ideas for enhancing overall accident resistance. The scope and contents of this study are as follows : development of a system of computer codes for severe accident analyses, development of severe accident management strategy.

  6. Statistical analysis of water traffic accident and safety management for sand ship%砂石船舶水上交通事故统计分析及安全管理

    李文华; 马晓雪; 马来好; 陈海泉; 张银东; 乔卫亮


    对某水域2008-2012年上半年砂石船舶水上交通事故进行统计分析,探索砂石船舶水上交通事故的发生规律。结合对砂石船舶营运系统中船员、船舶、环境、管理和砂石五个方面的剖析,有针对性地提出相应的安全管理对策,为相关责任部门制订砂石船舶水上交通安全管理对策提供参考。%Based on the statistical analysis of the sand ship traffic accidents in some water areas from 2008 to the first half year of 2012 , the occurrence of traffic accidents for sand ship was explored , and combining with statistical analysis on fol-lowing five aspects , including crew , ship, environment , man-agement and sand which were in the operation of the ship sys-tems, the countermeasures for safety management were pro-posed,which can provide reference for the relevant responsible departments .

  7. 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)


    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

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

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


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

  9. Development of system of computer codes for severe accident analysis and its applications

    Jang, H. S.; Jeon, M. H.; Cho, N. J. and others [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)


    The objectives of this study is to develop a system of computer codes for postulated severe accident analyses in nuclear power plants. This system of codes is necessary to conduct Individual Plant Examination for domestic nuclear power plants. As a result of this study, one can conduct severe accident assessments more easily, and can extract the plant-specific vulnerabilities for severe accidents and at the same time the ideas for enhancing overall accident-resistance. Severe accident can be mitigated by the proper accident management strategies. Some operator action for mitigation can lead to more disastrous result and thus uncertain severe accident phenomena must be well recognized. There must be further research for development of severe accident management strategies utilizing existing plant resources as well as new design concepts.

  10. [Multiple injuries in mass accidents].

    Wondrák, E


    The treatment starts with reanimation, managing the shock, followed by life-saving surgery on the central nervous system, chest, abdomen, large blood vessels and the uropoietic system. From the very beginning the therapy should be conducted on an intradisciplinary basis, first with the anaesthesiologist, later with other specialists as required. Once the patient's life has been saved, treatment of eyes, hands and systematic attention to extremities should follow. Shock has to be managed within 24 hours. Luxations of large joints should be reposed on the date of injury, open fractures closed, all fractures immobilized in favourable position. No extension should be applied in patients suffering from brain injuries; fractures of the femur should be fixed surgically by a second team in the course of the neurosurgical operation. A stomatologist's assistance makes general anaesthesia possible even with fractures of the jaw. In mass accidents the therapeutic plan for the polytraumatized should be fixed on the following day. A mass accident involving 35 injured treated within two and a half hours demonstrates this procedure in 7 polytraumatized persons.

  11. Accidents in nuclear ships

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


    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).

  12. The rise of citizen competence: asset or handicap for the French authorities during post-accident management?; La montee en competence citoyenne, atout ou handicap pour les autorites francaises en cas de gestion post-accidentelle?

    Villers, A. [Association Environnement et Developpement Alternatif (EDA), 59 - Lille (France)


    EDA is a non-profit association of volunteer members aware of the limits of the planet's capacities and motivated to prepare a future based on sustainability and solidarity. The ability to plan in advance the measures to be taken in a post-accident situation, adapting them to the territory concerned and making full use of active and responsible involvement by local participants, is highly valuable. Naturally, this must not take precedence over all the preventive measures to ensure that an accident does not occur. We did not think that after 40 years of practical experience and after 20 years of observation of the seriousness of the consequence of Chernobyl we were so unprepared today. The CLIs (local information committees) attached to basic nuclear installations are indisputably the crucial links to be used to provide the necessary training of selected citizens to help manage the emergency phase and above all the post-accident phases, on condition that they receive financial resources commensurate with the challenges to be faced. It is also important to consider increasing the competence of citizens over the whole territory. Nothing can be achieved under satisfactory conditions if the citizens are not prepared well in advance: this must begin at school, so that the population knows how to behave in these situations. We appreciate being associated with the work of CODIRPA in 'calm' phases and we try to make an active contribution at our level. The accounts from Norway and Belarus are there to prevent us from forgetting that we are all concerned. From 2008 we hope to play a constructive and committed role in confronting the challenges to be faced and thank ASN for allowing us to take part in the work of CODIPPA. (author)

  13. Comparison of childhood thyroid cancer prevalence among 3 areas based on external radiation dose after the Fukushima Daiichi nuclear power plant accident: The Fukushima health management survey.

    Ohira, Tetsuya; Takahashi, Hideto; Yasumura, Seiji; Ohtsuru, Akira; Midorikawa, Sanae; Suzuki, Satoru; Fukushima, Toshihiko; Shimura, Hiroki; Ishikawa, Tetsuo; Sakai, Akira; Yamashita, Shunichi; Tanigawa, Koichi; Ohto, Hitoshi; Abe, Masafumi; Suzuki, Shinichi


    The 2011 Great East Japan Earthquake led to a subsequent nuclear accident at the Fukushima Daiichi Nuclear Power Plant. In its wake, we sought to examine the association between external radiation dose and thyroid cancer in Fukushima Prefecture. We applied a cross-sectional study design with 300,476 participants aged 18 years and younger who underwent thyroid examinations between October 2011 and June 2015. Areas within Fukushima Prefecture were divided into three groups based on individual external doses (≥1% of 5 mSv, <99% of 1 mSv/y, and the other). The odds ratios (ORs) and 95% confidence intervals of thyroid cancer for all areas, with the lowest dose area as reference, were calculated using logistic regression models adjusted for age and sex. Furthermore, the ORs of thyroid cancer for individual external doses of 1 mSv or more and 2 mSv or more, with the external dose less than 1 mSv as reference, were calculated. Prevalence of thyroid cancer for the location groups were 48/100,000 for the highest dose area, 36/100,000 for the middle dose area, and 41/100,000 for the lowest dose area. Compared with the lowest dose area, age-, and sex-adjusted ORs (95% confidence intervals) for the highest-dose and middle-dose areas were 1.49 (0.36-6.23) and 1.00 (0.67-1.50), respectively. The duration between accident and thyroid examination was not associated with thyroid cancer prevalence. There were no significant associations between individual external doses and prevalence of thyroid cancer. External radiation dose was not associated with thyroid cancer prevalence among Fukushima children within the first 4 years after the nuclear accident.

  14. Road Traffic Accident Analysis of Ajmer City Using Remote Sensing and GIS Technology

    Bhalla, P.; Tripathi, S.; Palria, S.


    With advancement in technology, new and sophisticated models of vehicle are available and their numbers are increasing day by day. A traffic accident has multi-facet characteristics associated with it. In India 93% of crashes occur due to Human induced factor (wholly or partly). For proper traffic accident analysis use of GIS technology has become an inevitable tool. The traditional accident database is a summary spreadsheet format using codes and mileposts to denote location, type and severity of accidents. Geo-referenced accident database is location-referenced. It incorporates a GIS graphical interface with the accident information to allow for query searches on various accident attributes. Ajmer city, headquarter of Ajmer district, Rajasthan has been selected as the study area. According to Police records, 1531 accidents occur during 2009-2013. Maximum accident occurs in 2009 and the maximum death in 2013. Cars, jeeps, auto, pickup and tempo are mostly responsible for accidents and that the occurrence of accidents is mostly concentrated between 4PM to 10PM. GIS has proved to be a good tool for analyzing multifaceted nature of accidents. While road safety is a critical issue, yet it is handled in an adhoc manner. This Study is a demonstration of application of GIS for developing an efficient database on road accidents taking Ajmer City as a study. If such type of database is developed for other cities, a proper analysis of accidents can be undertaken and suitable management strategies for traffic regulation can be successfully proposed.

  15. Management options for food production systems affected by a nuclear accident. Task 2 options for minimising the production of contaminated milk

    Smith, J G; Mercer, J A; Nisbet, A F; Wilkins, B T


    This report describes an evaluation of three possible means by which the production of waste milk could be reduced following a nuclear accident. The three options studied are the reduction of contaminated pasture in the diet, the drying off of lactating dairy cattle and the slaughter of dairy cattle. The practicability of each of these is considered using criteria such as technical feasibility, capacity, cost, impact and acceptability, where appropriate. In theory reductions in waste milk arisings can be achieved with each option, however, there are a number of limitations associated with their practical application.

  16. Societal and ethical aspects of the Fukushima accident.

    Oughton, Deborah


    The Fukushima Nuclear Power Station accident in Japan in 2011 was a poignant reminder that radioactive contamination of the environment has consequences that encompass far more than health risks from exposure to radiation. Both the accident and remediation measures have resulted in serious societal impacts and raise questions about the ethical aspects of risk management. This article presents a brief review of some of these issues and compares similarities and differences with the lessons learned from the 1986 Chernobyl Nuclear Power Plant accident in Ukraine. Integr Environ Assess Manag 2016;12:651-653. © 2016 SETAC.

  17. Accidents Preventive Practice for High-Rise Construction

    Goh Kai Chen


    Full Text Available The demand of high-rise projects continues to grow due to the reducing of usable land area in Klang Valley, Malaysia. The rapidly development of high-rise projects has leaded to the rise of fatalities and accidents. An accident that happened in a construction site can cause serious physical injury. The accidents such as people falling from height and struck by falling object were the most frequent accidents happened in Malaysian construction industry. The continuous growth of high-rise buildings indicates that there is a need of an effective safety and health management. Hence, this research aims to identify the causes of accidents and the ways to prevent accidents that occur at high-rise building construction site. Qualitative method was employed in this research. Interview surveying with safety officers who are involved in highrise building project in Kuala Lumpur were conducted in this research. Accidents were caused by man-made factors, environment factors or machinery factors. The accidents prevention methods were provide sufficient Personal Protective Equipment (PPE, have a good housekeeping, execute safety inspection, provide safety training and execute accidents investigation. In the meanwhile, interviewees have suggested the new prevention methods that were develop a proper site layout planning and de-merit and merit system among sub-contractors, suppliers and even employees regarding safety at workplace matters. This research helps in explaining the causes of accidents and identifying area where prevention action should be implemented, so that workers and top management will increase awareness in preventing site accidents.

  18. 从一起电梯险兆事故谈电梯的使用与管理%Talk about the Use and Management of Elevator from a Near Miss Accidents

    赖跃阳; 曾京军


    In recent years, the frequent fault and accident elevator by media reports cause the attention of the government, society, industry. Because of the misunderstanding of mass media and public knowledge of the structure of the elevator, the public cannot be objective and dispassionate to regard the elevator fault and elevator accident.This paper explains the importance of the use and management of elevator through the concrete case.%近年来,电梯频发的故障及事故经媒体的报道,引发了政府、社会、行业高度关注,由于媒体与社会公众对电梯结构知识的认识误区,导致社会公众不能客观、冷静看待电梯故障与电梯事故,文中通过具体案例说明电梯使用与管理的重要性。

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

    Jørgensen, Kirsten


    broadly. This review identifies gaps in the prevention of simple accidents, relating to safety barriers for risk control and the management processes that need to be in place to deliver those risk controls in a continuingly effective state. The article introduces the ‘‘INFO cards’’ as a tool...... for the systematic observation of hazard sources in order to ascertain whether safety barriers and management deliveries are present. Safety management and safety culture, together with the INFO cards are important factors in the prevention process. The conclusion is that we must look at safety as a part of being...... of prevention or safety methodologies and procedures established for major accidents are applicable to simple accidents. The article goes back to basics about accidents causes, to review the nature of successful prevention techniques and to analyze what have been constraints to getting this knowledge used more...

  20. The survey of occupational accidents in Yazd gas agency (2013

    Amir Hossein Khoshakhlagh


    Full Text Available Background: Existence of coordinated and professional safety system to prevent occurrence of accidents and potential hazards seem to be essential in installing networks of gas distribution projects. Objective: To survey work-related accidents and safety performance indices in project implementation unit of Yazd gas agency. Methods: This analytical study was conducted on 197 of workforce in Yazd gas agency in 2013 that were selected by census and they were male. Demographic and accident information were gathered using a self-made questionnaire and face- to- face interview, and required information obtained from dossier to determine the safety performance indicators. Safety performance indicators were calculated in separately of 13 types occupations in project implementation unit of gas agency and data were analyzed using T-test. Findings: The highest accident frequency and severity rate were related to digging occupation and then metal line welding. Consequences of accidents were cuts (%56.7 and soreness (%14.9. The causes of accidents were related to uselessness of personal protective equipment (%25.2 and lack of precision in the task (%19.3. The highest rate of accident was observed among the age group 20-29 years with work experience of 4-6 years. Conclusion: According to the findings of this study and the risk of gas processes, it seems to be necessary the implementation of integrated management systems and training of workers about safety rules to improve the safety culture and prevent accidents.

  1. Predicting Severity and Duration of Road Traffic Accident

    Fang Zong


    Full Text Available This paper presents a model system to predict severity and duration of traffic accidents by employing Ordered Probit model and Hazard model, respectively. The models are estimated using traffic accident data collected in Jilin province, China, in 2010. With the developed models, three severity indicators, namely, number of fatalities, number of injuries, and property damage, as well as accident duration, are predicted, and the important influences of related variables are identified. The results indicate that the goodness-of-fit of Ordered Probit model is higher than that of SVC model in severity modeling. In addition, accident severity is proven to be an important determinant of duration; that is, more fatalities and injuries in the accident lead to longer duration. Study results can be applied to predictions of accident severity and duration, which are two essential steps in accident management process. By recognizing those key influences, this study also provides suggestive results for government to take effective measures to reduce accident impacts and improve traffic safety.

  2. Chernobyl accident and its consequences

    Gittus, J.H.


    The paper concerns the Chernobyl reactor accident, with emphasis on the design of the RBMK reactor and nuclear safety. A description is given of the Chernobyl nuclear power plant, including details of the RMBK reactor and safety systems. Comments on the design of the RBMK by UK experts prior to the accident are summarized, along with post-accident design changes to improve RBMK safety. Events of the Chernobyl accident are described, as well as design deficiencies highlighted by the accident. Differences between the USSR and UK approaches to nuclear safety are commented on. Finally source terms, release periods and environmental consequences are briefly discussed.

  3. 日本福岛核泄漏事故对公共危机管理的启示%Enlightenment of Japanese Nuclear Accident in Fukushima for Public Crisis Management



    研究了福岛核泄漏事故中日本政府和企业在危机管理中出现的问题,分析归纳出其对公共危机管理的启示,认为普及危机意识、危机管理常态化、危机信息公开化、危机协理多元化、危机决策合理化是应对公共危机的重要手段。%Problems in crisis management taken by the Japanese government and enterprises during the Fukushima Daiichi nuclear leakage accident are researched and its revelation to public crisis management is analyzed and summarized indicating that the popularization of crisis consciousness, normality and publicity of management and information, as well as diversity of crisis assistance and rationalization of decision-making are major means to tackee with public crisis.

  4. Occupational accidents aboard merchant ships

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


    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...... rate of accidents than Danish citizens. Age was a major risk factor for accidents causing permanent disability. Change of ship and the first period aboard a particular ship were identified as risk factors. Walking from one place to another aboard the ship caused serious accidents. The most serious...

  5. An Evaluation Methodology Development and Application Process for Severe Accident Safety Issue Resolution

    Robert P. Martin


    Full Text Available A general evaluation methodology development and application process (EMDAP paradigm is described for the resolution of severe accident safety issues. For the broader objective of complete and comprehensive design validation, severe accident safety issues are resolved by demonstrating comprehensive severe-accident-related engineering through applicable testing programs, process studies demonstrating certain deterministic elements, probabilistic risk assessment, and severe accident management guidelines. The basic framework described in this paper extends the top-down, bottom-up strategy described in the U.S Nuclear Regulatory Commission Regulatory Guide 1.203 to severe accident evaluations addressing U.S. NRC expectation for plant design certification applications.

  6. [Drowning accidents in childhood].

    Krandick, G; Mantel, K


    This is a report on five boys aged between 1 and 5 years who, after prolonged submersion in cold water, were treated at our department. On being taken out of the water, all the patients were clinically dead. After 1- to 3-hour successful cardiopulmonary resuscitation, with a rectal temperature of about 27 degrees C, they were rewarmed at a rate of 1 degree/hour. Two patients died within a few hours after the accident. One patient survived with an apallic syndrome, 2 children survived with no sequelae. In the event of a water-related accident associated with hypothermia, we consider suitable resuscitation to have preference over rewarming measures. The most important treatment guidelines and prognostic factors are discussed.

  7. Dementia and Traffic Accidents

    Petersen, Jindong Ding; Siersma, Volkert; Nielsen, Connie Thurøe;


    BACKGROUND: As a consequence of a rapid growth of an ageing population, more people with dementia are expected on the roads. Little is known about whether these people are at increased risk of road traffic-related accidents. OBJECTIVE: Our study aims to investigate the risk of road traffic......-related accidents for people aged 65 years or older with a diagnosis of dementia in Denmark. METHODS: We will conduct a nationwide population-based cohort study consisting of Danish people aged 65 or older living in Denmark as of January 1, 2008. The cohort is followed for 7 years (2008-2014). Individual's personal...... data are available in Danish registers and can be linked using a unique personal identification number. A person is identified with dementia if the person meets at least one of the following criteria: (1) a diagnosis of the disease in the Danish National Patient Register or in the Danish Psychiatric...

  8. Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.

    Tentner, A. M.; Parma, E.; Wei, T.; Wigeland, R.; Nuclear Engineering Division; SNL; INL


    An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.

  9. Correspondence model of occupational accidents

    Juan C. Conte


    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. 道路交通事故致胸部损伤813例救治体会%Management of thoracic injuries in traffic accident: in 813 cases

    王建柏; 高劲谋; 胡平


    Objective To investigate the experience of management of thoracic injuries in traffic accident. Methods The clinical data of 813 cases of thoracic injuries ( AIS ≥ 3 ) in traffic accident treated in our unit from Jan. 2002 to Nov. 2009 were studied retrospectively. Results There were 813 cases in this study. Of which 239 cases were drivers, 308 pedestrians, 132 passengers, 129 motorcycle riders, 5 cyclists. There were 182 cases (22.4% ) of cardiac injury, 171 cases ( 21% ) of flail chest, 696 cases of polytrauma ( 85.6% ). And 449 cases presented with shock on admission (55.2% ). Thoracotomy was done in 55 cases (6.8% ) , unplanned re - thoracotomy in 4 cases. The overall mortality rate was 6.8%. Among them, 16 cases of thoracic injuries directly resulted from hemorrhagic shock and extensive cardiac and pulmonary contusion/laceration;19 cases died of secondary injury, the main complications included pulmonary infection and ARDS;the remaining cases died of associated injury.Conclusion Different type of the victims in traffic accident has its own injury mechanism. Strengthening the recognition of high incidence rate of blunt cardiac injury and attaching importance to the management of flail chest can improve the success rate of treatment of thoracic injuries in traffic accident.%目的 总结道路交通事故致胸部损伤的救治经验.方法 回顾分析2002年1月~2009年12月收治的道路交通事故致胸部损伤(AIS≥3分)病例813例的临床资料.结果 本组伤员中汽车驾驶员239例,行人308例,乘员132例,摩托车驾驶员129例,骑自行车人5 例.其中心脏损伤182例(22.4%),连枷胸171例(21%),多发伤696例(85.6%);入院时休克449例(55.2%).剖胸手术55例(6.8%),再剖胸4例.治愈760例(93.5%),死亡53例(6.5%),直接死于胸伤16例,主要为失血性休克和广泛的心脏、肺挫裂伤;死于继发性损伤19例,肺部感染及ARDS为主要并发症;其余死于合并伤.结论 交通事故致胸部损

  11. [Chernobyl nuclear power plant accident and Tokaimura criticality accident].

    Takada, Jun


    It is clear from inspection of historical incidents that the scale of disasters in a nuclear power plant accident is quite low level overwhelmingly compared with a nuclear explosion in nuclear war. Two cities of Hiroshima and Nagasaki were destroyed by nuclear blast with about 20 kt TNT equivalent and then approximately 100,000 people have died respectively. On the other hand, the number of acute death is 30 in the Chernobyl nuclear reactor accident. In this chapter, we review health hazards and doses in two historical nuclear incidents of Chernobyl and Tokaimura criticality accident and then understand the feature of the radiation accident in peaceful utilization of nuclear power.

  12. Hypoglycaemic complications with diabetes mellitus management: the predominant adverse drug reaction presenting to the Accident and Emergency Department of The University Hospital of the West Indies.

    Gossell-Williams, M; Williams-Johnson, J; Francis, L


    Evaluation of adverse drug reactions (ADRs) is important to the assessment of risk factors in an aim to ensure maximum benefits of drug therapy. This study was done to assess the types of ADRs presenting to the Accident and Emergency department (A&E) of the University Hospital of the West Indies. Admissions to the A&E associated with drugs were followed on a weekly basis for 19 weeks from October 2007 to February 2008 using the patient logbook. Medical records of patients with suspected ADRs were collected and evaluated by an Emergency Medicine Consultant of A & E to confirm the occurrence of ADRs and the suspected drug. Of the 8170 admissions to A&E, 48 (0.6%) were related to ADRs, with most occurring in females and the mean age (+/- standard error) was 58.9 (+/- 3.4) years. Drug induced hypoglycaemia accounted for 28 (56.3%) cases of ADRs and included mainly patients on insulin, with or without a sulphonylurea therapy. Most of these diabetic patients also had co-morbidities and were on multi-drug therapy (18). Allergic reactions accounted for 10 (21%) of the ADR outcomes. Other drugs accounting for ADRs included cardiovascular drugs (10.4%), analgesic/anti-inflammatory medications (8.3%), drugs acting on the central nervous system (8.3%) and anti-infectives (8.3%). It is concluded that drug-induced hypoglycaemia is the major ADR presenting to the A&E of the University Hospital of the West Indies; it is a preventable ADR and therefore further investigation should evaluate possible factors attributed to the occurrences.

  13. 职业性慢性1-溴丙烷中毒事故处置%Management of occupational chronic 1-Bromopropane poisoning accident

    林辉; 郭翔; 郭美琼; 戎伟丰; 黄永顺; 郑倩玲; 余新天; 黄振烈; 何坚


    目的:探讨职业性慢性1-溴丙烷(1-BP)中毒事故的职业病危害因素识别、事故处置和职业病诊断的思路。方法采用现场职业卫生调查和应急职业健康检查相结合的方法,对某五金真空镀膜企业发生的群体性职业性1-BP中毒事故进行职业病危害因素识别,对患者进行职业病诊断。结果该企业由于使用含1-BP 的清洗剂替代三氯乙烯进行超声波清洗作业,导致4名清洗房作业工人在接触1-BP 清洗剂11~13个月后,均出现周围神经系统损害。在企业已经对清洗房进行改造的前提下,事后应急检测结果显示:清洗房空气中1-BP 的短时间接触浓度为1038.800~1466.100 mg/m3,时间加权平均浓度为371.500~654.100 mg/m3;1-BP 清洗剂顶空气中1-BP 相对百分比为97.1%。清洗房作业工人班后尿中1-BP 水平为25.50~155.64μg/L。4例患者均被诊断为职业性慢性1-BP 中毒性周围神经病。结论快速识别中毒事故的职业病危害因素,早期明确职业病诊断,有利于做好1-BP 所致职业危害的防治工作。%Objective To discuss occupational hazard factor recognition,disposal method and diagnostic strategy for occupational chronic 1-Bromopropane (1-BP)poisoning accident.Methods By occupational health investigation and emergency occupational physical examination,the occupational hazard factors were identified in a mass 1-BP poisoning accident happened in a hardware vacuum coating enterprise.The patients were provided with occupational disease diagnosis.Results Four workers were detected suffering from peripheral nerve system damage after exposure to 1-BP for 11-13 months,due to using cleaning agent containing 1-BP instead of trichloroethylene for ultrasonic cleaning operation in an enterprise.After cleaning room was reformed,the emergent testing results showed that the short-time exposure concentration and time-weighted average concentration of 1-BP were 1

  14. Development of a national doctrine for the management of the post-accident phase of a radiological emergency situation; Construction d'une doctrine nationale pour la gestion de la phase post-accidentelle d'une situation d'urgence radiologique

    Niel, J.Ch.; Godet, J.L. [Autorite de Surete Nucleaire (ASN), 75 - Paris (France)


    For several years, public Authorities have defined an organization for the management of emergency situations arising from an accident occurring at a nuclear installation. So far, the management of the risk arising from the post accident phase was, in itself, not explored with the same care. What so ever, no format policy on which the action of public Authority could be based is today available. The nuclear safety Authority (ASN), in relation with the other concerned departments, is now in charge, according to the above mentioned directive, to prepare and implement the necessary provisions to respond to a post accident situation. In dune 2005, ASN established the steering committee for the management of post nuclear or radiological emergency situations (CODIRPA). The definition of a national policy related to the management of the radiological risk during a post event situation having to integrate various organization aspects as: lifting of protection emergency provisions and rehabilitation of buildings, life in contaminated rural territories, agriculture and water, dose and radiological consequences, sanitary surveillance of victims and populations, indemnification, waste management of contaminated crops and soils, organization of public Authorities. During the 2. phase of CODIRPA work (2008-2009), the first elements of policy will be consolidated and new scenarios will be studied (one worsened scenario and one scenario with alpha emitting radionuclide). in parallel, a procedure for local actor's consultation should be elaborated. (authors)

  15. Accounting for the cost of occupational accidents

    Rikhardsson, Pall M.


    consequences for the company. This, however, presents some challenges due to the current set up of many management accounting systems. The paper explores these issues in the context of the Systematic Accident Cost Analysis (SACA) project, which was carried out during 2001 by The Aarhus School of Business...... and PricewaterhouseCoopers Denmark with financial support from The Danish National Working Environment Authority. It focused on developing and testing a method for the evaluation of the occupational costs and how this might be linked to management accounting and control systems....

  16. US Department of Energy Chernobyl accident bibliography

    Kennedy, R A; Mahaffey, J A; Carr, F Jr


    This bibliography has been prepared by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Office of Health and Environmental Research to provide bibliographic information in a usable format for research studies relating to the Chernobyl nuclear accident that occurred in the Ukrainian Republic, USSR in 1986. This report is a product of the Chernobyl Database Management project. The purpose of this project is to produce and maintain an information system that is the official United States repository for information related to the accident. Two related products prepared for this project are the Chernobyl Bibliographic Search System (ChernoLit{trademark}) and the Chernobyl Radiological Measurements Information System (ChernoDat). This report supersedes the original release of Chernobyl Bibliography (Carr and Mahaffey, 1989). The original report included about 2200 references. Over 4500 references and an index of authors and editors are included in this report.

  17. Accident prevention in SME using ORM

    Jørgensen, Kirsten; Duijm, Nijs Jan; Troen, Hanne


    Risk perception in SMEs is normally low, and this is closely related to the fact that the chance of a mall enterprise experiencing a serious accident is very small compared to companies that employ a large workforce. This is a fact even though the SMEs together have a higher accident frequency...... compared with large enterprises. To reach the SMEs we must find a way of supporting them, because they normally have neither the time nor the resources to acquire the knowledge and awareness necessary for working with their own safety. The Occupational Risk Model (ORM) developed by the Dutch Workgroup...... safety in SMEs, as the project also focuses on management factors that can motivate the SMEs to increase their risk awareness and own initiatives. The project is now half way through the project period....

  18. Comparative Assessment Of Natural Gas Accident Risks

    Burgherr, P.; Hirschberg, S


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

  19. A feasibility study of the use of incidents and accidents reports to evaluate effects of team resource management in air traffic control

    Andersen, V.; Bove, T.


    Valuable improvements in performance have been obtained by 'Crew Resource Management' (CRM) courses performed in the domain of aviation related to the crew in a cockpit, and in the maritime domain related to the crew on the bridge of large ships. CRM courses are currently being adapted...

  20. Accidents on ships in the Danish International Ship register

    Ádám, Balázs; Rasmussen, Hanna Barbara

    Safety has been in the focus of seafaring during the past decade that observed a gradual reduction of reported work injuries in Danish ships. The injuries are, however, unevenly distributed in the maritime workforce, depending on various factors, the nationality of seafarer among them. The aim of...... the occurrence as well as the reporting of accidents is crucial to construct effective preventive measures for risk management....... to report accidents causing at least one day off work beyond the day of accident but the first source contains several accidents not fulfilling this criterion, too. Radio Medical is an independent service where all Danish ships may seek medical advice. The data sets were merged by identification number...... Western European seafarers compared to South East Asian (mostly Filipino) employees. The results highlight a favourable level of reported injuries in the Danish maritime sector but also point out detectable differences between groups of employees. The identification of factors that determine...

  1. Analysis of accidents with organic material in health workers.

    Vieira, Mariana; Padilha, Maria Itayra; Pinheiro, Regina Dal Castel


    This retrospective and descriptive study with a quantitative design aimed to evaluate occupational accidents with exposure to biological material, as well as the profile of workers, based on reporting forms sent to the Regional Reference Center of Occupational Health in Florianópolis/SC. Data collection was carried out through a survey of 118 reporting forms in 2007. Data were analyzed electronically. The occurrence of accidents was predominantly among nursing technicians, women and the mean age was 34.5 years. 73% of accidents involved percutaneous exposure, 78% had blood and fluid with blood, 44.91% resulted from invasive procedures. It was concluded that strategies to prevent the occurrence of accidents with biological material should include joint activities between workers and service management and should be directed at improving work conditions and organization.

  2. Key Parameters for Operator Diagnosis of BWR Plant Condition during a Severe Accident

    Clayton, Dwight A [ORNL; Poore III, Willis P [ORNL


    The objective of this research is to examine the key information needed from nuclear power plant instrumentation to guide severe accident management and mitigation for boiling water reactor (BWR) designs (specifically, a BWR/4-Mark I), estimate environmental conditions that the instrumentation will experience during a severe accident, and identify potential gaps in existing instrumentation that may require further research and development. This report notes the key parameters that instrumentation needs to measure to help operators respond to severe accidents. A follow-up report will assess severe accident environmental conditions as estimated by severe accident simulation model analysis for a specific US BWR/4-Mark I plant for those instrumentation systems considered most important for accident management purposes.

  3. Learning from incidents and accidents

    Drupsteen, L.; Kampen, J. van


    There are many different definitions for what constitutes an incident or an accident, however the focus is always on unintended and often unforeseen events that cause unintended consequences. This article is focused on the process of learning from incidents and accidents. The focus is on making sure

  4. Proceedings of the workshop on severe accident research held in Japan (SARJ-97)

    Sugimoto, Jun [ed.


    The Workshop on Severe Accident Research held in Japan (SARJ-97) was taken place at Pacifico Yokohama on October 6 - 8, 1997, and attended by 180 participants from 15 countries and one international organizations. The 59 papers, which cover wide areas of severe accident research both in experiments and analysis, such as in-vessel melt retention, fuel-coolant interaction, fission products behavior, structural integrity, containment behavior, computer simulations, and accident management, are indexed individually. (J.P.N.)

  5. Proceedings of the workshop on severe accident research held in Japan (SARJ-98)

    Sugimoto, Jun [ed.


    The Workshop on Severe Accident Research held in Japan (SARJ-98) was taken place at Hotel Lungwood on November 4-6, 1998, and attended by 181 participants from 13 countries. The 63 papers, which cover wide areas of severe accident research both in experiments and analyses, such as in-vessel melt retention, fuel-coolant interaction, fission products behavior, structural integrity, containment behavior, computer simulations, and accident management, are indexed individually. (J.P.N.)

  6. Industrial accidents triggered by lightning.

    Renni, Elisabetta; Krausmann, Elisabeth; Cozzani, Valerio


    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.

  7. Traffic Accidents on Slippery Roads

    Fonnesbech, J. K.; Bolet, Lars


    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...

  8. Nuclear safety in light water reactors severe accident phenomenology

    Sehgal, Bal Raj


    This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents to teach nuclear professionals

  9. Typologie des Accidents Cyclistes

    Amoros, Emmanuelle; BILLOT-GRASSET, Alice; Hours, Martine


    L'usage du vélo est en hausse en ville ; cette pratique est encouragée dans le cadre du développement durable et de la lutte contre la sédentarité. Pour accompagner cela, il faut réduire les risques d'accident, et pour ce faire, mieux les connaître. Nous utilisons le Registre des victimes de la circulation routière du Rhône, basé sur les services hospitaliers (dont les urgences) ; il est quasi-exhaustif : env. 1100 blessés à vélo/an versus 120 dans les données officielles. L'ensemble des cycl...

  10. Desktop Severe Accident Graphic Simulator Module for CANDU6 : PSAIS

    Park, S. Y.; Song, Y. M. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    The ISAAC ((Integrated Severe Accident Analysis Code for CANDU Plant) code is a system level computer code capable of performing integral analyses of potential severe accident progressions in nuclear power plants, whose main purpose is to support a Level 2 probabilistic safety assessment or severe accident management strategy developments. The code has the capability to predict a severe accident progression by modeling the CANDU6- specific systems and the expected physical phenomena based on the current understanding of the unique accident progressions. The code models the sequence of accident progressions from a core heatup, pressure tube/calandria tube rupture after an uncovery from inside and outside, a relocation of the damaged fuel to the bottom of the calandria, debris behavior in the calandria, corium quenching after a debris relocation from the calandria to the calandria vault and an erosion of the calandria vault concrete floor, a hydrogen burn, and a reactor building failure. Along with the thermal hydraulics, the fission product behavior is also considered in the primary system as well as in the reactor building.

  11. Chernobyl accident and its consequences

    Gittus, J.H.; Bonell, P.G.; Hicks, D.


    The USSR power reactor programme is first described. The reasons for the accident at the Chernobyl-4 RBMK nuclear reactor on 26 April 1986, the sequence of events that took place, and the immediate and long-term consequences are considered. A description of the RBMK-type reactors is given and the design changes resulting from the experience of the accident are explained. The source terms describing the details of the radioactivity release associated with the accident and the environmental consequences are covered in the last two sections of the report. Throughout the text comments referring to the UK Nuclear Installations Inspectorate Safety assessment principles have been inserted. (U.K.).

  12. [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


    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

  13. Prediction of hydrogen concentration in containment during severe accidents using fuzzy neural network

    Kim, Dong Yeong; Kim, Ju Hyun; Yoo, Kwae Hwan; Na, Man Gyun [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)


    Recently, severe accidents in nuclear power plants (NPPs) have become a global concern. The aim of this paper is to predict the hydrogen buildup within containment resulting from severe accidents. The prediction was based on NPPs of an optimized power reactor 1,000. The increase in the hydrogen concentration in severe accidents is one of the major factors that threaten the integrity of the containment. A method using a fuzzy neural network (FNN) was applied to predict the hydrogen concentration in the containment. The FNN model was developed and verified based on simulation data acquired by simulating MAAP4 code for optimized power reactor 1,000. The FNN model is expected to assist operators to prevent a hydrogen explosion in severe accident situations and manage the accident properly because they are able to predict the changes in the trend of hydrogen concentration at the beginning of real accidents by using the developed FNN model.

  14. Development of a parametric containment event tree model for a severe BWR accident

    Okkonen, T. [OTO-Consulting Ay, Helsinki (Finland)


    A containment event tree (CET) is built for analysis of severe accidents at the TVO boiling water reactor (BWR) units. Parametric models of severe accident progression and fission product behaviour are developed and integrated in order to construct a compact and self-contained Level 2 PSA model. The model can be easily updated to correspond to new research results. The analyses of the study are limited to severe accidents starting from full-power operation and leading to core melting, and are focused mainly on the use and effects of the dedicated severe accident management (SAM) systems. Severe accident progression from eight plant damage states (PDS), involving different pre-core-damage accident evolution, is examined, but the inclusion of their relative or absolute probabilities, by integration with Level 1, is deferred to integral safety assessments. (33 refs., 5 figs., 7 tabs.).

  15. 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...

  16. Nuclear fuel cycle facility accident analysis handbook

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


    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.

  17. Paragliding accidents in remote areas.

    Fasching, G; Schippinger, G; Pretscher, R


    Paragliding is an increasingly popular hobby, as people try to find new and more adventurous activities. However, there is an increased and inherent danger with this sport. For this reason, as well as the inexperience of many operators, injuries occur frequently. This retrospective study centers on the helicopter rescue of 70 individuals in paragliding accidents. All histories were examined, and 43 patients answered a questionnaire. Nineteen (42%) pilots were injured when taking off, 20 (44%) during the flight, and six (13%) when landing. Routine and experience did not affect the prevalence of accident. Analysis of the causes of accident revealed pilot errors in all but three cases. In 34 rescue operations a landing of the helicopter near the site of the accident was possible. Half of the patients had to be rescued by a cable winch or a long rope fixed to the helicopter. Seven (10%) of the pilots suffered multiple trauma, 38 (54%) had injuries of the lower extremities, and 32 (84%) of them sustained fractures. Injuries to the spine were diagnosed in 34 cases with a fracture rate of 85%. One patient had an incomplete paraplegia. Injuries to the head occurred in 17 patients. No paraglider pilot died. The average hospitalization was 22 days, and average time of working inability was 14 weeks. Fourteen (34%) patients suffered from a permanent damage to their nerves or joints. Forty-three percent of the paragliders continued their sport despite the accident; two of them had another accident. An improved training program is necessary to lower the incidence of paragliding accidents. Optimal equipment to reduce injuries in case of accidents is mandatory. The helicopter emergency physician must perform a careful examination, provide stabilization of airways and circulation, give analgesics, splint fractured extremities, and transport the victim on a vacuum mattress to the appropriate hospital.

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

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


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

  19. 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.

  20. Development of MAAP5.0.3 Spent Fuel Pool Model for Severe Accident Analysis

    Seo, Mi Ro [KHNP-CRI, Daejeon (Korea, Republic of)


    After the Fukushima accident, the severe accident phenomena in the Spent Fuel Pool (SFP) have been the great issues in the nuclear industry. Generally, during full power operation status, the decay heat of the spent fuel in the SFP is not high enough to cause the severe accident that is the say, the melting of fuel and fuel rack. In addition to this, the SFP of the PWR is not isolated within the containment like the SFP of the old BWR plant, there are so many possible measures to prevent and mitigate severe accidents in the SFP. On the other hand, in the low power shutdown status (fuel refueling), all the core is transferred into the SFP during the refueling period. At this period, if some accidents happen such as the loss of SFP cooling and the failure of SFP integrity then the accidents may be developed into severe accident because the decay heat is high enough. So, the analysis of severe accidents in the SFP during low power shutdown state is greatly affected to the establishment of the major strategies in the severe accident management guideline (SAMG). However, the status of the domestic technical background for those analyses is very weak. it is known that the decay heat of the spent fuel in the SFP is not high enough to cause the severe accident qualitatively. However, there are some possibilities that can cause the severe accidents in the SFP if the loss of SFP cooling and integrity happens simultaneously. The severe accident phenomena in SFP themselves are not much different from those in the containment. However, since the structure of SFP cannot be isolated during the accidents like the containment, the consequence can be extremely significant. So, in terms of the establishment of the severe accident management strategy, it is necessary that the quantitative analysis for the severe accident progression in the SFP should be performed. In this study, the general behavior which can be appeared during the severe accidents in the SFP was analyzed using the

  1. Aspects Concerning The Rules And The Investigation Of Traffic Accidents As Work Accidents

    Tarnu, Lucian Ioan


    When Romania joined the European Union, it was imposed that the Romanian legislation in the field of the security and health at work be in line with the European one. The concept of health as it is defined by the International Body of Health, refers to a good physical, mental and social condition. The improvement of the activity of preventing the traffic accidents as work accidents must have as basis the correct and accurate evaluation of risks of getting injured. The goal of the activity of prevention and protection is to ensure the best working conditions, the prevention of accidents and occupational diseases and the adjustment to the scientific and technological progress. In the road transport sector, as in any other sector, it is very important to pay attention to working conditions to ensure a workforce motivated and well qualified. Some features make it a more difficult sector risk management than other sectors. However, if one takes into account how it works in practice this sector and the characteristics of drivers and how they work routinely, risks, dangers and threats can be managed efficiently and with great success.

  2. 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

  3. Ranking of severe accident research priorities

    Schwinges, B. [Gesell Anlagen and Reaktorsicherheit GRS mbH, D-50667 Cologne (Germany); Journeau, C. [CEA Cadarache, DEN STRI LMA, F-13115 St Paul Les Durance (France); Haste, T. [Paul Scherrer Inst, NES LTH, OVGA 312, CH-5232 Villigen (Switzerland); Meyer, L.; Tromm, W. [Forschungszentrum Karlsruhe, D-76021 Karlsruhe (Germany); Trambauer, K. [GRS mbH, Forschungsgelande, D-85748 Garching (Germany)


    The objectives of the SARNET network are to define common research programmes in the field of severe accidents and to develop common computer tools and methodologies for safety assessment in this field. To reach these objectives, one of the work packages, named 'Severe Accident Research Priorities' (SARP), aimed at reviewing and reassessing the priorities of research issues as a basis to harmonize and to re-orient research programmes, to define new ones, and to close - if possible - resolved issues on a common basis. The work was performed in close collaboration with 8 participating institutions, led by GRS, representing technical safety organisations, industry and utilities (IRSN, CEA, EDF, FZK, GRS, KTH, TUS, VTT). This action made use notably of (1) the outcomes of the EURSAFE project in the 5. Framework Programme, i. e. the Phenomena Identification and Ranking Tables (PIRT) on severe accidents, (2) the results of the validation and benchmarking activities on ASTEC, (3) the results of reactor calculations carried out in the other SARNET tasks, and (4) the outcome of the research performed in the three thematic sub-domains of SARNET (corium, containment and source term). The main outcome of EURSAFE was a list of 21 topics which included recommendations for experimental programmes and code developments. This list formed the basis of the work in SARP. Also the methodology applied in EURSAFE to consider both the risk potential and the severe accident issues where large uncertainties still subsist was adopted. The analyses of the progress of research and development activities considered whether (1) any research issue was resolved due to reduction of uncertainties or gain of scientific insights, (2) any new issue had to be added to the list of needed research, (3) any new process or phenomenon had to be included in the general PIRT list taking into account the safety relevance and the lack of knowledge, and (4) any new accident management program has to be

  4. [Accidents of fulguration].

    Virenque, C; Laguerre, J


    Fulguration, first electric accident in which the man was a victim, is to day better known. A clap of thunder is decomposed in two elements: lightning, and thunder. Lightning is caused by an electrical discharge, either within a cloud, or between two clouds, or, above all, between a cloud and the surface of the ground. Experimental equipments owned by the French Electricity Company and by the Atomic Energy Commission, have allowed to photograph lightnings and to measure certain physical characteristics (Intensity variable between 25 to 100 kA, voltage variable between 20 to 1 000 kV). The frequency of storms was learned: the isokeraunic level, in France, is about 20, meaning that thunder is heard twenty days during one year. Man may be stricken by thunder by direct hit, by sudden bursting, by earth current, or through various conductors. The electric charge which reached him may go to the earth directly by contact with the ground or may dissipate in the air through a bony promontory (elbow). The total number of victims, "wounded" or deceased, is not now known by statistics. Death comes by insulation breakdown of one of several anatomic cephalic formations: skull, meninx, brain. Many various lesions may happen in survivors: loss of consciousness, more or less long, sensorial or motion deficiencies. All these signs are momentary and generally reversible. Besides one may observe much more intense lesions on the skin: burns and, over all, characteristic aborescence (skin effect by high frequency current). The heart is protected, contrarily to what happens with industrial electrocution. The curative treatment is merely symptomatic : reanimation, surgery for burns or associated traumatic lesions. A prevention is researched to help the lonely man, in the country or in the mountains in the houses (lightning conductor, Faraday cage), in vehicles (aircraft, cars, ships). The mysterious and unforseeable character of lightning still stays, leaving a door opened for numerous

  5. LPG储罐爆炸事故评价及安全管理研究进展%Research Progress of Explosion Accident Evaluation and Safety Management for LPG Tanks

    刘经纬; 赵斌


    LPG储罐的爆炸事故时有发生,一旦出现爆炸事故,将导致大量的人员伤亡和经济损失,因此,有必要对其事故原因进行分析,并且提出有效的应对措施。首先,讨论了LPG典型事故,并且对事故类型及事故后果进行了分析;其次,研究了LPG储罐爆炸评价方法;最后,讨论了LPG储罐安全防护措施研究进展。%The explosion accident of LPG tank happens all the time;once explosion accident of LPG tank happens, a large number of casualties and economic losses will be caused, therefore it is necessary to carry out accident analysis for LPG tank, and effective countermeasures should be put forward. Firstly, the classic accidents were discussed, and the accident type and results of LPG tank were analyzed. Secondly, the LPG tank explosion evaluation method was studied. Finally, the safety countermeasures of LPG tank were summarized.

  6. Radiation dose assessment of ACP hot cell in accident

    Kook, D. H.; Jeong, W. M.; Koo, J. H.; Jeo, I. J.; Lee, E. P.; Ryu, K. S. [KAERI, Taejon (Korea, Republic of)


    The Advanced spent fuel Condition in Process(ACP) is under development for the effective management of spent fuel which had been generated in nuclear plants. The ACP needs a hot cell where most operations will be performed. To give priority to the environments safety, radiation doses evaluations for the radioactive nuclides in accident cases were preliminarily performed with the meteorological data around facility site. Fire accident prevails over several accidnets. Internal Dose and External Dose evaluation according to short dispersion data for that case show a safe margin for regulation limits and SAR limit of IMEF where this facility will be constructed.

  7. Nuclear accident dosimetry intercomparison studies.

    Sims, C S


    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.

  8. Radioactive materials transport accident analysis

    McSweeney, T.I.; Maheras, S.J.; Ross, S.B. [Battelle Memorial Inst. (United States)


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

  9. Traffic dynamics around weaving section influenced by accident: Cellular automata approach

    Kong, Lin-Peng; Li, Xin-Gang; Lam, William H. K.


    The weaving section, as a typical bottleneck, is one source of vehicle conflicts and an accident-prone area. Traffic accident will block lanes and the road capacity will be reduced. Several models have been established to study the dynamics around traffic bottlenecks. However, little attention has been paid to study the complex traffic dynamics influenced by the combined effects of bottleneck and accident. This paper presents a cellular automaton model to characterize accident-induced traffic behavior around the weaving section. Some effective control measures are proposed and verified for traffic management under accident condition. The total flux as a function of inflow rates, the phase diagrams, the spatial-temporal diagrams, and the density and velocity profiles are presented to analyze the impact of accident. It was shown that the proposed control measures for weaving traffic can improve the capacity of weaving section under both normal and accident conditions; the accidents occurring on median lane in the weaving section are more inclined to cause traffic jam and reduce road capacity; the capacity of weaving section will be greatly reduced when the accident happens downstream the weaving section.

  10. An analysis on the severe accident progression with operator recovery actions

    Vo, T.H. [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejon 305-353 (Korea, Republic of); Korea University of Science and Technology (UST), 217 Gajeong-ro, Yuseong-gu, Daejeon 305-333 (Korea, Republic of); Song, J.H., E-mail: [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejon 305-353 (Korea, Republic of); Korea University of Science and Technology (UST), 217 Gajeong-ro, Yuseong-gu, Daejeon 305-333 (Korea, Republic of); Kim, T.W.; Kim, D.H. [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejon 305-353 (Korea, Republic of)


    Highlights: • Severe accident progression for the station blackout and SBLOCA accident. • Analyses on APR1400 using MELCOR. • Operator recovery actions for decay heat removal and inventory make up. • Determine the time allowed for the operator to prevent reactor vessel failure. • Insight for the operator recovery actions for the severe accident management. - Abstract: Analyses on the severe accident progressions for the station blackout (SBO) accident and small break LOCA (SBLOCA) initiated severe accident were performed for APR1400 by using MELCOR computer code. Operator recovery actions for decay heat removal and inventory make up using a depressurization system and safety injection pump were simulated in parallel with a simulation of the severe accident progression. Sensitivity studies on the operator actions were performed to investigate the changes in the timing of the reactor vessel failure and to determine the time allowed for the operator to prevent reactor vessel failure. Sensitivity analyses on the effect of major modeling parameters were performed additionally to quantify the uncertainties in timing. It is found that the operator has about 2 h for the recovery actions after the indication of core damage by the signal of core exit thermocouple (CET) for the SBLOCA initiated severe accident, while the operator has to take immediate actions after the indication of core damage by CET for the SBO accident.

  11. Importance of risk communication during and after a nuclear accident.

    Perko, Tanja


    Past nuclear accidents highlight communication as one of the most important challenges in emergency management. In the early phase, communication increases awareness and understanding of protective actions and improves the population response. In the medium and long term, risk communication can facilitate the remediation process and the return to normal life. Mass media play a central role in risk communication. The recent nuclear accident in Japan, as expected, induced massive media coverage. Media were employed to communicate with the public during the contamination phase, and they will play the same important role in the clean-up and recovery phases. However, media also have to fulfill the economic aspects of publishing or broadcasting, with the "bad news is good news" slogan that is a well-known phenomenon in journalism. This article addresses the main communication challenges and suggests possible risk communication approaches to adopt in the case of a nuclear accident.

  12. Accident Prevention Through Effective Safety Management.


    to a 1.4 percent savings on total job costs. This is a conservative figure and 3 some companies have done substantially better. Exxon Corporation ...three categories in order to establish a favorable atmosphere for safe construction. 4.1.1 Communicatine Safety Goals to Employees A chief executive may...CopisFoESSCCO, 3. :al comte Inspetion I-u,, ofmeigCopies to ECMt, JF arid Meeting Note: AN or1igiis go to the corporate loss-prevention end/or safety

  13. Accident Sequence Evaluation Program: Human reliability analysis procedure

    Swain, A.D.


    This document presents a shortened version of the procedure, models, and data for human reliability analysis (HRA) which are presented in the Handbook of Human Reliability Analysis With emphasis on Nuclear Power Plant Applications (NUREG/CR-1278, August 1983). This shortened version was prepared and tried out as part of the Accident Sequence Evaluation Program (ASEP) funded by the US Nuclear Regulatory Commission and managed by Sandia National Laboratories. The intent of this new HRA procedure, called the ''ASEP HRA Procedure,'' is to enable systems analysts, with minimal support from experts in human reliability analysis, to make estimates of human error probabilities and other human performance characteristics which are sufficiently accurate for many probabilistic risk assessments. The ASEP HRA Procedure consists of a Pre-Accident Screening HRA, a Pre-Accident Nominal HRA, a Post-Accident Screening HRA, and a Post-Accident Nominal HRA. The procedure in this document includes changes made after tryout and evaluation of the procedure in four nuclear power plants by four different systems analysts and related personnel, including human reliability specialists. The changes consist of some additional explanatory material (including examples), and more detailed definitions of some of the terms. 42 refs.

  14. The child accident repeater: a review.

    Jones, J G


    The child accident repeater is defined as one who has at least three accidents that come to medical attention within a year. The accident situation has features in common with those of the child who has a single accident through simple "bad luck", but other factors predispose him to repeated injury. In the child who has a susceptible personality, a tendency for accident repetition may be due to a breakdown in adjustment to a stressful environment. Prevention of repeat accidents should involve the usual measures considered appropriate for all children as well as an attempt to provide treatment of significant maladjustment and modification of a stressful environment.

  15. Fukushima accident study using MELCOR

    Randall O Gauntt


    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).

  16. Road characteristics and bicycle accidents.

    Nyberg, P; Björnstig, U; Bygren, L O


    In Umeå, Sweden, defects in the physical road surface contributed to nearly half of the single bicycle accidents. The total social cost of these injuries to people amount to at least SEK 20 million (SEK 60,000 or about USD 8,500 per accident), which corresponds to the estimated loss of "eight life equivalents a year". Improved winter maintenance seems to have the greatest injury prevention potential and would probably reduce the number of injuries considerably, whereas improved road quality and modification of kerbs would reduce the most severe injuries. A local traffic safety program should try to prevent road accidents instead of handling the consequences of them. In accordance with Parliament decisions on traffic we would like to see increased investment in measures favoring bicycle traffic, where cycling is seen as a solution, not as a problem.

  17. Bathtub immersion accidents involving children.

    Pearn, J; Nixon, J


    A review of 19 consecutive serious bathtub immersion accidents (11 survivals, 8 fatalities) is presented. In all instances, consciousness was lost in the water. Unlike other childhood accidents which usually show a male predominance, the sexes are equally affected. The modal age is 11 months. Six separate causes of bath drownings and near-drownings have been identified, and in 14 of the 19 accidents, two or more causes were operating concurrently. Median estimated immersion time for survivals was four minutes, and five minutes for fatalities. The median depth of water was eight inches. An 'at risk' profile for home bathtub drownings is presented; this includes the youngest or second youngest child of a large family, a family of grade 4 to 7 sociooccupational status (congalton) and a family in which routine is temporarily broken.

  18. Internal Accident Report on EDH

    SC Department


    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: 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.

  19. [Diagnosis and treatment of diving accidents. New German guidelines for diving accidents 2014-2017].

    Jüttner, B; Wölfel, C; Liedtke, H; Meyne, K; Werr, H; Bräuer, T; Kemmerer, M; Schmeißer, G; Piepho, T; Müller, O; Schöppenthau, H


    In 2015 the German Society for Diving and Hyperbaric Medicine (GTÜM) and the Swiss Underwater and Hyperbaric Medical Society (SUHMS) published the updated guidelines on diving accidents 2014-2017. These multidisciplinary guidelines were developed within a structured consensus process by members of the German Interdisciplinary Association for Intensive Care and Emergency Medicine (DIVI), the Sports Divers Association (VDST), the Naval Medical Institute (SchiffMedInst), the Social Accident Insurance Institution for the Building Trade (BG BAU), the Association of Hyperbaric Treatment Centers (VDD) and the Society of Occupational and Environmental Medicine (DGAUM). This consensus-based guidelines project (development grade S2k) with a representative group of developers was conducted by the Association of Scientific Medical Societies in Germany. It provides information and instructions according to up to date evidence to all divers and other lay persons for first aid recommendations to physician first responders and emergency physicians as well as paramedics and all physicians at therapeutic hyperbaric chambers for the diagnostics and treatment of diving accidents. To assist in implementing the guideline recommendations, this article summarizes the rationale, purpose and the following key action statements: on-site 100% oxygen first aid treatment, still patient positioning and fluid administration are recommended. Hyperbaric oxygen (HBO) recompression remains unchanged the established treatment in severe cases with no therapeutic alternatives. The basic treatment scheme recommended for diving accidents is hyperbaric oxygenation at 280 kPa. For quality management purposes there is a need in the future for a nationwide register of hyperbaric therapy.

  20. Traffic safety information in South Africa : how to improve the National Accident Register. Submitted to the National Department of Transport, Republic of South Africa and the Ministry of Transport, Public Works and Water Management, The Netherlands.

    Sluis, J. van der (ed.)


    This report describes a project that was carried out to investigate ways and means to improve the problems experienced with the South African National Accident Register (NAR) system, and to determine a long term strategy on road safety information in South Africa. Within the framework of the Road Sa

  1. Effect of In-Vessel Retention Strategies under Postulated SGTR Accidents of OPR1000

    Choi, Wonjun; Lee, Yongjae; Kim, Sung Joong [Hanyang University, Seoul (Korea, Republic of); Kim, Hwan-Yeol; Park, Rae-Joon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    environment though MSSV which is located on broken steam generator. (2) In Mitigation 1 case, no core degradation occurred and severe accident was terminated. Thus, recovery of feed water is a top priority of severe accident management in SGTR accident. In case of Mitigation 2, RPV failure was delayed up to 2.85 hours and fission product retained in containment building. Therefore, it could be a proper mitigation strategy, if none of safety feature such as AFW pump or HPSI pump is recovered. (3) Opening PORV of SDS which is mitigation action of Mitigation 2 case can increase containment pressure and temperature.

  2. How to reduce the number of accidents


    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 HSE Unit

  3. Railway-controller-perceived competence in incidents and accidents.

    Cheng, Yung-Hsiang; Tsai, Yu-Chun


    Railway controllers play a pivotal role in service recovery of normal rail system operations when incidents and accidents occur. Those in this position must have sufficient competence to overcome task difficulties caused by accident uncertainties. This study adopts Taiwan's railway system as a case study to diagnose railway-controller-perceived competence when facing diverse tasks during incidents and accidents that are derived from a proposed conceptual model. Railway-controller-perceived competence is measured using the Rasch model. Analytical results indicate that working with an external rescue agency handling a rescue operation, explanations to the public, and communication with an external rescue agency are considered the most troublesome tasks. Additionally, railway-controller-perceived competence differs based on the work experience. This information will prove useful for rail system operators and government regulators when designing and regulating railway controller competence management systems. STATEMENT OF RELEVANCE: This study presents a systematic approach for examining the gap between railway-controller-perceived competence and task difficulties associated with incidents and accidents. The relevance of findings encompasses the effects of transportation ergonomics and railway issues on the problem-solving competence and decision-making skills of railway controllers, and the competence management system.

  4. Catastrophe model of the accident process, safety climate, and anxiety.

    Guastello, Stephen J; Lynn, Mark


    This study aimed (a) to address the evidence for situational specificity in the connection between safety climate to occupational accidents, (b) to resolve similar issues between anxiety and accidents, (c) to expand and develop the concept of safety climate to include a wider range of organizational constructs, (d) to assess a cusp catastrophe model for occupational accidents where safety climate and anxiety are treated as bifurcation variables, and environ-mental hazards are asymmetry variables. Bifurcation, or trigger variables can have a positive or negative effect on outcomes, depending on the levels of asymmetry, or background variables. The participants were 1262 production employees of two steel manufacturing facilities who completed a survey that measured safety management, anxiety, subjective danger, dysregulation, stressors and hazards. Nonlinear regression analyses showed, for this industry, that the accident process was explained by a cusp catastrophe model in which safety management and anxiety were bifurcation variables, and hazards, age and experience were asymmetry variables. The accuracy of the cusp model (R2 = .72) exceeded that of the next best log-linear model (R2 = .08) composed from the same survey variables. The results are thought to generalize to any industry where serious injuries could occur, although situationally specific effects should be anticipated as well.

  5. Trismus: An unusual presentation following road accident

    Thakur Jagdeep


    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.

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

    Oppe, S.


    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

  7. Proceedings of the workshop on severe accident research, Japan (SARJ-99)

    Hashimoto, Kazuichiro [ed.


    The Workshop on Severe Accident Research, Japan (SARJ-99) was taken place at Hotel Lungwood on November 8-10, 1999, and attended by 156 participants from 12 countries. A total of 46 papers, which covered wide areas of severe accident research both in experiments and analyses, such as fuel/coolant interaction, accident analysis and modeling, in-vessel phenomena, accident management, fission product behavior, research reactors, ex-vessel phenomena, and structural integrity, were presented. The panel discussion titled 'Link of Severe Accident Research Results to Regulation: Current Status and Future Perspective' was successfully conducted, and the wide variety of opinions and views were exchanged among panelists and experts. (J.P.N.)

  8. Accidents at work and costs analysis: a field study in a large Italian company.

    Battaglia, Massimo; Frey, Marco; Passetti, Emilio


    Accidents at work are still a heavy burden in social and economic terms, and action to improve health and safety standards at work offers great potential gains not only to employers, but also to individuals and society as a whole. However, companies often are not interested to measure the costs of accidents even if cost information may facilitate preventive occupational health and safety management initiatives. The field study, carried out in a large Italian company, illustrates technical and organisational aspects associated with the implementation of an accident costs analysis tool. The results indicate that the implementation (and the use) of the tool requires a considerable commitment by the company, that accident costs analysis should serve to reinforce the importance of health and safety prevention and that the economic dimension of accidents is substantial. The study also suggests practical ways to facilitate the implementation and the moral acceptance of the accounting technology.

  9. Corporate Cost of Occupational Accidents

    Rikhardsson, Pall M.; Impgaard, M.


    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...

  10. New technology for accident prevention

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


    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.

  11. Work Accidents and Professional Diseases

    Doru Hauptmann


    Full Text Available The major accident is defined as “any event occurred, like an emission of dangerous materials or agents, which emerges from uncontrolled evolutions along the exploitation of any objective that leads to the immediate or delayed occurrence of serious dangers with impact over human health or over the environment, inside or outside the objective in which are involved one or more than one dangerous materials”.The dangerous phenomenon is a potential source of harms. In the ambit of industrial risks of accidental origins, this expression more frequently refers to physical phenomena like conflagrations, explosions, toxic gases dispersion, etc.Any accident scenario relates itself to the potential effects at the level of environmental “targets”. In the case of major accidents, we can distinguish the following categories of “targets”: human (employees of the objective, working or resident people in the nearby of the emplacement; the installation or equipments that may stay at the origin of the accidents (dangerous equipments; certain all-important equipments to ensure the safety level of the installation (critical security equipments: control rooms, civil fire brigade headquarters, etc; goods and structures situated in the installation’ environment (ground water, rivers, soil, flora, fauna.

  12. 48 CFR 836.513 - Accident prevention.


    ... 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....

  13. 48 CFR 1836.513 - Accident prevention.


    ... 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....

  14. 48 CFR 636.513 - Accident prevention.


    ... 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...

  15. 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.


    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 disc

  16. Analysing truck position data to study roundabout accident risk

    Kamla, Jwan Jameel Shekh Mohammed


    In order to reduce accident risk, highway authorities prioritise maintenance budgets partly based upon previous accident history. However, as accident rates have continued to fall in most contexts, this approach has become problematic as accident ‘black spots’ have been treated and the number of accidents at any individual site has fallen. Another way of identifying sites of higher accident risk might be to identify near-miss accidents (where an accident nearly happened, but was avoided), whi...

  17. Blaming Leaders for Organizational Accidents: Proxy Logic in Collective- versus Individual-Agency Cultures

    Zemba, Yuriko; Young, Maia J.; Morris, Michael W.


    The current research investigates whether observers blame leaders for organizational accidents even when these managers are known to be causally uninvolved. Past research finds that the public blames managers for organizational harm if the managers are perceived to have personally played a causal role. The present research argues that East Asian…

  18. Outline of the Desktop Severe Accident Graphic Simulator Module for OPR-1000

    Park, S. Y.; Ahn, K. I. [KAERI, Daejeon (Korea, Republic of)


    This paper introduce the desktop severe accident graphic simulator module (VMAAP) which is a window-based severe accident simulator using MAAP as its engine. The VMAAP is one of the submodules in SAMEX system (Severe Accident Management Support Expert System) which is a decision support system for use in a severe accident management following an incident at a nuclear power plant. The SAMEX system consists of four major modules as sub-systems: (a) Severe accident risk data base module (SARDB): stores the data of integrated severe accident analysis code results like MAAP and MELCOR for hundreds of high frequency scenarios for the reference plant; (b) Risk-informed severe accident risk data base management module (RI-SARD): provides a platform to identify the initiating event, determine plant status and equipment availability, diagnoses the status of the reactor core, reactor vessel and containment building, and predicts the plant behaviors; (c) Severe accident management simulator module (VMAAP): runs the MAAP4 code with user friendly graphic interface for input deck and output display; (d) On-line severe accident management guidance module (On-line SAMG); provides available accident management strategies with an electronic format. The role of VMAAP in SAMEX can be described as followings. SARDB contains the most of high frequency scenarios based on a level 2 probabilistic safety analysis. Therefore, there is good chance that a real accident sequence is similar to one of the data base cases. In such a case, RI-SARD can predict an accident progression by a scenario-base or symptom-base search depends on the available plant parameter information. Nevertheless, there still may be deviations or variations between the actual scenario and the data base scenario. The deviations can be decreased by using a real-time graphic accident simulator, VMAAP.. VMAAP is a MAAP4-based severe accident simulation model for OPR-1000 plant. It can simulate spectrum of physical processes

  19. Prevention of accidents in SME’s

    Jørgensen, Kirsten; Duijm, Nijs Jan; Troen, Hanne


    we developed a method to observe and document the activities and risks in small enterprises, on the basis of the Dutch study. The co-operation between the Dutch and Danish projects has resulted in a very useful web-based risk assessment tool, which towards June 2009 will be accessible in Dutch...... in a series of small enterprises covering observations of about 120 man-days. These observations demonstrated that maintaining barriers against accidents can only partly be managed by the employer. Especially in enterprises with employees normally working outside the establishment, the daily safety assessment....... The results of the Danish project is an application of the Dutch findings to describe what risks and safety barriers are most important for small enterprises in some industry sectors and jobs. Based on this knowledge, we can formulate requirements for, 1) what can and should the employer take care of; 2) what...

  20. Guidelines for accident prevention and emergency preparedness

    Fthenakis, V.M.; Morris, S.C.; Moskowitz, P.D.


    This report reviews recent developments in the guidelines on chemical accident prevention, risk assessment, and management of chemical emergencies, principally in the United States and Europe, and discusses aspects of their application to developing countries. Such guidelines are either in the form of laws or regulations promulgated by governments, or of recommendations from international, professional, or non governmental organizations. In many cases, these guidelines specify lists of materials of concern and methods for evaluating safe usage of these materials and recommend areas of responsibility for different organizations; procedures to be included in planning, evaluation, and response; and appropriate levels of training for different classes of workers. Guidelines frequently address the right of communities to be informed of potential hazards and address ways for them to participate in planning and decision making.

  1. [Hanggliding accidents. Distribution of injuries and accident analysis].

    Ballmer, F T; Jakob, R P


    Paragliding--a relatively new sport to Switzerland--brought 23 patients with 48 injuries (38% lower limb and 29% spinal) within a period of 8 months to the Inselspital University hospital in Berne. The aim of the study in characterizing these injuries is to formulate some guidelines towards prevention. With over 90% of accidents occurring at either take off or landing, emphasis on better training for the beginner is proposed with strict guidelines for the more experienced pilot flying in unfavourable conditions.

  2. 基于风险管理理论的煤矿事故研究:人因风险因素探讨∗%Research on coal mine accidents based on risk management theory:discussion on man-made risk factors

    桑志彪; 彭锟; 申霞; 贺山峰; 钱洪伟; 揣小明


    基于风险管理理论,探讨了造成煤矿事故的人因风险因素,认为人因风险因素具有不确定性、潜在性、环境驱使性和可恢复性4个特点,分别从心理、生理、素质、环境、文化、管理6个方面详细分析了人因风险因素的产生原因,以期为科学研究煤矿人因事故形成机理、减少煤矿安全事故的发生提供一定的理论基础。%Based on risk management theory,the man-made risk factors for accidents in coal mines were discussed.These factors are characterized with uncertainty,potentiality,environmental driving and recoverability.The causes for man-made risk factors were analyzed in detail from six respects,such as psychology,physiology,quality,environment,culture and management.It is respected that this study can provide a certain theoretical foundation for the scientific study on the forming mechanism of man-made risks and for the decrease of the safety accidents in coal mines.

  3. Exploratory analysis of Spanish energetic mining accidents.

    Sanmiquel, Lluís; Freijo, Modesto; Rossell, Josep M


    Using data on work accidents and annual mining statistics, the paper studies work-related accidents in the Spanish energetic mining sector in 1999-2008. The following 3 parameters are considered: age, experience and size of the mine (in number of workers) where the accident took place. The main objective of this paper is to show the relationship between different accident indicators: risk index (as an expression of the incidence), average duration index for the age and size of the mine variables (as a measure of the seriousness of an accident), and the gravity index for the various sizes of mines (which measures the seriousness of an accident, too). The conclusions of this study could be useful to develop suitable prevention policies that would contribute towards a decrease in work-related accidents in the Spanish energetic mining industry.

  4. Root causes and impacts of severe accidents at large nuclear power plants.

    Högberg, Lars


    The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long-lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities.

  5. Safety against releases in severe accidents. Final report

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


    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.

  6. SWR 1000 severe accident control through in-vessel melt retention by external RPV cooling

    Kolev, N.I. [Framatome Advanced Nuclear Power, NDSI, Erlangen (Germany)


    Framatome Advanced Nuclear Power is being designing a new generation NPP with boiling water reactor SWR1000. Besides of various of modern passive and active safety features the system is also designed for controlling of a postulated severe accident with extreme low probability of occurrence. This work presents the rationales behind the decision to select the external cooling as a safety management strategy during severe accident. Bounding scenery are analyzed regarding the core melting, melt-water interaction during relocation of the melt from the core region into the lower head and the external coolability of the lower head. The conclusion is reached that the external cooling for the SWR1000 is a valuable strategy for accident management during postulated severe accidents. (authors)

  7. Fatal motorcycle accidents and alcohol

    Larsen, C F; Hardt-Madsen, M


    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....

  8. Practical approaches in accident analysis

    Stock, M.

    An accident analysis technique based on successive application of structural response, explosion dynamics, gas cloud formation, and plant operation failure mode models is proposed. The method takes into account the nonideal explosion characteristic of a deflagration in the unconfined cloud. The resulting pressure wave differs significantly from a shock wave and the response of structures like lamp posts and walls can differ correspondingly. This gives a more realistic insight into explosion courses than a simple TNT-equivalent approach.

  9. [Multicenter paragliding accident study 1990].

    Lautenschlager, S; Karli, U; Matter, P


    During the period from 1.1.90 until 31.12.90, 86 injuries associated with paragliding were analyzed in a prospective study in 12 different Swiss hospitals with reference to causes, patterns, and frequencies. The injuries showed a mean score of over 2 and were classified as severe. Most frequent spine injuries (36%) and lesions of the lower extremity (35%) with a high risk of the ankles were diagnosed. One accident was fatal. 60% of the accidents happened during landing, 26% during launching and 14% during flight. Half of the pilots were affected during their primary training course. Most accidents were caused by inflight error of judgement--especially incorrect estimation of wind conditions--and further the choice of unfavourable landing sites. In contrast to previous injury-reports, only one equipment failure could be noted, but often the equipment was not corresponding with the experience and the weight of the pilot. To reduce the frequency of paragliding-injuries an accurate choice of equipment and an increased attention to environmental factors is mandatory. Furthermore an education-program regarding the attitude and intelligence of the pilot should be included in training courses.

  10. Medical consequences of Chernobyl accident

    Galstyan I.A.


    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.

  11. A System Supporting the Analysis of Motorway Traffic Accidents

    Davide Anghinolfi


    Full Text Available This work presents a business intelligence tool for monitoring traffic accidents on motorways and supporting decisions relevant to road safety. The system manages information on road characteristics, traffic accidents and traffic volumes and produces reports for monitoring the evolution of key performance indicators for road safety, supporting decisions on actions for risk mitigation and safety improvements for road users. The paper illustrates the different types of analyses performed by the system. Pattern based analysis is used to evaluate safety performance indicators for the road sections matching defined patterns. Two different road segmentation algorithms, used to identify the most critical road sections according to various severity indicators, are presented and discussed. Differential analysis compares the value of selected severity indicators before and after the implementation of an intervention on a road. Finally, a graphical user interface allows the accident locations to be visualized and accidents with specific characteristics to be highlighted. The system was evaluated on the data collected between 2009 and 2011 for the A15 motorway in Italy, connecting Parma to La Spezia.

  12. [Accidents in travellers - the hidden epidemic].

    Walz, Alexander; Hatz, Christoph


    The risk of malaria and other communicable diseases is well addressed in pre-travel advice. Accidents are usually less discussed. Thus, we aimed at assessing accident figures for the Swiss population, based on data of the register from 2004 to 2008 of the largest Swiss accident insurance organization (SUVA). More than 139'000 accidents over 5 years showed that 65 % of the accidents overseas are injuries, and 24 % are caused by poisoning or harm by cold, heat or air pressure. Most accidents happened during leisure activities or sports. More than one third of the non-lethal and more than 50 % of the fatal accidents happened in Asia. More than three-quarters of non-lethal accidents take place in people between 25 and 54 years. One out of 74 insured persons has an accident abroad per year. Despite of many analysis short-comings of the data set with regard to overseas travel, the figures document the underestimated burden of disease caused by accidents abroad and should affect the given pre-health advice.

  13. Accidente laboral: ACSOM una nueva orientación para gestión automática del riesgo Work accidents: ACSOM a new orientation for automatic risk management

    A. I. García Felipe


    Full Text Available Fundamento. Analizar la accidentalidad laboral en todo tipo de empresas, a través de los riesgos que la provocan, teniendo en cuenta que el objetivo final es establecer una clasificación de riesgos prioritarios. Esta información permite abordar las acciones preventivas oportunas sobre los riesgos más vulnerables. Material y Métodos. Se aplica un conjunto de técnicas estadístico-matemáticas, basadas fundamentalmente en contrastes estadísticos, a los accidentes laborales acaecidos durante tres años, en un organismo de investigación y desarrollo español (I+D con 8.780 trabajadores. Se utiliza como patrón de referencia en este estudio, para un análisis comparativo, el conjunto de accidentes en España durante un periodo de 11 años. Resultados. Tras la aplicación de la nueva metodología, los dos primeros riesgos que requieren acciones preventivas prioritarias son interacción con substancias agresivas y accidentes con maquinaria móvil. Si únicamente se hubieran considerado los dos riesgos con frecuencias más elevadas, sin tener en cuenta la vulnerabilidad de cada uno de ellos, los riesgos prioritarios hubieran sido sobreesfuerzos y caídas al mismo nivel. Conclusiones. El análisis proporciona una relación de los riesgos más vulnerables (puntos débiles, sobre los cuales actuar y de esta forma ser más efectivos a la hora de reducir la accidentalidad.Background. To analyse workplace accidents, by considering the risks that provoke such accidents, bearing in mind that the final aim is to establish a classification of priority risks. This information will make it possible to undertake the opportune preventive actions against the most vulnerable risks. Material and Methods. A set of statistical-mathematical techniques, essentially based on statistical contrasts, was applied to work accidents taking place during a three year period in a Spanish Research and Development (R+D organisation with 8,780 workers. The reference standard

  14. SARNET: Severe accident research network of excellence

    Albiol, T.; Van Dorsselaere, J. P. [IRSN, DPAM, F-13115 St Paul Les Durance (France); Chaumont, B. [IRSN, DSR, SAGR, F-92262 Fontenay Aux Roses (France); Haste, T. [Paul Scherrer Inst, NES, LTH, OVGA 312, CH-5232 Villigen (Switzerland); Journeau, Ch. [CEA Cadarache, DEN, STRI, LMA, F-13115 St Paul Les Durance (France); Meyer, L. [Forschungszentrum Karlsruhe, D-76021 Karlsruhe (Germany); Sehgal, Bal Raj [KTH, AlbaNova Univ Ctr, S-10691 Stockholm (Sweden); Schwinges, Bernd [Gesell Anlagen and Reaktorsicherheit GRS mbH, D-50667 Cologne (Germany); Beraha, D. [GRS mbH, Forschungsgelande, D-85748 Garching (Germany); Annunziato, A. [Commiss European Communities, JRC, IPSC, I-21020 Ispra, VA (Italy); Zeyen, R. [Commiss European Communities, JRC IE, IRSN DPAM DIR, F-13115 St Paul Les Durance (France)


    Fifty-one organisations network in SARNET (Severe Accident Research Network of Excellence) their research capacities in order to resolve the most important pending issues for enhancing, with regard to Severe Accidents (SA), the safety of existing and future Nuclear Power Plants (NPPs). This project. co-funded by the European Commission (EC) under the 6. Framework Programme, has been defined in order to optimise the use of the available means and to constitute sustainable research groups in the European Union. SARNET tackles the fragmentation that may exist between the different national R and D programmes, in defining common research programmes and developing common computer tools and methodologies for safety assessment. SARNET comprises most of the organisations involved in SA research in Europe, plus Canada. To reach these objectives, all the organisations networked in SARNET contributed to a joint Programme of Activities, which consisted of: Implementation of an advanced communication tool for accessing all project information, fostering exchange of information, and managing documents; Harmonization and re-orientation of the research programmes, and definition of new ones; Analysis of the experimental results provided by research programmes in order to elaborate a common understanding of relevant phenomena; Development of the ASTEC code (integral computer code used to predict the NPP behaviour during a postulated SA), which capitalizes in terms of physical models the knowledge produced within SARNET; Development of Scientific Databases in which all the results of research programmes are stored in a common format (DATANET); Development of a common methodology for Probabilistic Safety Assessment of NPPs; Development of short courses and writing a textbook on Severe Accidents for students and researchers; Promotion of personnel mobility amongst various European organisations. This paper presents the major achievements after four and a half years of operation of the

  15. Quantifying the risk of extreme aviation accidents

    Das, Kumer Pial; Dey, Asim Kumer


    Air travel is considered a safe means of transportation. But when aviation accidents do occur they often result in fatalities. Fortunately, the most extreme accidents occur rarely. However, 2014 was the deadliest year in the past decade causing 111 plane crashes, and among them worst four crashes cause 298, 239, 162 and 116 deaths. In this study, we want to assess the risk of the catastrophic aviation accidents by studying historical aviation accidents. Applying a generalized Pareto model we predict the maximum fatalities from an aviation accident in future. The fitted model is compared with some of its competitive models. The uncertainty in the inferences are quantified using simulated aviation accident series, generated by bootstrap resampling and Monte Carlo simulations.

  16. 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


    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.

  17. Injuries to pedestrians in road traffic accidents.

    Atkins, R. M.; Turner, W H; Duthie, R. B.; Wilde, B. R.


    Although there have been many reports on injuries to occupants of cars in road traffic accidents, there have been few prospective studies of injuries to pedestrians in such accidents. For this reason a two year prospective study of pedestrians in road traffic accidents in the Oxford region was carried out. The incidence of death in pedestrians was significantly higher than in car occupants or motorcyclists. The principal determinant of death was the weight of the vehicle concerned. The most c...

  18. Analysis on distribution of freeway accidents under various conditions in China

    Xiaofei Wang


    Full Text Available This study aims to provide a current survey on the situation of freeway accidents in China. The results show that the accident rate, death toll, injury toll, and direct loss of property are 3.2, 8.4, 7.2, and 24.3 times that of the average for an ordinary highway in China. Freeway accidents occur mainly in Southern (20.77% and Central (20.2% China. With detailed data from Guangdong Province, the number of accidents in freeways with 80 km/h design speed (29.58/km/103 pcu was more than three times that in freeways with design speed of 100 km/h (9.54/km/103 pcu and 120 km/h (9.42/km/103 pcu. The total accident rate increased monotonously with the decrease in horizontal radius. The results indicate that 54.54% (/km/103 pcu of accidents occurred on a steep slope (4%–5%, representing about 10 times that of 3%–4% slope and 20 times that of the less than 3% slope. Based on the data, the safety situation of China’s highway transportation is obviously grim, and improving freeway heavy traffic management in economically developed regions, strengthening the safeguarding of mountain freeways, applying small radius and large vertical grade with caution, and developing a monitoring system of tunnels and interchanges could be used as effective measures to prevent freeway accidents.


    S.O. Bader


    The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. The radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses. This subset of the total release fraction is referred to as the respirable release fraction. Potential accidents may involve waste forms that are characterized as either bare (unconfined) fuel assemblies or confined fuel assemblies. The confined CSNF assemblies at the MGR are contained in shipping casks, canisters, or disposal containers (waste packages). In contrast to the bare fuel assemblies, the container that confines the fuel assemblies has the potential of providing an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. However, this analysis will not take credit for this additional bamer and will establish only the total release fractions for bare unconfined CSNF assemblies, which may however be

  20. Methodological guidelines for developing accident modification functions

    Elvik, Rune


    This paper proposes methodological guidelines for developing accident modification functions. An accident modification function is a mathematical function describing systematic variation in the effects of road safety measures. The paper describes ten guidelines. An example is given of how to use...... limitations in developing accident modification functions are the small number of good evaluation studies and the often huge variation in estimates of effect. It is therefore still not possible to develop accident modification functions for very many road safety measures. © 2015 Elsevier Ltd. All rights...

  1. Systematics of Reconstructed Process Facility Criticality Accidents

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


    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.

  2. Aerospace Accident - Injury Autopsy Data System -

    Department of Transportation — The Aerospace Accident Injury Autopsy Database System will provide the Civil Aerospace Medical Institute (CAMI) Aerospace Medical Research Team (AMRT) the ability to...

  3. Occupational Accidents with Agricultural Machinery in Austria.

    Kogler, Robert; Quendler, Elisabeth; Boxberger, Josef


    The number of recognized accidents with fatalities during agricultural and forestry work, despite better technology and coordinated prevention and trainings, is still very high in Austria. The accident scenarios in which people are injured are very different on farms. The common causes of accidents in agriculture and forestry are the loss of control of machine, means of transport or handling equipment, hand-held tool, and object or animal, followed by slipping, stumbling and falling, breakage, bursting, splitting, slipping, fall, and collapse of material agent. In the literature, a number of studies of general (machine- and animal-related accidents) and specific (machine-related accidents) agricultural and forestry accident situations can be found that refer to different databases. From the database Data of the Austrian Workers Compensation Board (AUVA) about occupational accidents with different agricultural machinery over the period 2008-2010 in Austria, main characteristics of the accident, the victim, and the employer as well as variables on causes and circumstances by frequency and contexts of parameters were statistically analyzed by employing the chi-square test and odds ratio. The aim of the study was to determine the information content and quality of the European Statistics on Accidents at Work (ESAW) variables to evaluate safety gaps and risks as well as the accidental man-machine interaction.

  4. On severe accident hydrogen behaviour in Loviisa

    Okkonen, T. [OTO-Consulting Ay, Helsinki (Finland)


    This study is related to the hydrogen management strategy of the Loviisa ice-condenser containments. A synthetic survey is conducted of the various parts of the subject by using compact `back-of-the-envelope` analysis methods. The analysed cases are consistent with the principal hydrogen management approaches proposed by the utility Imatran Voima Oy (IVO). The study begins by introduction of the Loviisa plant features and various severe accident types. Hydrogen generation characteristics are analysed mainly for the core degradation phase, but the hydrogen sources from molten fuel-coolant interactions and reflooding of a degraded core are discussed, as well. The hydrogen generation and release rates are compared with the overall gas convection and mixing conditions in order to estimate hydrogen concentrations in the containment. The natural convection currents are examined also from the scaling point of view, concerning the scaled-down VICTORIA tests of IVO. Finally, the potential for large deflagration loadings or local detonations is examined for the Loviisa containments. The study is concluded by preliminary subjective judgments about the most critical factors of the Loviisa hydrogen problematics and about any issues that may require additional confirmative research. (orig.) (47 refs., 4 figs., 24 tabs.).

  5. HTGR severe accident sequence analysis

    Harrington, R.M.; Ball, S.J.; Kornegay, F.C.


    Thermal-hydraulic, fission product transport, and atmospheric dispersion calculations are presented for hypothetical severe accident release paths at the Fort St. Vrain (FSV) high temperature gas cooled reactor (HTGR). Off-site radiation exposures are calculated for assumed release of 100% of the 24 hour post-shutdown core xenon and krypton inventory and 5.5% of the iodine inventory. The results show conditions under which dose avoidance measures would be desirable and demonstrate the importance of specific release characteristics such as effective release height. 7 tables.

  6. Interactions of severe accident research and regulatory positions (ISARRP)

    Sehgal, B.R. (comp.) [Royal Inst. of Tech., Stockholm (Sweden). Nuclear Power Safety


    The work Programme of the ISARRP Project was divided into several work packages. The work was conducted in the form of presentations and discussions, held during several meetings whose character was that of workshops. Short reports were prepared by the partners assigned to each task. Work Package 1: Critical review of the SA phenomenological research. The objective of this work package was to consider the progress made world-wide in research on the resolution of the outstanding phenomenological issues posed by severe accidents. Work Package 2: Relevance of severe accident research to SAMG requirements and implementation. The objective of this work package was to relate the progress made in the resolution of the SA issues to the practical matter of what results are required or have been used for the management of severe accidents. Clearly, the SAMG is the most important avenue employed by the regulatory organizations to assure themselves of the safe (from public perspective) performance of a nuclear plant in a postulated severe accident event. Work Package 3: Relevance of severe accident research to PSA and the risk informed regulatory approach. The objectives of this work package is to relate the results obtained by the severe accident research to the requirements of a PSA and of the new trend of employing the risk informed approach in promulgating regulations. Clearly a PSA identifies vulnerabilities in the knowledge base, however, their importance is decidedly plant specific. Nevertheless the uncertainties in the phenomenology or in resolution of issues lead to uncertainties in the PSA conclusions and in the adoption of the risk informed approach. Work Package 4: Questionnaire and the evaluation of responses to the questions. The purpose of this work package is to solicit the views of the regulatory organizations towards the results of the SA research and the benefits they have derived from it in terms of regulatory actions, or in the confidence they have gained

  7. Speed Spatial Distribution Models for Traffic Accident Section of Freeway Based on Computer Simulation

    Decai Li; Jiangwei Chu; Wenhui Zhang; Xiaojuan Wang; Guosheng Zhang


    Simulation models for accident section on freeway are built in microscopic traffic flow simulation environment. In these models involving 2⁃lane, 3⁃lane and 4⁃lane freeway, one detector is set every 10 m to measure section running speed. According to the simulation results, speed spatial distribution curves for traffic accident section on freeway are drawn which help to determine dangerous sections on upstream of accident section. Furthermore, the speed spatial distribution models are obtained for every speed distribution curve. The results provide theoretical basis for determination on temporal and spatial influence ranges of traffic accident and offer reference to formulation of speed limit scheme and other management measures.

  8. 某深基坑降水方案及涌水事故处理%Design of Ground Water Lowering Scheme and Management of Water Inrush Accident in a Deep Foundation Pit



    详细说明了武汉地区某车站的降水及防水设计,并就施工过程中遇到的涌水事件,对设计方案进行补充和修正,对今后此种地质条件下深基坑工程的降水防水设计有良好的借鉴作用。%The design of ground water lowering and waterproofing scheme of a station pit in Wuhan is described in de -tail.A water inrush accident in the construction process is analyzed and the design scheme is accordingly amended and supplemented , which could be useful experience for the design of water lowering and waterproofing scheme of deep foun -dation pits with similar geological conditions .

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

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


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

  10. Radiological accidents balance in medicine; Bilan des accidents radiologiques en medecine

    Nenot, J.C.


    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.

  11. Squeal Those Tires! Automobile-Accident Reconstruction.

    Caples, Linda Griffin


    Methods use to reconstruct traffic accidents provide settings for real life applications for students in precalculus, mathematical analysis, or trigonometry. Described is the investigation of an accident in conjunction with the local Highway Patrol Academy integrating physics, vector, and trigonometry. Class findings were compared with those of…

  12. 48 CFR 36.513 - Accident prevention.


    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Accident prevention. 36.513 Section 36.513 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION SPECIAL... prevention. (a) The contracting officer shall insert the clause at 52.236-13, Accident Prevention,...

  13. Global estimates of fatal occupational accidents.

    Takala, J


    Data on occupational accidents are not available from all countries in the world. Furthermore, underreporting, limited coverage by reporting and compensation schemes, and non-harmonized accident recording and notification systems undermine efforts to obtain worldwide information on occupational accidents. This paper presents a method and new estimated global figures of fatal accidents at work by region. The fatal occupational accident rates reported to the International Labour Office are extended to the total employed workforce in countries and regions. For areas not covered by the reported information, rates from other countries that have similar or comparable conditions are applied. In 1994, an average estimated fatal occupational accident rate in the whole world was 14.0 per 100,000 workers, and the total estimated number of fatal occupational accidents was 335,000. The rates are different for individual countries and regions and for separate branches of economic activity. In conclusion, fatal occupational accident figures are higher than previously estimated. The new estimates can be gradually improved by obtaining and adding data from countries where information is not yet available. Sectoral estimates for at least key economic branches in individual countries would further increase the accuracy.

  14. Occupational blood exposure accidents in the Netherlands.

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


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

  15. Accidents of bus drivers : an epidemiological approach

    M.L.I. Pokorny (Mirko); D.H.J. Blom (Dick)


    textabstractIn the history of accident research much emphasis has been laid on general statistics, different types of case studies concentrating on various personal factor-s, circumstantial influences etc. Often, in certain waves, the unequal initial liability theory (the accident proneness concept;

  16. An introduction to serious nuclear accident chemistry

    Mark Russell St. John Foreman


    A review of the chemistry occurring inside a nuclear power plant during a serious reactor accident is presented. This includes some aspects of the behavior of nuclear fuel, its cladding, cesium and iodine. This review concentrates on the chemistry of an accident in a water-cooled reactor loaded with uranium dioxide or mixed metal oxide fuel.

  17. Fatal traffic accidents and forensic medicine

    Kazuhiko Kibayashi


    Full Text Available In the event of a traffic accident fatality, the death is reported as an “unusual death,” an inquest is conducted, and, if necessary, a forensic autopsy is performed to prove any causal relationship between the accident and the death, identify the vehicle at fault, and determine the cause of the accident. A forensic autopsy of a traffic accident fatality needs to both determine the cause of death and identify the mechanism of injury, an analytical task that requires observation of three major traffic accident factors: the body, the vehicles involved, and the scene of the accident. Also crucial to determining the cause of death is the process of looking into whether the people involved in the accident had any diseases that might affect their driving performance or were under the influence of alcohol or drugs. In order to reduce the number of people killed in traffic accidents, it will be important to promote joint research uniting forensic medicine, clinical medicine, automotive engineering, and road engineering, take measures to limit the impact of inebriated pedestrians and pedestrians suffering from dementia, and ensure proper screening of alcohol and illegal drug consumption in drivers.

  18. Review of Severe Accident Phenomena in LWR and Related Severe Accident Analysis Codes

    Muhammad Hashim


    Full Text Available Firstly, importance of severe accident provision is highlighted in view of Fukushima Daiichi accident. Then, extensive review of the past researches on severe accident phenomena in LWR is presented within this study. Various complexes, physicochemical and radiological phenomena take place during various stages of the severe accidents of Light Water Reactor (LWR plants. The review deals with progression of the severe accidents phenomena by dividing into core degradation phenomena in reactor vessel and post core melt phenomena in the containment. The development of various computer codes to analyze these severe accidents phenomena is also summarized in the review. Lastly, the need of international activity is stressed to assemble various severe accidents related knowledge systematically from research organs and compile them on the open knowledge base via the internet to be available worldwide.

  19. [Clinical examinations for the traffic accident patients].

    Hitosugi, Masahito


    Traffic accident is a leading cause of unintentional death and about six-thousands annually died in Japan. As about one-million of persons suffer from traffic injuries, most of them seek medical attention. Therefore, medical staffs have to find the injuries accurately and treat immediately. Furthermore, the cause of accident should also be considered; why the accident was occurred, human error of the driver? To solve these problems, clinical examinations were needed. Medical staffs have to understand the characteristics of the traffic injuries: severe and multiple blunt injuries, popular injuries can be estimated with considering the pattern of the accident. Because some of the accidents are occurred when the driver is under the influence of alcohol and other drugs, screening of these subjects should be performed. Because the public is largely unaware of the preventable nature of traffic injuries, in addition to diagnose and treat accurately, we medical staffs have to attend on the primary prevention of the traffic injuries.

  20. Commercial SNF Accident Release Fractions

    J. Schulz


    The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the

  1. Risk communication in the case of the Fukushima accident: Impact of communication and lessons to be learned.

    Perko, Tanja


    Risk communication about the Fukushima Daiichi nuclear power plant accident in 2011 was often not transparent, timely, clear, nor factually correct. However, lessons related to risk communication have been identified and some of them are already addressed in national and international communication programmes and strategies. The Fukushima accident may be seen as a practice scenario for risk communication with important lessons to be learned. As a result of risk communication failures during the accident, the world is now better prepared for communication related to nuclear emergencies than it was 5 years ago The present study discusses the impact of communication, as applied during the Fukushima accident, and the main lessons learned. It then identifies pathways for transparent, timely, clear and factually correct communication to be developed, practiced and applied in nuclear emergency communication before, during, and after nuclear accidents. Integr Environ Assess Manag 2016;12:683-686. © 2016 SETAC.

  2. On Traffic Accident Characteristic Analysis and Management Basing on the Equivalent death tolls and injured People%基于当量死亡人数的群死群伤交通事故的特点分析及治理



    以一次发生10人死亡以上特大道路交通事故为研究对象,以事故当量死亡人数为基础,拟合了2004-2010年事故的数学模型,指出其发展变化与总体形势高度正相关。2007-2010年间,3月与8月、16日与7日、昼间12小时,西南地区、二级公路与高速公路、平直路段,营运公司、客运车辆、2年以下及10-12年驾龄的驾驶人,发生或引发的事故损害后果更为严重。2009-2010年,因超速和超载等14种直接原因而发生,其深层次的间接原因中以运输企业安全责任制不到位更为突出。明确了科学合理地制定防治规划、强化路面执法管理、完善道路及交通安全设施、落实交通安全责任倒查制等治理措施的具体要求。%Taking the serious road traffic accidents with more than 10 deaths as the research objects, basing on the accident death tolls, we have made the teaching model of 2004-2010 years accident, pointing out that the changes and general tendency are in a highly positive correlation. During 2007-2010, 16th or 17th of March and August, 12 hours a day, in the southwest area, on the grade II highway and expressway, in the straight section, some travel companies, passenger vehicles and the driver with 2-year or 10-12 year driving experience would meet with accident damage easily with more serious consequences. During 2009 and 2010, 14 direct causes including over-speed and overload directly lead the occurrence of the accident. The deeper and indirect reason lies in the safety transportation responsibility of companies. This paper clearly suggests some specific requirements of governance measures including the scientific and reasonable development planning, the strengthening the control management of pavement law enforcement, the improving the road and traffic safety facilities, the implementing the traffic safety duty mechanism etc.

  3. NASA Accident Precursor Analysis Handbook, Version 1.0

    Groen, Frank; Everett, Chris; Hall, Anthony; Insley, Scott


    Catastrophic accidents are usually preceded by precursory events that, although observable, are not recognized as harbingers of a tragedy until after the fact. In the nuclear industry, the Three Mile Island accident was preceded by at least two events portending the potential for severe consequences from an underappreciated causal mechanism. Anomalies whose failure mechanisms were integral to the losses of Space Transportation Systems (STS) Challenger and Columbia had been occurring within the STS fleet prior to those accidents. Both the Rogers Commission Report and the Columbia Accident Investigation Board report found that processes in place at the time did not respond to the prior anomalies in a way that shed light on their true risk implications. This includes the concern that, in the words of the NASA Aerospace Safety Advisory Panel (ASAP), "no process addresses the need to update a hazard analysis when anomalies occur" At a broader level, the ASAP noted in 2007 that NASA "could better gauge the likelihood of losses by developing leading indicators, rather than continue to depend on lagging indicators". These observations suggest a need to revalidate prior assumptions and conclusions of existing safety (and reliability) analyses, as well as to consider the potential for previously unrecognized accident scenarios, when unexpected or otherwise undesired behaviors of the system are observed. This need is also discussed in NASA's system safety handbook, which advocates a view of safety assurance as driving a program to take steps that are necessary to establish and maintain a valid and credible argument for the safety of its missions. It is the premise of this handbook that making cases for safety more experience-based allows NASA to be better informed about the safety performance of its systems, and will ultimately help it to manage safety in a more effective manner. The APA process described in this handbook provides a systematic means of analyzing candidate

  4. MELCOR Accident Consequence Code System (MACCS)

    Rollstin, J.A. (GRAM, Inc., Albuquerque, NM (USA)); Chanin, D.I. (Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA)); Jow, H.N. (Sandia National Labs., Albuquerque, NM (USA))


    This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previously used CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projections, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. Volume I, the User's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems. Volume II, the Model Description, describes the underlying models that are implemented in the code, and Volume III, the Programmer's Reference Manual, describes the code's structure and database management.

  5. MELCOR Accident Consequence Code System (MACCS)

    Jow, H.N.; Sprung, J.L.; Ritchie, L.T. (Sandia National Labs., Albuquerque, NM (USA)); Rollstin, J.A. (GRAM, Inc., Albuquerque, NM (USA)); Chanin, D.I. (Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA))


    This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previously used CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projection, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. Volume I, the User's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems. Volume II, the Model Description, describes the underlying models that are implemented in the code, and Volume III, the Programmer's Reference Manual, describes the code's structure and database management. 59 refs., 14 figs., 15 tabs.

  6. Autonomous Vehicles: Disengagements, Accidents and Reaction Times.

    Dixit, Vinayak V; Chand, Sai; Nair, Divya J


    Autonomous vehicles are being viewed with scepticism in their ability to improve safety and the driving experience. A critical issue with automated driving at this stage of its development is that it is not yet reliable and safe. When automated driving fails, or is limited, the autonomous mode disengages and the drivers are expected to resume manual driving. For this transition to occur safely, it is imperative that drivers react in an appropriate and timely manner. Recent data released from the California trials provide compelling insights into the current factors influencing disengagements of autonomous mode. Here we show that the number of accidents observed has a significantly high correlation with the autonomous miles travelled. The reaction times to take control of the vehicle in the event of a disengagement was found to have a stable distribution across different companies at 0.83 seconds on average. However, there were differences observed in reaction times based on the type of disengagements, type of roadway and autonomous miles travelled. Lack of trust caused by the exposure to automated disengagements was found to increase the likelihood to take control of the vehicle manually. Further, with increased vehicle miles travelled the reaction times were found to increase, which suggests an increased level of trust with more vehicle miles travelled. We believe that this research would provide insurers, planners, traffic management officials and engineers fundamental insights into trust and reaction times that would help them design and engineer their systems.

  7. Bayesian networks for maritime traffic accident prevention: benefits and challenges.

    Hänninen, Maria


    Bayesian networks are quantitative modeling tools whose applications to the maritime traffic safety context are becoming more popular. This paper discusses the utilization of Bayesian networks in maritime safety modeling. Based on literature and the author's own experiences, the paper studies what Bayesian networks can offer to maritime accident prevention and safety modeling and discusses a few challenges in their application to this context. It is argued that the capability of representing rather complex, not necessarily causal but uncertain relationships makes Bayesian networks an attractive modeling tool for the maritime safety and accidents. Furthermore, as the maritime accident and safety data is still rather scarce and has some quality problems, the possibility to combine data with expert knowledge and the easy way of updating the model after acquiring more evidence further enhance their feasibility. However, eliciting the probabilities from the maritime experts might be challenging and the model validation can be tricky. It is concluded that with the utilization of several data sources, Bayesian updating, dynamic modeling, and hidden nodes for latent variables, Bayesian networks are rather well-suited tools for the maritime safety management and decision-making.

  8. [Return to work after occupational accidents and occupational diseases].

    Mehrhoff, F


    The key formula "by all suitable means" is a structural support for successful occupational reintegration. In this respect, the special system of accident insurance administered primarily through the "Berufsgenossenschaften" (BG), differs from the other branches of social security. This system's roots in civil law do not allow any comparison with the principle of public law insurance underlying the other branches of social security in Germany. Under the statutory accident insurance scheme, the employer, i.e., the liable party within the employment relationship, has to compensate any health damage incurred by an employee, subject to the principles of compensation for damages under civil law, in a manner enabling the employee to return to his position in worklife and in society as unscathed as possible. From this general mandate by the legislator, the social partners involved within the self-management of the BGs draw their strength and their dynamics in arranging for organizational methods within the-administrative offices and in cooperation with the health care providers. This control of rehabilitation, i.e., the accident insurance system's share of the responsibility for successful rehabilitation, contributes a great deal to reentergrating insured persons into work and career, returns valuable workers to the employers, thus having a favourable effect for the gross national product of a society, and last but not least provides a support for the social state.

  9. [Mineral oil drinking water pollution accident in Slavonski Brod, Croatia].

    Medverec Knežević, Zvonimira; Nadih, Martina; Josipović, Renata; Grgić, Ivanka; Cvitković, Ante


    On 21 September 2008, heavy oil penetrated the drinking water supply in Slavonski Brod, Croatia. The accident was caused by the damage of heat exchange units in hot water supply. The system was polluted until the beginning of November, when the pipeline was treated with BIS O 2700 detergent and rinsed with water. Meanwhile, water samples were taken for chemical analysis using spectrometric and titrimetric methods and for microbiological analysis using membrane filtration and total plate count. Mineral oils were determined with infrared spectroscopy. Of the 192 samples taken for mineral oil analysis, 55 were above the maximally allowed concentration (MAC). Five samples were taken for polycyclic aromatic hydrocarbon (PAH), benzene, toluene, ethylbenzene, and xylene analysis (BTEX), but none was above MAC. Epidemiologists conducted a survey about health symptoms among the residents affected by the accident. Thirty-six complained of symptoms such as diarrhoea, stomach cramps, vomiting, rash, eye burning, chills, and gastric disorders.This is the first reported case of drinking water pollution with mineral oil in Slavonski Brod and the accident has raised a number of issues, starting from poor water supply maintenance to glitches in the management of emergencies such as this.

  10. Accidents in Canada: mortality and hospitalization.

    Riley, R; Paddon, P


    For Canadians under 45, accidents are the leading cause of both death and hospitalization. For the Canadian population as a whole, accidents rank fourth as a cause of death, after cardiovascular disease (CVD), cancer and respiratory disease. This article analyzes accident mortality and hospitalization in Canada using age-specific rates, age-standardized mortality rates (ASMR), and potential years of life lost (PYLL). The six major causes of accidental death for men are motor vehicle traffic accidents (MVTA), falls, drowning, fires, suffocation and poisoning. For women, the order is slightly different: MVTA, falls, fires, suffocation, poisoning and drowning. From 1971 to 1986, age-standardized mortality rates (ASMR) for accidents decreased by 44% for men and 39% for women. The largest decrease occurred in the under 15 age group. Accidents accounted for 11.5% of total hospital days in 1985, and 8% of hospital discharges. Because young people have the highest rates of accidental death, potential years of life lost (PYLL) are almost as high for accidents as for cardiovascular disease, although CVD deaths outnumbered accidental deaths by almost five to one in 1985.

  11. An analysis of aircraft accidents involving fires

    Lucha, G. V.; Robertson, M. A.; Schooley, F. A.


    All U. S. Air Carrier accidents between 1963 and 1974 were studied to assess the extent of total personnel and aircraft damage which occurred in accidents and in accidents involving fire. Published accident reports and NTSB investigators' factual backup files were the primary sources of data. Although it was frequently not possible to assess the relative extent of fire-caused damage versus impact damage using the available data, the study established upper and lower bounds for deaths and damage due specifically to fire. In 12 years there were 122 accidents which involved airframe fires. Eighty-seven percent of the fires occurred after impact, and fuel leakage from ruptured tanks or severed lines was the most frequently cited cause. A cost analysis was performed for 300 serious accidents, including 92 serious accidents which involved fire. Personal injury costs were outside the scope of the cost analysis, but data on personnel injury judgements as well as settlements received from the CAB are included for reference.

  12. Road accidents and business cycles in Spain.

    Rodríguez-López, Jesús; Marrero, Gustavo A; González, Rosa Marina; Leal-Linares, Teresa


    This paper explores the causes behind the downturn in road accidents in Spain across the last decade. Possible causes are grouped into three categories: Institutional factors (a Penalty Point System, PPS, dating from 2006), technological factors (active safety and passive safety of vehicles), and macroeconomic factors (the Great recession starting in 2008, and an increase in fuel prices during the spring of 2008). The PPS has been blessed by incumbent authorities as responsible for the decline of road fatalities in Spain. Using cointegration techniques, the GDP growth rate, the fuel price, the PPS, and technological items embedded in motor vehicles appear to be statistically significantly related with accidents. Importantly, PPS is found to be significant in reducing fatal accidents. However, PPS is not significant for non-fatal accidents. In view of these results, we conclude that road accidents in Spain are very sensitive to the business cycle, and that the PPS influenced the severity (fatality) rather than the quantity of accidents in Spain. Importantly, technological items help explain a sizable fraction in accidents downturn, their effects dating back from the end of the nineties.

  13. Evaluation of the Relationship between Job Stress and Unsafe Acts with Occupational Accidents in a Vehicle Manufacturing Plant

    I. Mohammadfam


    Full Text Available Introduction & Objective: Nowadays the vehicle manufacturing industries in Iran are critical sites as far as occupational accidents are concerned. At the same time, occupational stress and unsafe acts have also been recognized as effective factors in increasing the risk of mental and physical health problems and occupational accidents. The main aim of this research was to evaluate the relationship between job stress and unsafe acts with occupational accidents.Materials & Methods: Data were collected using of “safety behaviors sampling technique”, standardized job stress questionnaire and analytical accident indices were calculated. The selection method of all samples was on a random basis. The information was then analyzed using Excel, SPSS and appropriate statistical tests.Results: The results of the study showed that there was a significant relationship between job stress and unsafe acts, the level of stress and unsafe acts with the number of occurred accidents (p-value<0.05. The study of the relationship between job stress, unsafe acts and occupational accidents via regression logistic test showed that increasing one percent in unsafe acts have more effect on accidents than increasing one grade in job stress. So, the rate or probability accidents can be predicted in organization by changes in the two mentioned variables.Conclusion: Reducing or eliminating identified effective stress factors and decreasing unsafe acts require the investment and implementation of an occupational stress management program.

  14. Problems of the security of facility viewed from accident information; Jiko joho kara mita setsubi hozen no kadai

    Nishikawa, K. [The High Pressure Gas Safety Inst. of Japan, Tokyo (Japan)


    In petroleum complexes and chemical complexes in which the control of operation of the plants is being automated, most of the accidents recently occurring are accidents occurring during, especially, works which are difficult to automate, such as non-steady work and maintenance work rather than accidents ascribed to erroneous operation. The number of aged facilities has increased, and the facility maintenance work tends to be subcontracted increasingly. The facility engineering will become a still more important problem in the future. The High Pressure Gas Safety Institute of Japan has issued a compendium on the safety of high pressure gas every year since 1987, and they issued a collection of examples of accidents in complexes in 1991. This paper introduces main examples of the accidents concerning the facility maintenance, extracted from the accident information recorded in the compendium and the collection of examples of accidents. Finally, lessons learned from the accident information are enumerated, and future problems are posed which include subcontraction of the facility maintenance work, the facility management cost and the facility safety. 6 refs., 1 fig., 1 tab.

  15. The work of the South Manchester Accident Rescue Team (SMART).

    Redmond, A D


    Skills acquired in the hospital do not necessarily translate to the scene of an accident. However, training in certain hospital specialties, particularly accident and emergency medicine, will expose doctors to dealing with very ill patients in a less rigidly structured environment. The operating theatre is a disciplined and controlled environment. Skill in anaesthesia, monitoring and operating, if tested only in these circumstances may be found to be gravely inadequate when exposed to the fluctuant and hostile environment at the site. Doctors who wish to do this sort of work or are designated to do it, must undergo regular and frequent training, especially if they are not trained in accident and emergency departments. This has long been recognised by the British Association for Immediate Care. In combination with the Royal College of Surgeons of Edinburgh they have now established a diploma in Immediate Medical Care. In urban areas the need for a doctor to attend at the scene of an accident is usually limited to entrapment. These occasions are likely to be infrequent and this can result in a lack of preparedness for such events. Interhospital transfer, primarily from peripheral hospitals to the specialist services of a teaching hospital, often involves critically ill and injured patients. The management of these cases by the mobile team provides regular, frequent exposure to working in a 'hostile' environment. Relationships with the rescue services are developed and staff become familiar with equipment and call-out procedures. The care of transported patients is improved. None of our patients have died in transit or within 6 h of arrival at base.(ABSTRACT TRUNCATED AT 250 WORDS)




    Full Text Available The Fukushima Dai-Ichi accident in 2011 has affected various aspects of the nuclear society worldwide. The accident revealed some problems in the conventional approaches used to ensure the safety of nuclear installations. To prevent such disastrous accidents in the future, we have to learn from them and improve the conventional approaches in a more systematic manner. In this paper, we will cover three issues. The first is to identify the key issues that affected the progress of the Fukushima Dai-Ichi accident greatly. We examine the accident from a defense-in-depth point of view to identify such issues. The second is to develop a more systematic approach to enhance the safety of nuclear installations. We reexamine nuclear safety from a risk point of view. We use the concepts of residual and unknown risks in classifying the risk space. All possible accident scenarios types are reviewed to clarify the characteristics of the identified issues. An approach is proposed to improve our conventional approaches used to ensure nuclear safety including the design of safety features and the safety assessments from a risk point of view. Finally, we address some issues to be improved in the conventional risk assessment and management framework and/or practices to enhance nuclear safety.

  17. Incorporation of severe accidents in the licensing of nuclear power plants

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz, E-mail:, E-mail: [Comissao Nacional de Energia Nuclear (CNEN) Rio de Janeiro, RJ (Brazil)


    Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

  18. Radiation Exposure and Thyroid Cancer Risk After the Fukushima Nuclear Power Plant Accident in Comparison with the Chernobyl Accident.

    Yamashita, S; Takamura, N; Ohtsuru, A; Suzuki, S


    The actual implementation of the epidemiological study on human health risk from low dose and low-dose rate radiation exposure and the comprehensive long-term radiation health effects survey are important especially after radiological and nuclear accidents because of public fear and concern about the long-term health effects of low-dose radiation exposure have increased considerably. Since the Great East Japan earthquake and the Fukushima Daiichi Nuclear Power Plant accident in Japan, Fukushima Prefecture has started the Fukushima Health Management Survey Project for the purpose of long-term health care administration and medical early diagnosis/treatment for the prefectural residents. Especially on a basis of the lessons learned from the Chernobyl accident, both thyroid examination and mental health care are critically important irrespective of the level of radiation exposure. There are considerable differences between Chernobyl and Fukushima regarding radiation dose to the public, and it is very difficult to estimate retrospectively internal exposure dose from the short-lived radioactive iodines. Therefore, the necessity of thyroid ultrasound examination in Fukushima and the intermediate results of this survey targeting children will be reviewed and discussed in order to avoid any misunderstanding or misinterpretation of the high detection rate of childhood thyroid cancer.

  19. Analysis of accidents leading to amputations associated with operating with press machines, using Ishikawa and SCAT Combined method in a car manufacturing company

    J. Nematolahi


      Conclusion: According to results, the main interfce causes of accidents leading to amputation due to operating with press machines is hurry at work because of increased production volume particularly by contractor companies. Furthermore, non-dynamic HSE system accompanied by ineffective supervision of personnel’s unsafe acts by the first layers of management are recognized as the basic causes of such accidents.

  20. Elements to diminish radioactive accidents; Elementos para disminuir accidentes radiactivos

    Cortes I, M.E.; Ramirez G, F.P. [Instituto Mexicano del Petroleo, Eje Central Lazaro Cardenas 152, C.P. 07730 Mexico D.F. (Mexico)


    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. Development of heat insulation device to protect pressure measuring instruments from high temperature under the severe accident

    Ham, Jaehyun; Shin, Sung Min; Kang, Hyun Gook [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)


    Micro Control Unit (MCU), communication module, and power supply system are also needed to be protected for the pressure transmitter. The harsh condition in containment which is created by the severe accident are composed of five elements: high temperature, high pressure, high humidity, high radiation, and physical threats by shrapnel generated during the process of the severe accident. Among these five elements, high temperature should be focused because other elements can be solved even with the thin shield. In this study, a detailed design of the heat insulation device which will be installed in the containment based on the Min Yoo's study and a verification test are done. Development of heat insulation device which enables operator to get in-containment data for the proper mitigation process under the severe accident was done in this study. With researches for severe accident management systems which proceeding actively since the Fukushima accident, researches for reliable instrumentations of in-containment data which is necessary to operate severe accident management systems properly in harsh condition during accident also should be progressed.

  2. Design and application of a tool for structuring, capitalizing and making more accessible information and lessons learned from accidents involving machinery.

    Sadeghi, Samira; Sadeghi, Leyla; Tricot, Nicolas; Mathieu, Luc


    Accident reports are published in order to communicate the information and lessons learned from accidents. An efficient accident recording and analysis system is a necessary step towards improvement of safety. However, currently there is a shortage of efficient tools to support such recording and analysis. In this study we introduce a flexible and customizable tool that allows structuring and analysis of this information. This tool has been implemented under TEEXMA®. We named our prototype TEEXMA®SAFETY. This tool provides an information management system to facilitate data collection, organization, query, analysis and reporting of accidents. A predefined information retrieval module provides ready access to data which allows the user to quickly identify the possible hazards for specific machines and provides information on the source of hazards. The main target audience for this tool includes safety personnel, accident reporters and designers. The proposed data model has been developed by analyzing different accident reports.

  3. Phenomenology of severe accidents in BWR type reactors. First part; Fenomenologia de accidentes severos en reactores nucleares de agua en ebullicion. Primera parte

    Sandoval V, S. [Instituto de Investigaciones Electricas, Gerencia de Energia Nuclear, Av. Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico)


    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)

  4. Psychophysiological and other factors affecting human performance in accident prevention and investigation. [Comparison of aviation with other industries

    Klinestiver, L.R.


    Psychophysiological factors are not uncommon terms in the aviation incident/accident investigation sequence where human error is involved. It is highly suspect that the same psychophysiological factors may also exist in the industrial arena where operator personnel function; but, there is little evidence in literature indicating how management and subordinates cope with these factors to prevent or reduce accidents. It is apparent that human factors psychophysological training is quite evident in the aviation industry. However, while the industrial arena appears to analyze psychophysiological factors in accident investigations, there is little evidence that established training programs exist for supervisors and operator personnel.

  5. The Chernobyl accident consequences; Consequences de l'accident de Tchernobyl



    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.)

  6. 48 CFR 852.236-87 - Accident prevention.


    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Accident prevention. 852... Accident prevention. As prescribed in 836.513, insert the following clause: Accident Prevention (SEP 1993....236-13, Accident Prevention. However, only the Contracting Officer may issue an order to stop all...

  7. 46 CFR 4.03-1 - Marine casualty or accident.


    ... States vessel wherever such casualty or accident occurs; or (3) With respect to a foreign tank vessel... 46 Shipping 1 2010-10-01 2010-10-01 false Marine casualty or accident. 4.03-1 Section 4.03-1... AND INVESTIGATIONS Definitions § 4.03-1 Marine casualty or accident. Marine casualty or accident...

  8. 46 CFR 196.30-5 - Accidents to machinery.


    ... 46 Shipping 7 2010-10-01 2010-10-01 false Accidents to machinery. 196.30-5 Section 196.30-5... Reports of Accidents, Repairs, and Unsafe Equipment § 196.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use...

  9. 46 CFR 97.30-5 - Accidents to machinery.


    ... 46 Shipping 4 2010-10-01 2010-10-01 false Accidents to machinery. 97.30-5 Section 97.30-5 Shipping... Reports of Accidents, Repairs, and Unsafe Equipment § 97.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use...

  10. 46 CFR 78.33-5 - Accidents to machinery.


    ... 46 Shipping 3 2010-10-01 2010-10-01 false Accidents to machinery. 78.33-5 Section 78.33-5 Shipping... Accidents, Repairs, and Unsafe Equipment § 78.33-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use of the...

  11. Ruthenium release from fuel in accident conditions

    Brillant, G.; Marchetto, C.; Plumecocq, W. [Inst. de Radioprotection et de Surete Nucleaire, DPAM, SEMIC, LETR and LIMSI, Saint-Paul-Lez-Durance (France)


    During a hypothetical nuclear power plant accident, fission products may be released from the fuel matrix and then reach the containment building and the environment. Ruthenium is a very hazardous fission product that can be highly and rapidly released in some accident scenarios. The impact of the atmosphere redox properties, temperature, and fuel burn-up on the ruthenium release is discussed. In order to improve the evaluation of the radiological impact by accident codes, a model of the ruthenium release from fuel is proposed using thermodynamic equilibrium calculations. In addition, a model of fuel oxidation under air is described. Finally, these models have been integrated in the ASTEC accident code and validation calculations have been performed on several experimental tests. (orig.)

  12. MELCOR analysis of the TMI-2 accident

    Boucheron, E.A.


    This paper describes the analysis of the Three Mile Island-2 (TMI-2) standard problem that was performed with MELCOR. The MELCOR computer code is being developed by Sandia National Laboratories for the Nuclear Regulatory Commission for the purpose of analyzing severe accident in nuclear power plants. The primary role of MELCOR is to provide realistic predictions of severe accident phenomena and the radiological source team. The analysis of the TMI-2 standard problem allowed for comparison of the model predictions in MELCOR to plant data and to the results of more mechanistic analyses. This exercise was, therefore valuable for verifying and assessing the models in the code. The major trends in the TMI-2 accident are reasonably well predicted with MELCOR, even with its simplified modeling. Comparison of the calculated and measured results is presented and, based on this comparison, conclusions can be drawn concerning the applicability of MELCOR to severe accident analysis. 5 refs., 10 figs., 3 tabs.

  13. [Severe parachuting accident. Analysis of 122 cases].

    Krauss, U; Mischkowsky, T


    Based on a population of 122 severely injured patients the causes of paragliding accidents and the patterns of injury are analyzed. A questionnaire is used to establish a sport-specific profile for the paragliding pilot. The lower limbs (55.7%) and the lower parts of the spine (45.9%) are the most frequently injured parts of the body. There is a high risk of multiple injuries after a single accident because of the tremendous axial power. The standard of equipment is good in over 90% of the cases. Insufficient training and failure to take account of geographical and meteorological conditions are the main determinants of accidents sustained by paragliders, most of whom are young. Nevertheless, 80% of our patients want to continue paragliding. Finally some advice is given on how to prevent paragliding accidents and injuries.

  14. The Chornobyl accident: A comprehensive risk assessment

    Vargo, G.J. [ed.; Poyarkov, V.; Bar`yakhtar, V.; Kukhar, V.; Los, I.; Kholosha, V.; Shestopalov, V.


    The authors, all of whom are Ukrainian and Russian scientists involved with Chornobyl nuclear power plant since the April 1986 accident, present a comprehensive review of the accident. In addition, they present a risk assessment of the remains of the destroyed reactor and its surrounding shelter, Chornobyl radioactive waste storage and disposal sites, and environmental contamination in the region. The authors explore such questions as the risks posed by a collapse of the shelter, radionuclide migration from storage and disposal facilities in the exclusion zone, and transfer from soil to vegetation and its potential regional impact. The answers to these questions provide a scientific basis for the development of countermeasures against the Chornobyl accident in particular and the mitigation of environmental radioactive contamination in general. They also provide an important basis for understanding the human health and ecological risks posed by the accident.

  15. Safety analysis of surface haulage accidents

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


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

  16. Review of methodology for accident consequence assessment

    Strenge, D.L.; Soldat, J.K.; Watson, E.C.


    This report reviews current methodologies for reactor accident consequence analysis and describes areas where modifications are warranted. Methodologies reviewed are: (1) Models in Regulatory Guides 1.109, 1.111 and 1.113 used for evaluation of compliance with 10 CFR 50 Appendix I; (2) Models in Regulatory Guides used for evaluation of consequences from accidents of Classes 3-8; (3) Models for evaluation of Class 9 accidents presented in the Reactor Safety Study; and (4) Models in the Liquid Pathway Generic Study. The review is designed to aid in the ultimate goal of selection of a comprehensive set of models to extend the Class 9 methodology of the Reactor Safety Study to the analysis of Classes 3-8 accidents.

  17. The epidemiology of bicyclist's collision accidents

    Larsen, L. B.


    of bicyclists and risk situations. The findings should make a basis for preventive programmes in order to decrease the number and severity of bicyclists collision accidents. Data from the emergency room in a 2 year period was combined with data from questionnaires. The study group consisted of 1021 bicyclists...... group of accidents were the collisions with the 'soft' road users (bicyclists, mopeds, and pedestrians) and another group were the collisions with the 'hard' road users (motor vehicles, motorcycles). Preventive measures have to be directed at both these groups of accidents. To decrease the number...... of collision accidents with motor vehicles it is necessary to separate the bicyclists from the 'hard road traffic' especially at crossings. Preventive measures must also be directed at the bicyclists. Information must be given to warn the bicyclists against the risks, not only for collisions with motor...

  18. [Model of Analysis and Prevention of Accidents - MAPA: tool for operational health surveillance].

    de Almeida, Ildeberto Muniz; Vilela, Rodolfo Andrade de Gouveia; da Silva, Alessandro José Nunes; Beltran, Sandra Lorena


    The analysis of work-related accidents is important for accident surveillance and prevention. Current methods of analysis seek to overcome reductionist views that see these occurrences as simple events explained by operator error. The objective of this paper is to analyze the Model of Analysis and Prevention of Accidents (MAPA) and its use in monitoring interventions, duly highlighting aspects experienced in the use of the tool. The descriptive analytical method was used, introducing the steps of the model. To illustrate contributions and or difficulties, cases where the tool was used in the context of service were selected. MAPA integrates theoretical approaches that have already been tried in studies of accidents by providing useful conceptual support from the data collection stage until conclusion and intervention stages. Besides revealing weaknesses of the traditional approach, it helps identify organizational determinants, such as management failings, system design and safety management involved in the accident. The main challenges lie in the grasp of concepts by users, in exploring organizational aspects upstream in the chain of decisions or at higher levels of the hierarchy, as well as the intervention to change the determinants of these events.

  19. Severe accident testing of electrical penetration assemblies

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


    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. Personality characteristics of the child accident repeater

    Manheimer, Dean I.; Mellinger, Glen D


    From 8874 boys and girls aged 4 to 18 in Berkeley-Oakland, California, 684 were selected to represent high-, intermediateor low-accident-liability children, based on records of medically attended injuries. Using data from intensive interviews with mothers supplemented with school records, we found a statistically significant relation between accident liability and indexes of extraversion, daring, roughhousing, and other traits tending to expose children to hazards. Similar relations held for ...

  1. Development of Methodology for Spent Fuel Pool Severe Accident Analysis Using MELCOR Program

    Kim, Won-Tae; Shin, Jae-Uk [RETech. Co. LTD., Yongin (Korea, Republic of); Ahn, Kwang-Il [KAERI, Daejeon (Korea, Republic of)


    The general reason why SFP severe accident analysis has to be considered is that there is a potential great risk due to the huge number of fuel assemblies and no containment in a SFP building. In most cases, the SFP building is vulnerable to external damage or attack. In contrary, low decay heat of fuel assemblies may make the accident processes slow compared to the accident in reactor core because of a great deal of water. In short, its severity of consequence cannot exclude the consideration of SFP risk management. The U.S. Nuclear Regulatory Commission has performed the consequence studies of postulated spent fuel pool accident. The Fukushima-Daiichi accident has accelerated the needs for the consequence studies of postulated spent fuel pool accidents, causing the nuclear industry and regulatory bodies to reexamine several assumptions concerning beyond-design basis events such as a station blackout. The tsunami brought about the loss of coolant accident, leading to the explosion of hydrogen in the SFP building. Analyses of SFP accident processes in the case of a loss of coolant with no heat removal have studied. Few studies however have focused on a long term process of SFP severe accident under no mitigation action such as a water makeup to SFP. USNRC and OECD have co-worked to examine the behavior of PWR fuel assemblies under severe accident conditions in a spent fuel rack. In support of the investigation, several new features of MELCOR model have been added to simulate both BWR fuel assembly and PWR 17 x 17 assembly in a spent fuel pool rack undergoing severe accident conditions. The purpose of the study in this paper is to develop a methodology of the long-term analysis for the plant level SFP severe accident by using the new-featured MELCOR program in the OPR-1000 Nuclear Power Plant. The study is to investigate the ability of MELCOR in predicting an entire process of SFP severe accident phenomena including the molten corium and concrete reaction. The


    O. Gamankova


    Full Text Available The paper deals with the peculiarities of financial provision of public and private accident insurance. Analyzes the methodology of forming insurance premium rates in private accident insurance. The study examines the practice of reforming the financial security of the state social insurance against accidents. The results show need to implement scientifically proven approach to determining premium rates in the state social insurance based on mathematical statistics and actuarial calculations to ensure that such conditions on the one hand, can insure the risk, and the other - to provide the insurer the ability to perform insurance obligations' commitments. One of the promising areas of improvement Accident Insurance determines to define increasing the role of the private sector to create and attraction of investments, financing, reduce costs, and provision of insurance services on insurance against accidents at a qualitatively higher level. The results show the need to consider the usefulness of a mixed provision of services to accident insurance under state or non-state system, and the viability and effectiveness of the combination of these systems.




    Full Text Available

    Introduction. Car accident mortality is the third order causes of death in the USA, following cardiovascular diseases and cancers. Given present survival and outcome Iranian data, more than 14,000 patients die annually in road accidents. Having a valid and reliable data could be useful in reduce mortality and morbidity reduction.
    Methods. Twenty five percent of total traumatic patients in Isfahan were selected (N=2809 at the time of study (1997-1998. Forty five percent of them with car accident were asked about causes of accidents and risk factors for the severity and type of injuries were recorded based on International Classification of Disease 10.
    Results. Most of the victims were young (10-20 years old, students and industrial workers. Statistically unreasonable numbers of cars without extension of roads and high ways, using old and unsafe cars will affects on accidents.
    Discussion. In comparison with European and some Asian countries, Iran has unacceptable road accidents and it seems necessary to pay more attention to stop the current increasing data.


  4. 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.

  5. [Drivers of advanced age in traffic accidents].

    Bilban, Marjan


    The elderly are vulnerable and potentially unpredictable active participants in traffic who deserve special attention. Longer life expectancy entails a greater number of senior drivers, that is, persons with various health problems and difficulties accompanying old age. At the turn of the millennium, the share of population aged 65 or more in Slovenia was around 13%, and in 25 years it will be near as much as 19%. The share of drivers from this age group was 28% a year ago, and it is expected to reach about 54%. Numerous studies have shown that there are many differences in driving attitude between the young and the elderly. The young are by large active victims, and their main offense and cause of accident is speeding, while the elderly are more passive and their main offense is ignoring and enforcing the right of way. This paper focuses on the differences in the occurrence and type of injuries between the young and the elderly drivers, based on an analysis of all road accidents in Slovenia in the period between 1998-2000. Older people (over 65) caused only 4.7% of all road accidents (16.7% of all accidents involving pedestrians, 11.5% of all involving cyclists, 2.7% involving motorcyclists and 5% of all accidents involving car drivers). Of all accidents, 89.3% were without injuries, and the fatal outcome was registered in 0.4% accidents. Among the elderly (65-74 years of age), however, this share was 1%, and rising to 2.7% with the age 75 and above. By calculating the weight index, which discriminates between minor and severe injuries, and the fatal outcome, it was established that age groups 65-74 and > or = 75 cause three and five times greater damage, respectively than age groups from 18 to 54 years. With years, psychophysical changes lead to a drop in driving ability, which in turn increases the risk of road accidents. It is true that elderly people cause less traffic accidents (and also drive less) than the young, but when they are involved in an accident

  6. Advances in operational safety and severe accident research

    Simola, K. [VTT Automation (Finland)


    A project on reactor safety was carried out as a part of the NKS programme during 1999-2001. The objective of the project was to obtain a shared Nordic view of certain key safety issues related to the operating nuclear power plants in Finland and Sweden. The focus of the project was on selected central aspects of nuclear reactor safety that are of common interest for the Nordic nuclear authorities, utilities and research bodies. The project consisted of three sub-projects. One of them concentrated on the problems related to risk-informed deci- sion making, especially on the uncertainties and incompleteness of probabilistic safety assessments and their impact on the possibilities to use the PSA results in decision making. Another sub-project dealt with questions related to maintenance, such as human and organisational factors in maintenance and maintenance management. The focus of the third sub-project was on severe accidents. This sub-project concentrated on phenomenological studies of hydrogen combustion, formation of organic iodine, and core re-criticality due to molten core coolant interaction in the lower head of reactor vessel. Moreover, the current status of severe accident research and management was reviewed. (au)

  7. Exploring Environmental Effects of Accidents During Marine Transport of Dangerous Goods by Use of Accident Descriptions

    Rømer, Hans Gottberg; Haastrup, P.; Petersen, H J Styhr


    On the basis of 1776 descriptions of water transport accidents involving dangerous goods, environmental problems in connection with releases of this kind are described and discussed. It was found that most detailed descriptions of environmental consequences concerned oil accidents, although most...

  8. Reliability and Failure in NASA Missions: Blunders, Normal Accidents, High Reliability, Bad Luck

    Jones, Harry W.


    NASA emphasizes crew safety and system reliability but several unfortunate failures have occurred. The Apollo 1 fire was mistakenly unanticipated. After that tragedy, the Apollo program gave much more attention to safety. The Challenger accident revealed that NASA had neglected safety and that management underestimated the high risk of shuttle. Probabilistic Risk Assessment was adopted to provide more accurate failure probabilities for shuttle and other missions. NASA's "faster, better, cheaper" initiative and government procurement reform led to deliberately dismantling traditional reliability engineering. The Columbia tragedy and Mars mission failures followed. Failures can be attributed to blunders, normal accidents, or bad luck. Achieving high reliability is difficult but possible.

  9. A tool for safety officers when analysing the basic causes of simple accidents

    Jørgensen, Kirsten

    situation no one could do anything about. In 1999 a new practical tool for use by safety officers was developed and used by training systems. The tool involves three steps: one for observing facts, one for analysing the event, and one for preventive solutions. The tool has been used by various companies...... for some years with interesting results. Both the difficulties and the benefits will be presented, together with examples of the use of the tool. The main purpose of the tool is to demonstrate how management and workers can get a much better understanding of why accidents happen, even those accidents...

  10. Study on coal mines accidents based on the grey relational analysis

    WANG Shuai; ZHANG Jin-long


    The subject investigated the system of people-machine-environment in coal mines. The coal mines working process was researched and the theory of grey system was applied to analyze coal mines safety accidents and those relevant factors. This re-search reveals that this analysis method is easy and highly available and the result is of great credibility, which can not only provide theoretical supports to the quantitative study of coal mines safety accident, but offer basis for coal mines companies' safety management.

  11. Reactor Core Coolability Analysis during Hypothesized Severe Accidents of OPR1000

    Lee, Yongjae; Seo, Seungwon; Kim, Sung Joong [Hanyang University, Seoul (Korea, Republic of); Ha, Kwang Soon; Kim, Hwan-Yeol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    CET showed similar trends. Therefore, JaCET is expected to provide judgmental information to the reactor operators for the proper severe accident management.

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

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


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

  13. Accident Case Study of Organizational Silence Communication Breakdown: Shuttle Columbia, Mission STS-107

    Rocha, Rodney


    This report has been developed by the National Aeronautics and Space Administration (NASA) ESMD Risk and Knowledge Management team. This document provides a point-in-time, cumulative, summary of key lessons learned derived from the official Columbia Accident Investigation Board (CAIB). Lessons learned invariably address challenges and risks and the way in which these areas have been addressed. Accordingly the risk management thread is woven throughout the document. This report is accompanied by a video that will be sent at request

  14. 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)


    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.

  15. Long-term follow-up of radiation accident patients in Peru: review of two cases.

    Barriga, L E; Zaharia, M; Pinillos, L; Moscol, A; Heredia, A; Sarria, G; Marquina, J; Barriga, O; Picon, C


    Overexposure to radioactive sources used in radiotherapy or industrial radiography may result in severe health consequences. This report assesses the initial clinical status and the medical and psychological long-term follow-up of two radiation accident patients from Peru during the mid-to-late 1990s: one patient exposed to a radiotherapy (60)Co source in Arequipa, the other patient to a (192)Ir source in Yanango. Commonalities and differences are described. The main causes in both accidents were human error and the failure to apply appropriate safety guidelines and standard operating procedures. Education and training of the personnel working with radiation sources are essential to prevent accidents. The experience gained from the medical management of the two patients is valuable for future treatment of such patients.

  16. Assessment of Loads and Performance of a Containment in a Hypothetical Accident (ALPHA). Facility design report

    Yamano, Norihiro; Maruyama, Yu; Kudo, Tamotsu; Moriyama, Kiyofumi; Ito, Hideo; Komori, Keiichi; Sonobe, Hisao; Sugimoto, Jun [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment


    In the ALPHA (Assessment of Loads and Performance of Containment in Hypothetical Accident) program, several tests have been performed to quantitatively evaluate loads to and performance of a containment vessel during a severe accident of a light water reactor. The ALPHA program focuses on investigating leak behavior through the containment vessel, fuel-coolant interaction, molten core-concrete interaction and FP aerosol behavior, which are generally recognized as significant phenomena considered to occur in the containment. In designing the experimental facility, it was considered to simulate appropriately the phenomena mentioned above, and to cover experimental conditions not covered by previous works involving high pressure and temperature. Experiments from the viewpoint of accident management were also included in the scope. The present report describes design specifications, dimensions, instrumentation of the ALPHA facility based on the specific test objectives and procedures. (author)

  17. Relationship between speed and traffic accident and speed limit on freeway

    CHENG Guo-zhu; PEI Yu-long


    To develop an equation between discrete degree of speed and traffic accident on freeway in China and give reasonable suggestions of speed management, the relation model was established between speed standard deviation and accident rate per 100,000,000 vehicle kilometers by regression analysis. The model shows that the more discrete is the speed distribution, the higher is the accident rate, which provides theoretical gist for speed limit on freeway. It is suggested that speed limit should be set according to 85th percentile speed obtained by the relationship between 85th percentile speed and Rcc, (curvature change rate of single circular curve), anddifferent speed limits should be set for cars and trucks. Through analyzing spot speed data of eight freeways in China, regression models were established between 85th percentile speed and RCCs and 15th percentile speed and RCCs. Reasonable speed limit suggestion values are put forward through these models.

  18. Radiological accidents: methodologies of radio nuclides dis incorporation; Accidentes radiologicos: metodologias de desincorporacion de radionuclidos

    Jimenez F, E. A. [Universidad Autonoma del Estado de Mexico, Facultad de Medicina, Paseo Tollocan s/n, 50180 Toluca, Estado de Mexico (Mexico); Paredes G, L. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Cortes, A., E-mail: [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)


    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)

  19. Epidemiological characteristics of fatal pedestrian accidents in Fars Province of Iran: a community-based survey

    Payam Peymani; Ali Foroutan; Seyed Mehdi Ahmadi; Fariborz Ghaffarpasand; Hassan Joulaei; Kamran B Lankarani; Seyed Taghi Heydari; Amin Hoseinzadeh; Yaser Sarikhani; Arya Hedjazi; Mohammad Zarenezhad; Ghasem Moafian; Mohammad Reza Aghabeigi; Najmeh Maharlouei


    Objective: To determine the epidemiological characteristics of fatal pedestrian accidents in Fars Province of Iran.Methods: This cross-sectional study was conducted in Fars Province of Iran during a 29-month period from March 2009 to July 2011.The data were from the Fars Forensic Medicine Registry.In 4 923 recorded road traffic accident fatalities,971 deaths were due to pedestrian accidents.The demographic and accident-related information were analyzed by SPSS version 11.5.P value less than 0.05 was considered significant.Results: The mean age of decedents was (47.2±26.2)years,ranging from 6 months to 103 years old.Males accounted for 69.8% of all deaths.Fatal accidents were most common in September; 56.1% of the fatal injuries occurred on intracity roads and 33.1% on extracity roads.Fatal head injuries were present in 60.54% of cases.Evaluation of the injury site and the cause of death found that they were significantly associated with age,interval between injury and death.Besides,the type of roads played an important role in mortality.Conclusion: Although the clinical management of trauma patients has been improved in our country in the recent decade,decreasing the burden of injuries needs coordination among trauma system organizations.

  20. Enhanced Accident Tolerant LWR Fuels: Metrics Development

    Shannon Bragg-Sitton; Lori Braase; Rose Montgomery; Chris Stanek; Robert Montgomery; Lance Snead; Larry Ott; Mike Billone


    The Department of Energy (DOE) Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) is conducting research and development on enhanced Accident Tolerant Fuels (ATF) for light water reactors (LWRs). This mission emphasizes the development of novel fuel and cladding concepts to replace the current zirconium alloy-uranium dioxide (UO2) fuel system. The overall mission of the ATF research is to develop advanced fuels/cladding with improved performance, reliability and safety characteristics during normal operations and accident conditions, while minimizing waste generation. The initial effort will focus on implementation in operating reactors or reactors with design certifications. To initiate the development of quantitative metrics for ATR, a LWR Enhanced Accident Tolerant Fuels Metrics Development Workshop was held in October 2012 in Germantown, MD. This paper summarizes the outcome of that workshop and the current status of metrics development for LWR ATF.

  1. Predicting road accidents: Structural time series approach

    Junus, Noor Wahida Md; Ismail, Mohd Tahir


    In this paper, the model for occurrence of road accidents in Malaysia between the years of 1970 to 2010 was developed and throughout this model the number of road accidents have been predicted by using the structural time series approach. The models are developed by using stepwise method and the residual of each step has been analyzed. The accuracy of the model is analyzed by using the mean absolute percentage error (MAPE) and the best model is chosen based on the smallest Akaike information criterion (AIC) value. A structural time series approach found that local linear trend model is the best model to represent the road accidents. This model allows level and slope component to be varied over time. In addition, this approach also provides useful information on improving the conventional time series method.

  2. A Review of Criticality Accidents 2000 Revision

    Thomas P. McLaughlin; Shean P. Monahan; Norman L. Pruvost; Vladimir V. Frolov; Boris G. Ryazanov; Victor I. Sviridov


    Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report.

  3. Assessment of CRBR core disruptive accident energetics

    Theofanous, T.G.; Bell, C.R.


    The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly.

  4. Bundled automobile insurance coverage and accidents.

    Li, Chu-Shiu; Liu, Chwen-Chi; Peng, Sheng-Chang


    This paper investigates the characteristics of automobile accidents by taking into account two types of automobile insurance coverage: comprehensive vehicle physical damage insurance and voluntary third-party liability insurance. By using a unique data set in the Taiwanese automobile insurance market, we explore the bundled automobile insurance coverage and the occurrence of claims. It is shown that vehicle physical damage insurance is the major automobile coverage and affects the decision to purchase voluntary liability insurance coverage as a complement. Moreover, policyholders with high vehicle physical damage insurance coverage have a significantly higher probability of filing vehicle damage claims, and if they additionally purchase low voluntary liability insurance coverage, their accident claims probability is higher than those who purchase high voluntary liability insurance coverage. Our empirical results reveal that additional automobile insurance coverage information can capture more driver characteristics and driving behaviors to provide useful information for insurers' underwriting policies and to help analyze the occurrence of automobile accidents.

  5. Internal Accident Report: fill it out!


    It is important to report all accidents, near-misses and dangerous situations so that they can be avoided in the future.   Reporting these events allows the relevant services to take appropriate action and implement corrective and preventive measures. It should be noted that the routing of the internal accident report was recently changed to make sure that the people who need to know are informed. Without information, corrective action is not possible. Without corrective action, there is a risk that the events will recur. As soon as you experience or see something amiss, fill out an internal accident report! If you have any questions the HSE Unit will be happy to answer them. Contact us at The HSE Unit

  6. Agricultural implications of the Fukushima nuclear accident

    Nakanishi, Tomoko M.


    More than 4 years has passed since the accident at the Fukushima Nuclear Power Plant. Immediately after the accident, 40 to 50 academic staff of the Graduate School of Agricultural and Life Sciences at the University of Tokyo created an independent team to monitor the behavior of the radioactive materials in the field and their effects on agricultural farm lands, forests, rivers, animals, etc. When the radioactive nuclides from the nuclear power plant fell, they were instantly adsorbed at the site where they first touched; consequently, the fallout was found as scattered spots on the surface of anything that was exposed to the air at the time of the accident. The adsorption has become stronger over time, so the radioactive nuclides are now difficult to remove. The findings of our study regarding the wide range of effects on agricultural fields are summarized in this report. PMID:27538845

  7. Reconfigurable mobile manipulation for accident response



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

  8. MDCT findings in sports and recreational accidents

    Bensch, Frank V; Koivikko, Mika P; Koskinen, Seppo K (Dept. of Radiology, Toeoeloe Hospital, Helsinki (Finland)), email:


    Background. Sports and recreational accidents involving critical areas of the body occur commonly in the general population. Reports on their demographics and recommendations for screening procedures are, however, few. Purpose. To assess injuries of the craniofacial area, spine, and torso resulting from sports and recreational accidents with multidetector computed tomography (MDCT) as primary imaging method in a Level I trauma center. Material and Methods. All emergency room CT requests over a time span of 105 months were reviewed retrospectively for trauma mechanism and injury. Patients were identified using an electronic picture archiving and communications system (PACS), and MDCT studies interpreted by two radiologists independently. Results. Of a total of 5898 patients, 492 patients (301 boys/men, 191 girls/women, age range 2-76 years, mean 33.5 years, median 29.5 years) with sports or recreational accidents emerged. A total of 102 traumatic findings were diagnosed, thereof 72 (71%) serious. The three most commonly encountered serious injuries were intracranial injury, fractures of facial bones, and vertebral injuries. The three most common injury mechanisms were bicycling, horseback riding, and team ball sports. Patients from recreational activities were on average significantly younger (29.2 years) than those from sports accidents (36.9 years; P < 0.001). Only age groups <21 years and 41-50 years differed in injury severity from the other age groups (P = 0.004 and P = 0.063, respectively). Of all trauma mechanisms, only bicycling had a significantly increased risk of injury (P < 0.001). Conclusion. Injuries in sports and recreational accidents presented with an overall incidence of 21%, of which 71% are serious. The most common mechanisms of injury were bicycling, horseback riding, and team ball sports. The largest incidence of serious injury involved bicycling. Because of the high probability of a serious injury and the high energies that are often involved

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

    Wyss, G.D.; Camp, A.L.; Miller, L.A.; Dingman, S.E.; Kunsman, D.M. (Sandia National Labs., Albuquerque, NM (USA)); Medford, G.T. (Science Applications International Corp., Albuquerque, NM (USA))


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

  10. Dose estimates from the Chernobyl accident

    Lange, R.; Dickerson, M.H.; Gudiksen, P.H.


    The Lawrence Livermore National Laboratory Atmospheric Release Advisory Capability (ARAC) responded to the Chernobyl nuclear reactor accident in the Soviet Union by utilizing long-range atmospheric dispersion modeling to estimate the amount of radioactivity released (source term) and the radiation dose distribution due to exposure to the radioactive cloud over Europe and the Northern Hemisphere. In later assessments, after the release of data on the accident by the Soviet Union, the ARAC team used their mesoscale to regional scale model to focus in on the radiation dose distribution within the Soviet Union and the vicinity of the Chernobyl plant. 22 refs., 5 figs., 5 tabs.

  11. Accident Safety Design for High Speed Elevator

    Tawiwat Veeraklaew


    Full Text Available There have been many elevators exist in buildings for such a long time; however, an accident might happen as a free fall due to lacks of maintenance or some other accident such as firing. Although this situation is rarely occurred, many people are still concerned about it. The question here is how to make passengers to feel safe and confident when they are using an elevator, especially, high speed elevator. This problem is studied here in this paper as a free fall spring-mass-damper system with the stiffness and damping coefficient can be computed as minimum jerk of the system with given constraints on trajectories.

  12. Lessons learned from early criticality accidents

    Malenfant, R.E.


    Four accidents involving the approach to criticality occurred during the period July, 1945, through May, 1996. These have been described in the format of the OPERATING EXPERIENCE WEEKLY SUMMARY which is distributed by the Office of Nuclear and Facility Safety. Although the lessons learned have been incorporated in standards, codes, and formal procedures during the last fifty years, this is their first presentation in this format. It is particularly appropriate that they be presented in the forum of the Nuclear Criticality Technology Safety Project Workshop closest to the fiftieth anniversary of the last of the four accidents, and that which was most instrumental in demonstrating the need to incorporate lessons learned.


    Woods, Michael; /SLAC


    A graduate student received a laser eye injury from a femtosecond Ti:sapphire laser beam while adjusting a polarizing beam splitter optic. The direct causes for the accident included failure to follow safe alignment practices and failure to wear the required laser eyewear protection. Underlying root causes included inadequate on-the-job training and supervision, inadequate adherence to requirements, and inadequate appreciation for dimly visible beams outside the range of 400-700nm. This paper describes how the accident occurred, discusses causes and lessons learned, and describes corrective actions being taken.

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


    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)

  15. Management of trauma to supporting dental structures.

    Elias, Husam; Baur, Dale A


    Teeth, periodontium, and supporting alveolar bone are frequently involved in trauma and account for approximately 15% of all emergency room visits. The cause of the dentoalveolar trauma varies in different demographics but generally results from falls, playground accidents, domestic violence, bicycle accidents, motor vehicle accidents, assaults, altercations, and sports injuries. Dentoalveolar injuries should be considered an emergency situation because successful management of the injury requires proper diagnosis and treatment within a limited time to achieve better outcomes.

  16. Pressure Load Analysis during Severe Accidents for the Evaluation of Late Containment Failure in OPR-1000

    Park, S. Y.; Ahn, K. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    The MAAP code is a system level computer code capable of performing integral analyses of potential severe accident progressions in nuclear power plants, whose main purpose is to support a level 2 probabilistic safety assessment or severe accident management strategy developments. The code employs lots of user-options for supporting a sensitivity and uncertainty analysis. The present application is mainly focused on determining an estimate of the containment building pressure load caused by severe accident sequences. Key modeling parameters and phenomenological models employed for the present uncertainty analysis are closely related to in-vessel hydrogen generation, gas combustion in the containment, corium distribution in the containment after a reactor vessel failure, corium coolability in the reactor cavity, and molten-corium interaction with concrete. The phenomenology of severe accidents is extremely complex. In this paper, a sampling-based phenomenological uncertainty analysis was performed to statistically quantify uncertainties associated with the pressure load of a containment building for a late containment failure evaluation, based on the key modeling parameters employed in the MAAP code and random samples for those parameters. Phenomenological issues surrounding the late containment failure mode are highly complex. Included are the pressurization owing to steam generation in the cavity, molten corium-concrete interaction, late hydrogen burn in the containment, and the secondary heat removal availability. The methodology and calculation results can be applied for the optimum assessment of a late containment failure model. The accident sequences considered were a loss of coolant accidents and loss of offsite accidents expected in the OPR-1000 plant. As a result, uncertainties addressed in the pressure load of the containment building were quantified as a function of time. A realistic evaluation of the mean and variance estimates provides a more complete


    Buckley, R.; Hunter, C.


    The United States Forest Service-Savannah River (USFS) routinely performs prescribed fires at the Savannah River Site (SRS), a Department of Energy (DOE) facility located in southwest South Carolina. This facility covers {approx}800 square kilometers and is mainly wooded except for scattered industrial areas containing facilities used in managing nuclear materials for national defense and waste processing. Prescribed fires of forest undergrowth are necessary to reduce the risk of inadvertent wild fires which have the potential to destroy large areas and threaten nuclear facility operations. This paper discusses meteorological observations and numerical model simulations from a period in early 2002 of an incident involving an early-morning multicar accident caused by poor visibility along a major roadway on the northern border of the SRS. At the time of the accident, it was not clear if the limited visibility was due solely to fog or whether smoke from a prescribed burn conducted the previous day just to the northwest of the crash site had contributed to the visibility. Through use of available meteorological information and detailed modeling, it was determined that the primary reason for the low visibility on this night was fog induced by meteorological conditions.

  18. Risk forecasting and evaluating model of Environmental pollution accident

    ZENG Wei-hua; CHENG Sheng-tong


    Environmental risk (ER) fact ore come from ER source and they are controlled by the primary control mechanism (PCM) of environmental risk, due to the self failures or the effects of external environment risk trigger mechanism, the PCM could not work regularly any more, then, the ER factore will release environmental space, and an ER field is formed up. The forming of ER field does not mean that any environmental pollution accident(EPA) will break out; only the ER receptore are exposed in the ER field and damaged seriously,the potential ER really turns into an actual EPA. Researching on the general laws of evolving from environmental risk to EPA, this paper bring forwards a relevant concept model of risk forecasting and evaluating of EPA. This model provides some scientific methods for risk evaluation, prevention and emergency response of EPA. This model not only enriches and develops the theory system of environment safety and emergency response, but also acts as an instruction for public safety, enterprise' s safety management and emergency response of the accident.

  19. Radiation accident at Mayapuri scrap market, Delhi, 2010.

    Dey, A B; Mohanan, Sandeep; Damodaran, Deepak; Soneja, Manish; Jain, Neetu; Mohan, Anant; Vikram, Naval Kishore; Sood, Rita


    This article reports the accidental public radiation exposure in a scrap market in Delhi, India, on March 2010. The source, a gamma unit containing Cobalt-60 pencils, was improperly disposed of by a research institution in violation of national regulations for radiation protection and safety of radioactive sources. The unit was sold off to unsuspecting scrap dealers who dismantled the equipment. This event subsequently caused the most severe radiation accident reported in India to date, resulting in seven radiation injuries and one death. The clinical course of five of the patients treated at the All India Institute of Medical Sciences hospital, New Delhi, is summarised in this report. All five patients suffered from the haematological form of the acute radiation syndrome and local cutaneous radiation injury as well. While four patients exposed to doses between 0.6 and 2.8 Gy survived with intensive or supportive treatment, the patient with the highest exposure of 3.1 Gy died due to acute respiratory distress syndrome and multi-organ failure on Day 16 after hospitalisation. The incident highlights the current gaps in the knowledge, infrastructure and legislation in handling radioactive materials. Medical institutions need to formulate individualised triage and management guidelines to immediately respond to future public radiological accidents.

  20. Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario

    Rempe, J. L. [Rempe and Associates, LLC, Idaho Falls, ID (United States); Knudson, D. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lutz, R. J. [Lutz Nuclear Safety Consultant, LLC, Asheville, NC (United States)


    The accidents at the Three Mile Island Unit 2 (TMI-2) and Fukushima Daiichi Units 1, 2, and 3 nuclear power plants demonstrate the critical importance of accurate, relevant, and timely information on the status of reactor systems during a severe accident. These events also highlight the critical importance of understanding and focusing on the key elements of system status information in an environment where operators may be overwhelmed with superfluous and sometimes conflicting data. While progress in these areas has been made since TMI-2, the events at Fukushima suggests that there may still be a potential need to ensure that critical plant information is available to plant operators. Recognizing the significant technical and economic challenges associated with plant modifications, it is important to focus on instrumentation that can address these information critical needs. As part of a program initiated by the Department of Energy, Office of Nuclear Energy (DOE-NE), a scoping effort was initiated to assess critical information needs identified for severe accident management and mitigation in commercial Light Water Reactors (LWRs), to quantify the environment instruments monitoring this data would have to survive, and to identify gaps where predicted environments exceed instrumentation qualification envelop (QE) limits. Results from the Pressurized Water Reactor (PWR) scoping evaluations are documented in this report. The PWR evaluations were limited in this scoping evaluation to quantifying the environmental conditions for an unmitigated Short-Term Station BlackOut (STSBO) sequence in one unit at the Surry nuclear power station. Results were obtained using the MELCOR models developed for the US Nuclear Regulatory Commission (NRC)-sponsored State of the Art Consequence Assessment (SOARCA) program project. Results from this scoping evaluation indicate that some instrumentation identified to provide critical information would be exposed to conditions that

  1. Research of 3S Technology in Management Emergency of Urban Trafifc Accident%基于3S技术的道路交通应急管理研究

    徐彩丽; 栾金金; 杨现青; 任传祥


    本文通过对我国当前的交通现状进行分析理解,结合近几年国家对交通建设提出的要求,进而对国内道路交通应急管理进行了解分析。在阐述3S工作的基本原理的基础上,结合3S技术在道路应急管理中的应用案例进行分析,以期将3S技术在交通领域更好地推广与发展,最终实现交通的智能化目标。为人们的生活、娱乐、出行等带来方便,推动和谐社会的构建。%This article based on the traffic situation to analyze our current status of transportation in our country, combined with the requirements of the proposed transportation construction, and thus the domestic road traffic management to understand the contingency analysis . In this paper the basic principle of 3S work on the basis of combining the application of 3S technology in road emergency management case analysis, in the hope of the 3S technology in the field of traffic better promotion and development, and finally achieve the aim of intelligent traffic. For the life of people bring convenience, entertainment, travel, to promote the building of a harmonious society.

  2. Violent deaths among composers (accidents, drownings and murders)

    Breitenfeld, Darko; Vodanović, Marijo; Akrap, Ankica; Juran, Dominik; Kranjčec, Darko; Vuksanović, Marina


    In this study, we described different accidents, drowning and murders as the main cause of death among 145 composers. We included accidents (48 composers), drowning (26 composers) and murders (71 composers) which were mainly fatal, and premature. Accidents are the third leading cause of deaths today. Murders were often during the wars and revolutions (World War I, II, French, Russian revolution). We mentioned all of the etiologies of these accidents, drowning and murders according to the c...

  3. Towards Improving Crash Data Management System in Gulf Countries

    Dr. Jamal Almatawah


    Full Text Available Scientific and analytical approaches to accident data collection, storage and analysis are essential in dealing with road safety problems. Police accident records in the majority of countries form the main (and sometimes the only source of accident data. Access to the accident database is also important to identifying specific safety problems and evaluating the effectiveness of the countermeasure introduced. Accident data collection and analysis offered by technological innovation such as Electronic Data Entry (EDE, Electronic Data transfer (EDT, and Geographic Information system (GIS are implemented in developed countries. Developing countries, including the Gulf countries, should take advantage of the experience of developed countries on how the advance accident data management system works to identifying, more accurately, the main factors contributing to traffic accident. The main purpose of this research is to provide information on accident statistics process in Virginia state, starting from the time of accident occurring until it is stored in the database, with the aim of using it towards improving the process of collecting and maintaining accident data system in Gulf countries. The task is performed by reviewing the relevant international literature and interviewing police officers in charge and academic researchers in order to compare the accident data management system and also the quality of the data. Recommendations towards developing the crash data management system will be obtained based on the research results and international experience.

  4. Accidents due to falls from roof slabs

    Bruno Alves Rudelli

    Full Text Available CONTEXT AND OBJECTIVE Falls from the roof slabs of houses are accidents of high potential severity that occur in large Brazilian cities and often affect children and adolescents. The aims of this study were to characterize the factors that predispose towards this type of fall involving children and adolescents, quantify the severity of associated lesions and suggest preventive measures. DESIGN AND SETTING Descriptive observational prospective longitudinal study in two hospitals in the metropolitan region of São Paulo. METHODS Data were collected from 29 cases of falls from roof slabs involving children and adolescents between October 2008 and October 2009. RESULTS Cases involving males were more prevalent, accounting for 84%. The predominant age group was schoolchildren (7 to 12 years old; 44%. Leisure activities were most frequently being practiced on the roof slab at the time of the fall (86%, and flying a kite was the most prevalent game (37.9%. In 72% of the cases, the children were unaccompanied by an adult responsible for them. Severe conditions such as multiple trauma and traumatic brain injuries resulted from 79% of the accidents. CONCLUSION Falls from roof slabs are accidents of high potential severity, and preventive measures aimed towards informing parents and guardians about the dangers and risk factors associated with this type of accident are needed, along with physical protective measures, such as low walls around the slab and gates with locks to restrict free access to these places.

  5. Severe Accident Test Station Activity Report

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


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

  6. ANS severe accident program overview & planning document

    Taleyarkhan, R.P.


    The Advanced Neutron Source (ANS) severe accident document was developed to provide a concise and coherent mechanism for presenting the ANS SAP goals, a strategy satisfying these goals, a succinct summary of the work done to date, and what needs to be done in the future to ensure timely licensability. Guidance was received from various bodies [viz., panel members of the ANS severe accident workshop and safety review committee, Department of Energy (DOE) orders, Nuclear Regulatory Commission (NRC) requirements for ALWRs and advanced reactors, ACRS comments, world-wide trends] were utilized to set up the ANS-relevant SAS goals and strategy. An in-containment worker protection goal was also set up to account for the routine experimenters and other workers within containment. The strategy for achieving the goals is centered upon closing the severe accident issues that have the potential for becoming certification issues when assessed against realistic bounding events. Realistic bounding events are defined as events with an occurrency frequency greater than 10{sup {minus}6}/y. Currently, based upon the level-1 probabilistic risk assessment studies, the realistic bounding events for application for issue closure are flow blockage of fuel element coolant channels, and rapid depressurization-related accidents.

  7. Diving Accidents. Analyses of Underlying Variables.


    Nitrogen narcosis 3 0.3 bad gas 3 0.3 Total 1,036 100.1 1,033 100.2 Another factor of potential relevance in mishap occurrence was the time of day...exposure air, and nitrogen -oxygen equivalent air were all at relatively high risk of terminating in a mishap. Accident rates for the other variables

  8. Accidents with biological material in workers

    Cleonice Andréa Alves Cavalcante


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

  9. [Current situation of accidents in the world].

    Aguilar-Zinser, José Valente


    According to the World Health Organization (WHO), the number of traffic accidents is of concern. About 1.2 million people die every year on the roadways and about 20 to 50 million suffer from non-lethal trauma. Countries with low or medium incomes have higher rates of lethality by traffic accidents (21.5 and 19.5 per 100,000 habitants, respectively) than countries with higher incomes (10.3 per 100,000). It is estimated that the cost of traffic accidents in countries that are members of the Organization for Economic Cooperation and Development (OECD), escalate to rates that are between 2-5% of the gross domestic product (GDP). According to data from the health sector in Mexico, these rates are equivalent to 1.3 of GDR The WHO foresees that traffic accident traumas will rise to be the third cause of mortality in 2030. Because of the high complexity of the transport sector, it is necessary that the Transport and Communication Ministry works in a multidisciplinary and intersectorial fashion to ensure that the land transportation systems operate effectively in accordance with national economic development and the quality of life of the Mexican people.

  10. Chernobyl accident. [Radiation monitoring in UK

    Gittus, J.H.


    A brief report is given of the implications for the UK from the radioactivity released during the Chernobyl accident. Results of radio-activity monitoring around the UK are given and the additional radiation doses to the UK population are evaluated.

  11. Speed Variance and Its Influence on Accidents.

    Garber, Nicholas J.; Gadirau, Ravi

    A study was conducted to investigate the traffic engineering factors that influence speed variance and to determine to what extent speed variance affects accident rates. Detailed analyses were carried out to relate speed variance with posted speed limit, design speeds, and other traffic variables. The major factor identified was the difference…

  12. Fatal accidents among Danes with multiple sclerosis

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


    We compared the rate of fatal accidents among Danes with multiple sclerosis (MS) with that of the general population. The study was based on linkage of the Danish Multiple Sclerosis Registry to the Cause of Death Registry and covered all 10174 persons in whom MS was diagnosed during the period 1953...

  13. Analysis of Credible Accidents for Argonaut Reactors

    Hawley, S. C.; Kathern, R. L.; Robkin, M. A.


    Five areas of potential accidents have been evaluated for the Argonaut-UTR reactors. They are: • insertion of excess reactivity • catastrophic rearrangement of the core • explosive chemical reaction • graphite fire • fuel-handling accident. A nuclear excursion resulting from the rapid insertion of the maximum available excess reactivity would produce only 12 MWs which is insufficient to cause fuel melting even with conservative assumptions. Although precise structural rearrangement of the core would create a potential hazard, it is simply not credible to assume that such an arrangement would result from the forces of an earthquake or other catastrophic event. Even damage to the fuel from falling debris or other objects is unlikely given the normal reactor structure. An explosion from a metal-water reaction could not occur because there is no credible source of sufficient energy to initiate the reaction. A graphite fire could conceivably create some damage to the reactor but not enough to melt any fuel or initiate a metal-water reaction. The only credible accident involving offsite doses was determined to be a fuel-handling accident which, given highly conservative assumptions, would produce a whole-body dose equivalent of 2 rem from noble gas immersion and a lifetime dose equivalent commitment to the thyroid of 43 rem from radioiodines.

  14. Inventory of socioeconomic costs of work accidents

    Mossink, J.; Greef, M. de


    The European Commission has prioritised the need to develop knowledge of the economic and social costs arising from occupational accidents and illnesses in their communication about a new Community strategy on safety and health at work for 2002-06. This report from the Agency aims to contribute to t

  15. Facial trauma among victims of terrestrial transport accidents

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


    ABSTRACT INTRODUCTION: In developing countries, terrestrial transport accidents - TTA, especially those involving automobiles and motorcycles - are a major cause of facial trauma, surpassing urban violence. OBJECTIVE: This cross-sectional census study attempted to determine facial trauma occurrence with terrestrial transport accidents etiology, involving cars, motorcycles, or accidents with pedestrians in the northeastern region of Brazil, and examine victims' socio-demographic characteri...

  16. 48 CFR 652.236-70 - Accident Prevention.


    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Accident Prevention. 652... SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and Clauses 652.236-70 Accident Prevention. As prescribed in 636.513, insert the following clause: Accident Prevention (APR 2004) (a) General....

  17. 48 CFR 52.236-13 - Accident Prevention.


    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Accident Prevention. 52.236-13 Section 52.236-13 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION....236-13 Accident Prevention. As prescribed in 36.513, insert the following clause: Accident...

  18. Concussion in Motor Vehicle Accidents: The Concussion Identification Index


    Motor Vehicle Accidents; TBI (Traumatic Brain Injury); Brain Contusion; Brain Injuries; Cortical Contusion; Concussion Mild; Cerebral Concussion; Brain Concussion; Accidents, Traffic; Traffic Accidents; Traumatic Brain Injury With Brief Loss of Consciousness; Traumatic Brain Injury With no Loss of Consciousness; Traumatic Brain Injury With Loss of Consciousness

  19. [Fatal electric arc accidents due to high voltage].

    Strauch, Hansjürg; Wirth, Ingo


    The frequency of electric arc accidents has been successfully reduced owing to preventive measures taken by the professional association. However, the risk of accidents has continued to exist in private setting. Three fatal electric arc accidents caused by high voltage are reported with reference to the autopsy findings.

  20. 49 CFR 178.345-8 - Accident damage protection.


    ... or more than 2 inches from the point of attachment to the tank must have accident damage protection... accident damage protection device; or (iii) Attached to the cargo tank in accordance with the requirements... damaged in an accident could result in a loss of lading from the cargo tank must be protected by...

  1. The case for research into the zero accident vision

    Zwetsloot, G.I.J.M.; Aaltonen, M.; Wybo,J.L.; Saari, J.; Kines, P.; Beeck, R. op de


    This discussion paper is written out of a concern. We noticed that many companies with a good safety reputation have adopted a zero accident vision, yet there is very little scientific research in this field. The zero accident vision addresses the accidents causing deaths and severe injuries among c

  2. Severe Accident Test Station Design Document

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


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

  3. Recommendation for environmental management and safety systems in high risk industrial accidents; Linee guida per l'integrazione dei sistemi di gestione ambiente e sicurezza nelle aziende a rischio di incidente rilevante

    Luciani, R.; Andriola, L.; Caropresso, G.; Paci, S.; Vignati, S.; Vignoni, P.C. [ENEA Centro Ricerche Casaccia, Rome (Italy). Dipt. Ambiente


    This document presents the IMPREMAS Project from Italian ENEA (National Agency for New Technology, Energy and the Environment) for the eco-management of small and medium enterprises at risk for se and manipulation of hazardous substances. [Italian] Il presente documento e' stato elaborato nell'ambito del progetto IMPREMAS condotto dall'ENEA, in collaborazione con il Ministero dell'Ambiente, Regione Lombardia, Federchimica e Finlombarda, per la realizzazione di un progetto pilota per l'eco-gestione delle piccole e medie imprese classificate a rischio per l'uso e lo stoccaggio di sostanze pericolose previste dal DPR. n. 175 del 17-5-1988. L'azione ha riguardato l'applicazione del regolamento EMAS 1836/93 congiuntamente alla implementazione di un sistema di sicurezza per piccole e medie imprese a rischio di incidente rilevante del settore chimico-farmaceutico con l'obiettivo di mettere a punto le linee guida di riferimento per l'integrazione dei sistemi ambiente e sicurezza.

  4. Decision support system for containment and release management

    Oosterhuis, B. [Twente Univ., Enschede (Netherlands). Computer Science Dept.


    The Containment and Release Management project was carried out within the Reinforced Concerted Action Programme for Accident Management Support and partly financed by the European Union. In this report a prototype of an accident management support system is presented. The support system integrates several concepts from accident management research, like safety objective trees, severe accident phenomena, calculation models and an emergency response data system. These concepts are provided by the prototype in such a way that the decision making process of accident management is supported. The prototype application is demonstrated by process data taken from a severe accident scenario for a pressurized water reactor (PWR) that was simulated with the thermohydraulic computer program MAAP. The prototype was derived from a decision support framework based on a decision theory. For established and innovative concepts from accident management research it is pointed out in which way these concepts can support accident management and how these concepts can be integrated. This approach is generic in two ways; it applies to both pressurized and boiling water reactors and it applies to both in vessel management and containment and release management. The prototype application was developed in Multimedia Toolbox 3.0 and requires at least a 386 PC with 4 MB memory, 6 MB free disk space and MS Windows 3.1. (orig.).

  5. Skills development at a paramedic accident simulation centre.

    Donaghy, John


    Practice simulation in acute and pre-hospital care settings is a growing area of interest for clinicians and health educationalists, and there is much evidence to support its use (Pike and O'Donnell 2010). Most simulation is delivered through computer-aided software or in virtual environments, however last year the University of Hertfordshire opened an accident simulation centre which is an outdoor facility that offers pre- and post-registration paramedics the opportunity to experience a range of scenarios in a 'real life' but secure environment. This article describes how the centre enables students to apply theory to practice in complex situations, such as managing patients injured in road traffic collisions.

  6. Do failures in non-technical skills contribute to fatal medical accidents in Japan? A review of the 2010–2013 national accident reports

    Uramatsu, Masashi; Fujisawa, Yoshikazu; Mizuno, Shinya; Souma, Takahiro; Komatsubara, Akinori; Miki, Tamotsu


    Objectives We sought to clarify how large a proportion of fatal medical accidents can be considered to be caused by poor non-technical skills, and to support development of a policy to reduce number of such accidents by making recommendations about possible training requirements. Design Summaries of reports of fatal medical accidents, published by the Japan Medical Safety Research Organization, were reviewed individually. Three experienced clinicians and one patient safety expert conducted the reviews to determine the cause of death. Views of the patient safety expert were given additional weight in the overall determination. Setting A total of 73 summary reports of fatal medical accidents were reviewed. These reports had been submitted by healthcare organisations across Japan to the Japan Medical Safety Research Organization between April 2010 and March 2013. Primary and secondary outcome measures The cause of death in fatal medical accidents, categorised into technical skills, non-technical skills and inevitable progress of disease were evaluated. Non-technical skills were further subdivided into situation awareness, decision making, communication, team working, leadership, managing stress and coping with fatigue. Results Overall, the cause of death was identified as non-technical skills in 34 cases (46.6%), disease progression in 33 cases (45.2%) and technical skills in two cases (5.5%). In two cases, no consensual determination could be achieved. Further categorisation of cases of non-technical skills were identified as 14 cases (41.2%) of problems with situation awareness, eight (23.5%) with team working and three (8.8%) with decision making. These three subcategories, or combinations of them, were identified as the cause of death in 33 cases (97.1%). Conclusions Poor non-technical skills were considered to be a significant cause of adverse events in nearly half of the fatal medical accidents examined. Improving non-technical skills may be effective for

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

    Prato, Carlo Giacomo; Kaplan, Sigal


    examining occurrence of injury to bus passengers. Results Bus accident severity is positively related to (i) the involvement of vulnerable road users, (ii) high speed limits, (iii) night hours, (iv) elderly drivers of the third party involved, and (v) bus drivers and other drivers crossing in yellow or red...... principle of sustainable transit and advance the vision “every accident is one too many”. Methods Bus accident data were retrieved from the national accident database for the period 2002–2011. A generalized ordered logit model allows analyzing bus accident severity and a logistic regression enables...

  8. Analysis of surface powered haulage accidents, January 1990--July 1996

    Fesak, G.M.; Breland, R.M.; Spadaro, J. [Dept. of Labor, Arlington, VA (United States)


    This report addresses surface haulage accidents that occurred between January 1990 and July 1996 involving haulage trucks (including over-the-road trucks), front-end-loaders, scrapers, utility trucks, water trucks, and other mobile haulage equipment. The study includes quarries, open pits and surface coal mines utilizing self-propelled mobile equipment to transport personnel, supplies, rock, overburden material, ore, mine waste, or coal for processing. A total of 4,397 accidents were considered. This report summarizes the major factors that led to the accidents and recommends accident prevention methods to reduce the frequency of these accidents.

  9. Comparative Assessment of Severe Accidents in the Chinese Energy Sector

    Hirschberg, S.; Burgherr, P.; Spiekerman, G.; Cazzoli, E.; Vitazek, J.; Cheng, L


    This report deals with the comparative assessment of accidents risks characteristic for the various electricity supply options. A reasonably complete picture of the wide spectrum of health, environmental and economic effects associated with various energy systems can only be obtained by considering damages due to normal operation as well as due to accidents. The focus of the present work is on severe accidents, as these are considered controversial. By severe accidents we understand potential or actual accidents that represent a significant risk to people, property and the environment and may lead to large consequences. (author)

  10. ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives

    Chatelard, P., E-mail: [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES, B.250, Cadarache BP3 13115, Saint-Paul-lez-Durance, Cedex (France); Reinke, N.; Arndt, S. [Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Schwertnergasse 1, 50677 Köln (Germany); Belon, S.; Cantrel, L.; Carenini, L.; Chevalier-Jabet, K.; Cousin, F. [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES, B.250, Cadarache BP3 13115, Saint-Paul-lez-Durance, Cedex (France); Eckel, J. [Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Schwertnergasse 1, 50677 Köln (Germany); Jacq, F.; Marchetto, C.; Mun, C.; Piar, L. [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN-RES, B.250, Cadarache BP3 13115, Saint-Paul-lez-Durance, Cedex (France)


    The severe accident integral code ASTEC, jointly developed since almost 20 years by IRSN and GRS, simulates the behaviour of a whole nuclear power plant under severe accident conditions, including severe accident management by engineering systems and procedures. Since 2004, the ASTEC code is progressively becoming the reference European severe accident integral code through in particular the intensification of research activities carried out in the frame of the SARNET European network of excellence. The first version of the new series ASTEC V2 was released in 2009 to about 30 organizations worldwide and in particular to SARNET partners. With respect to the previous V1 series, this new V2 series includes advanced core degradation models (issued from the ICARE2 IRSN mechanistic code) and necessary extensions to be applicable to Gen. III reactor designs, notably a description of the core catcher component to simulate severe accidents transients applied to the EPR reactor. Besides these two key-evolutions, most of the other physical modules have also been improved and ASTEC V2 is now coupled to the SUNSET statistical tool to make easier the uncertainty and sensitivity analyses. The ASTEC models are today at the state of the art (in particular fission product models with respect to source term evaluation), except for quenching of a severely damage core. Beyond the need to develop an adequate model for the reflooding of a degraded core, the main other mean-term objectives are to further progress on the on-going extension of the scope of application to BWR and CANDU reactors, to spent fuel pool accidents as well as to accidents in both the ITER Fusion facility and Gen. IV reactors (in priority on sodium-cooled fast reactors) while making ASTEC evolving towards a severe accident simulator constitutes the main long-term objective. This paper presents the status of the ASTEC V2 versions, focussing on the description of V2.0 models for water-cooled nuclear plants.

  11. The effect of roundabout design features on cyclist accident rate

    Hels, Tove; Orozova-Bekkevold, Ivanka


    yearly rate of cyclist accidents on one hand and roundabout geometry, age and traffic volume (vehicles and cyclists) on the other. We related all roundabout cyclist accidents recorded by the hospital emergency department of the town of Odense, Denmark, through the years 1999-2003 (N = 171) to various...... geometric features, age and traffic volume of all roundabouts on the Danish island of Funen (N = 88). Cyclist and vehicle volumes turned out to be significant predictors in most of our models-the higher the volumes, the more accidents. Moreover, potential vehicle speed was a significant predictor, and so...... was age of the roundabout-older roundabouts related to more accidents and higher accident probability. Excluding 48 single cyclist accidents strengthened the relationship between accidents on one hand and vehicle and cyclist volume and potential vehicle speed on the other. This stresses the significance...

  12. Decision Tree Model for Non-Fatal Road Accident Injury

    Fatin Ellisya Sapri


    Full Text Available Non-fatal road accident injury has become a great concern as it is associated with injury and sometimes leads to the disability of the victims. Hence, this study aims to develop a model that explains the factors that contribute to non-fatal road accident injury severity. A sample data of 350 non-fatal road accident cases of the year 2016 were obtained from Kota Bharu District Police Headquarters, Kelantan. The explanatory variables include road geometry, collision type, accident time, accident causes, vehicle type, age, airbag, and gender. The predictive data mining techniques of decision tree model and multinomial logistic regression were used to model non-fatal road accident injury severity. Based on accuracy rate, decision tree with CART algorithm was found to be more accurate as compared to the logistic regression model. The factors that significantly contribute to non-fatal traffic crashes injury severity are accident cause, road geometry, vehicle type, age and collision type.

  13. A Study on the Operation Strategy for Combined Accident including TLOFW accident

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


    It is difficult for operators to recognize the necessity of a feed-and-bleed (F-B) operation when the loss of coolant accident and failure of secondary side occur. An F-B operation directly cools down the reactor coolant system (RCS) using the primary cooling system when residual heat removal by the secondary cooling system is not available. The plant is not always necessary the F-B operation when the secondary side is failed. It is not necessary to initiate an F-B operation in the case of a medium or large break because these cases correspond to low RCS pressure sequences when the secondary side is failed. If the break size is too small to sufficiently decrease the RCS pressure, the F-B operation is necessary. Therefore, in the case of a combined accident including a secondary cooling system failure, the provision of clear information will play a critical role in the operators' decision to initiate an F-B operation. This study focuses on the how we establish the operation strategy for combined accident including the failure of secondary side in consideration of plant and operating conditions. Previous studies have usually focused on accidents involving a TLOFW accident. The plant conditions to make the operators confused seriously are usually the combined accident because the ORP only focuses on a single accident and FRP is less familiar with operators. The relationship between CET and PCT under various plant conditions is important to decide the limitation of initiating the F-B operation to prevent core damage.

  14. Integrated hydrogen control solutions for severe accidents using passive autocatalytic recombiners

    Bauer, M.; Tietsch, W.; Sabate Farnos, R.


    In a severe accident or a beyond-design-basis-accident, the reaction of water with zirconium alloy cladding, radiolysis of water, corium-concrete reactions and other corrosion phenomena generate hydrogen (H2). The detonation of this H2 in containment or in auxiliary buildings can result in damage to structures or loss of containment integrity. Identifying the generation and special distribution of hydrogen and controlling its concentration with Passive Autocatalytic Recombiners (PARs) solves this concern. Westinghouse's approach for hydrogen management starts by defining the quantities and transport/distribution of H{sub 2} in-containment and out of containment with analysis tools such as MAAP, MELCOR, GASFLOW or FATE. Based on the results of these analyses, an optimized H2 Control Strategy is proposed in terms of number and location of PARs, and efficient integration with other H{sub 2} management devices like e.g. existing igniters, H{sub 2} monitors, etc.

  15. Research on safety management shell in coal mine

    LI Hong-xia(李红霞); TIAN Shui-cheng(田水承); YU Zhong-ming(郁钟铭); CHEN Yong-gang(陈勇刚)


    Based on the shell (jieke) theory investigation of accident prevention in coal mine, submited a new definition of safety management shell, and analyzed causes on the lack of accident prevention, then pointed that the strength of research and practice of safety management is necessary to format enduring safety in coal mine.

  16. Major accident analysis and prevention of coal mines in China from the year of 1949 to 2009

    Wu Lirong; Jiang Zhongan; Cheng Weimin; Zuo Xiuwei; Lv Dawei; Yao Yujing


    From the year of 1949 to the present,the China national coal output has been increasing quickly and became first in the world in 2009.But at the same time,major coal mining accidents still exist nowadays.In order to review the overall situation and provide information on major accidents of coal mines in China,we investigated 26 major coal mining accidents in China between the years of 1949 and 2009 through statistical methods,each of which led to more than 1 00 fatalities.Statistical characteristics about accident-related factors such as time,death toll,accident reasons,characters and nature of enterprise were analyzed.And some special conclusions have been achieved.For example,although we have made great progress,the safety situation in China coal mining industry is still serious,and the reasons for the mining accidents are all human errors which are not inevitable.Such results may be helpful to prevent major accidents in coal mines.Moreso,based on both the knowledge of other countries which have good safety situation nowadays and the safety management situation of China,we made suggestion on safety management of China coal mining.In conclusion,countermeasures were proposed in accordance with the results of statistical studies and the analyses of problems existed in coal mines,including the perfection of safety supervision organization,the establishment of cooperating agency among government,coal mines and workers,the perfection of safety rules and regulations,the improvement of safety investment,the enhancement of safety training,the development of safety technique,and the development of emergency rescue technique and equipment.

  17. Estimating the frequency of nuclear accidents

    Raju, Suvrat


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

  18. Accident characteristics of injured motorcyclists in Malaysia.

    Pang, T Y; Umar, R S; Azhar, A A; Ahmad, M M; Nasir, M T; Harwant, S


    This study examines the accident characteristics of injured motorcyclists in Malaysia. The aim of this study is to identify the characteristics of motorcyclists who are at higher fatality risk and subsequently be the targeted group for the fatality-reduction countermeasures. A total of 412 motorcycle crash victims with serious or fatal injuries were analysed. The results showed that the injured motorcyclists were predominant young, novice riders of less than 3 years licensure and male. A fatal outcome was more likely to be associated with a larger engine capacity motorcycle, collision with a heavy vehicle, head on collision, and collision at a non-junction road. In contrast, a non-fatal outcome was more likely to be associated with a small engine capacity motorcycle, collision with another motorcycle or passenger car, junction accidents, and side or rear collisions.

  19. On Hobbes’s distinction of accidents

    Lupoli Agostino


    Full Text Available An interpolation introduced by K. Schuhmann in his critical edition of "De corpore" (chap. VI, § 13 diametrically overturns the meaning of Hobbes’s doctrine of distinction of accidents in comparison with all previous editions. The article focuses on the complexity of this crucial juncture in "De corpore" argument on which depends the interpretation of Hobbes’s whole conception of science. It discusses the reasons pro and contra Schuhmann’s interpolation and concludes against it, because it is not compatible with the rationale underlying the complex architecture of "De corpore", which involves a symmetry between the ‘logical’ distinction of accidents and the ‘metaphysical’ distinction of phantasms.

  20. BMX bicycles: accident comparison with other models.


    A comparison has been made between BMX bicycle accidents and those occurring when children ride other types of bicycle. The injuries sustained are compared to see if the clinical impressions that BMX are more dangerous, and produce more facial injuries, are correct. This was found not to be true as half the children involved rode BMX bicycles, and the injuries sustained were similar to those occurring to non BMX riders. BMX riders had a lower proportion of serious injuries than riders of raci...

  1. The dominance of accidents caused by banalities

    Jørgensen, Kirsten

    Most prevention analysis is focused on high risks, such as explosion, fire, lack of containment for chemicals, crashes in transportation systems, lack of oxygen, or chemical poisoning. In the industrial world, these kinds of risk still lead to incidents with huge consequences, albeit very seldom...... as an example of how much information such systems can offer in general for the work of accident prevention in more traditional and common enterprises....

  2. Human and organisational factors in maritime accidents: analysis of collisions at sea using the HFACS.

    Chauvin, Christine; Lardjane, Salim; Morel, Gaël; Clostermann, Jean-Pierre; Langard, Benoît


    Over the last decade, the shipping industry has implemented a number of measures aimed at improving its safety level (such as new regulations or new forms of team training). Despite this evolution, shipping accidents, and particularly collisions, remain a major concern. This paper presents a modified version of the Human Factors Analysis and Classification System, which has been adapted to the maritime context and used to analyse human and organisational factors in collisions reported by the Marine Accident and Investigation Branch (UK) and the Transportation Safety Board (Canada). The analysis shows that most collisions are due to decision errors. At the precondition level, it highlights the importance of the following factors: poor visibility and misuse of instruments (environmental factors), loss of situation awareness or deficit of attention (conditions of operators), deficits in inter-ship communications or Bridge Resource Management (personnel factors). At the leadership level, the analysis reveals the frequent planning of inappropriate operations and non-compliance with the Safety Management System (SMS). The Multiple Accident Analysis provides an important finding concerning three classes of accidents. Inter-ship communications problems and Bridge Resource Management deficiencies are closely linked to collisions occurring in restricted waters and involving pilot-carrying vessels. Another class of collisions is associated with situations of poor visibility, in open sea, and shows deficiencies at every level of the socio-technical system (technical environment, condition of operators, leadership level, and organisational level). The third class is characterised by non-compliance with the SMS. This study shows the importance of Bridge Resource Management for situations of navigation with a pilot on board in restricted waters. It also points out the necessity to investigate, for situations of navigation in open sea, the masters' decisions in critical conditions

  3. [Violence and accidents among older and younger adults: evidence from the Surveillance System for Violence and Accidents (VIVA), Brazil].

    Luz, Tatiana Chama Borges; Malta, Deborah Carvalho; Sá, Naíza Nayla Bandeira de; Silva, Marta Maria Alves da; Lima-Costa, Maria Fernanda


    Data from the Brazilian Surveillance System for Violence and Accidents (VIVA) in 2009 were used to examine socio-demographic characteristics, outcomes, and types of accidents and violence treated at 74 sentinel emergency services in 23 Brazilian State capitals and the Federal District. The analysis included 25,201 individuals aged > 20 years (10.1% > 60 years); 89.3% were victims of accidents and 11.9% victims of violence. Hospitalization was the outcome in 11.1% of cases. Compared to the general population, there were more men and non-white individuals among victims of accidents, and especially among victims of violence. As compared to younger adults (20-59 years), accidents and violence against elderly victims showed less association with alcohol, a higher proportion of domestic incidents, more falls and pedestrian accidents, and aggression by family members. Policies for the prevention of accidents and violence should consider the characteristics of these events in the older population.

  4. Radiological protection issues arising during and after the Fukushima nuclear reactor accident.

    González, Abel J; Akashi, Makoto; Boice, John D; Chino, Masamichi; Homma, Toshimitsu; Ishigure, Nobuhito; Kai, Michiaki; Kusumi, Shizuyo; Lee, Jai-Ki; Menzel, Hans-Georg; Niwa, Ohtsura; Sakai, Kazuo; Weiss, Wolfgang; Yamashita, Shunichi; Yonekura, Yoshiharu


    Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP. While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with 'contamination' of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information. Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled. It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of potential

  5. Accident prevention in a contextual approach

    Dyhrberg, Mette Bang


    Many recommendations on how to establish an accident prevention program do exist. The aim of many agencies is to promote the implementation of these recommendations in enterprises. The discussion has mainly focused on incentives either in the form of an effective enforcement of the law or as a fo......Many recommendations on how to establish an accident prevention program do exist. The aim of many agencies is to promote the implementation of these recommendations in enterprises. The discussion has mainly focused on incentives either in the form of an effective enforcement of the law...... or as a focus on developing the insurance system to establish (economic) motivation. This paper suggests a more elaborated theoretical approach emphasising a differentiated understanding of the external and internal actors and how these relations form the actions of the actors. The theoretical components...... of such a contextual approach is shortly described and demonstrated in relation to a Danish case on accident prevention. It is concluded that the approach presently offers a post-ante, descriptive analytical understanding, and it is argued that it can be developed to a frame of reference for planning actions...

  6. Calculation reliability in vehicle accident reconstruction.

    Wach, Wojciech


    The reconstruction of vehicle accidents is subject to assessment in terms of the reliability of a specific system of engineering and technical operations. In the article [26] a formalized concept of the reliability of vehicle accident reconstruction, defined using Bayesian networks, was proposed. The current article is focused on the calculation reliability since that is the most objective section of this model. It is shown that calculation reliability in accident reconstruction is not another form of calculation uncertainty. The calculation reliability is made dependent on modeling reliability, adequacy of the model and relative uncertainty of calculation. All the terms are defined. An example is presented concerning the analytical determination of the collision location of two vehicles on the road in the absence of evidential traces. It has been proved that the reliability of this kind of calculations generally does not exceed 0.65, despite the fact that the calculation uncertainty itself can reach only 0.05. In this example special attention is paid to the analysis of modeling reliability and calculation uncertainty using sensitivity coefficients and weighted relative uncertainty.

  7. Risk Estimation Methodology for Launch Accidents.

    Clayton, Daniel James; Lipinski, Ronald J.; Bechtel, Ryan D.


    As compact and light weight power sources with reliable, long lives, Radioisotope Power Systems (RPSs) have made space missions to explore the solar system possible. Due to the hazardous material that can be released during a launch accident, the potential health risk of an accident must be quantified, so that appropriate launch approval decisions can be made. One part of the risk estimation involves modeling the response of the RPS to potential accident environments. Due to the complexity of modeling the full RPS response deterministically on dynamic variables, the evaluation is performed in a stochastic manner with a Monte Carlo simulation. The potential consequences can be determined by modeling the transport of the hazardous material in the environment and in human biological pathways. The consequence analysis results are summed and weighted by appropriate likelihood values to give a collection of probabilistic results for the estimation of the potential health risk. This information is used to guide RPS designs, spacecraft designs, mission architecture, or launch procedures to potentially reduce the risk, as well as to inform decision makers of the potential health risks resulting from the use of RPSs for space missions.

  8. Emergency Responses and Health Consequences after the Fukushima Accident; Evacuation and Relocation.

    Hasegawa, A; Ohira, T; Maeda, M; Yasumura, S; Tanigawa, K


    The Fukushima accident was a compounding disaster following the strong earthquake and huge tsunami. The direct health effects of radiation were relatively well controlled considering the severity of the accident, not only among emergency workers but also residents. Other serious health issues include deaths during evacuation, collapse of the radiation emergency medical system, increased mortality among displaced elderly people and public healthcare issues in Fukushima residents. The Fukushima mental health and lifestyle survey disclosed that the Fukushima accident caused severe psychological distress in the residents from evacuation zones. In addition to psychiatric and mental health problems, there are lifestyle-related problems such as an increase proportion of those overweight, an increased prevalence of hypertension, diabetes mellitus and dyslipidaemia and changes in health-related behaviours among evacuees; all of which may lead to an increased cardiovascular disease risk in the future. The effects of a major nuclear accident on societies are diverse and enduring. The countermeasures should include disaster management, long-term general public health services, mental and psychological care, behavioural and societal support, in addition to efforts to mitigate the health effects attributable to radiation.

  9. Serious brain injury coexisting with multiple injuries caused by traffic accidents in 69 cases

    张浚; 张鹤飞; 等


    Objective To explore the speciality,diagnosis,cure principle of serious brain injury coexisting with nultiple injuries caused by traffic accidents.Methods To analyze the clinic data of 69 cases of serious rain injury combined by oter parts of injuries caused by traffic accidents received from January 1998 to April 1999.Results This type of injury took up 11.5 percent of brain injuries in the same term and 33.6 percent of serious brain injuries.The specialities of the injury are that most of them were pedestrians crashed by vehicles.Coesisting injuries including chest injury and limb fractures accounted for a large part.The brain injury usally presented profound disturbance of consciousness,being dangerous and complicated,and a high ISS value.After treatment 13 cases died,9 cases was heavily crippled,11 cases lightly crippled,and 36 cases recovered.The death was usually caused by brain injury.Conclusions Road traffic accidents increased substantially every year.Most of them are related with violating drive rules and regulations.It is important to decrease the road traffic accidents by strengthening propaganda on traffic safety and traffic management.The main principles for salvage should emphasize the importance of pre-hospital emergency rescue and the accurate diagnosis rate,especially the distinction between coma and shock.The priority should be put on those injuries threatening to life.

  10. Study of Factors Related to Accidents Occuring during the Construction Phase of Oil, Gas and Petrochemical Projects

    H Asilian Mahabadi


    Full Text Available Introduction: Construction phase in industries is a dynamic process that is naturally and intrinsically dangerous and as it becomes more complicated, the accidents rate also increases. One should note that without considering a model, one could not obtain useful and reliable information and method to prevent accidents. Therefore, to achieve useful methods for preventing accidents, it is desirable to consider a model. The general goal of this study was presentation of a model. A model is the reflection of a fact. In other words, it should be said that the model represents a system or process whose behavior can be predicted. Models are therefore used for understanding the behavior of actual terminals and show a theory in the way that covers important variables for describing phenomena and instead, ignore factors of low importance in the expression of those phenomena. Methods: This study was a research article conducted in 2004-2005 in the Assaluyeh region. Data was gathered from accident reports present in security and health records of the projects and also statistics present at the treatment centers. In this study, an analytical model (multi-regression was presented to describe the impact of effective and deep factors on the possibility of an increase in accidents leading to death, through measurement of the effects of independent variables on the dependent variables. For this purpose, the structure of 50 accidents that led to death were studied along with another 2700 accidents, and after studying the accident reports and related documents, observing operations and equipment, counseling with accident observers and an expert team of managers, supervisors and engineers, and simulation of some accidents, unsafe conditions and functions, mismanagement and use of worn out and defective tools, equipment, devices and machinery were considered as the four independent variables and the job accidents leading to death were considered as dependent

  11. Report of the Presidential Commission on the Space Shuttle Challenger Accident, Volume 1

    Rogers, W. P.; Armstrong, N. A.; Acheson, D. C.; Covert, E. E.; Feynman, R. P.; Hotz, R. B.; Kutyna, D. J.; Ride, S. K.; Rummel, R. W.; Sutter, J. F.


    The findings of the Commission regarding the circumstances surrounding the Challenger accident are reported and recommendations for corrective action are outlined. All available mission data, subsequent tests, and wreckage analyses were reviewed and specific failure scenarios were developed. The Commission concluded that the cause of the Mission 51-L accident was the failure of the pressure seal in the aft field joint of the right solid rocket motor. The failure was due to a faulty design unacceptably sensitive to a number of factors. These factors were the effects of temperature, physical dimensions, the character of materials, the effects of reuse, processing, and the reaction of the joint to dynamic loading. In addition to analyzing the material causes of the accident, the Commission examined the chain of decisions that culminated in approval of the launch. It concluded that the decision making process was flawed in several ways including (1) failure in communication resulting in a launch decision based on incomplete and misleading information, (2) a conflict between engineering data and management judgements, and (3) a NASA management structure that permitted flight safety problems to bypass key Shuttle managers.

  12. Consequences of severe nuclear accidents in Europe

    Seibert, Petra; Arnold, Delia; Mraz, Gabriele; Arnold, Nikolaus; Gufler, Klaus; Kromp-Kolb, Helga; Kromp, Wolfgang; Sutter, Philipp


    A first part of the presentation is devoted to the consequences of the severe accident in the 1986 Chernobyl NPP. It lead to a substantial radioactive contaminated of large parts of Europe and thus raised the awareness for off-site nuclear accident consequences. Spatial patterns of the (transient) contamination of the air and (persistent) contamination of the ground were studied by both measurements and model simulations. For a variety of reasons, ground contamination measurements have variability at a range of spatial scales. Results will be reviewed and discussed. Model simulations, including inverse modelling, have shown that the standard source term as defined in the ATMES study (1990) needs to be updated. Sensitive measurements of airborne activities still reveal the presence of low levels of airborne radiocaesium over the northern hemisphere which stems from resuspension. Over time scales of months and years, the distribution of radionuclides in the Earth system is constantly changing, for example relocated within plants, between plants and soil, in the soil, and into water bodies. Motivated by the permanent risk of transboundary impacts from potential major nuclear accidents, the multidisciplinary project flexRISK (see has been carried out from 2009 to 2012 in Austria to quantify such risks and hazards. An overview of methods and results of flexRISK is given as a second part of the presentation. For each of the 228 NPPs, severe accidents were identified together with relevant inventories, release fractions, and release frequencies. Then, Europe-wide dispersion and dose calculations were performed for 2788 cases, using the Lagrangian particle model FLEXPART. Maps of single-case results as well as various aggregated risk parameters were produced. It was found that substantial consequences (intervention measures) are possible for distances up to 500-1000 km, and occur more frequently for a distance range up to 100-300 km, which is in

  13. The effect of roundabout design features on cyclist accident rate.

    Hels, Tove; Orozova-Bekkevold, Ivanka


    Roundabouts are known to result in fewer traffic accidents than traditional intersections. However, this is to a lesser degree true for bicycles than for vehicles. In this paper, we aimed at establishing statistical relationships through Poisson regression and logistic regression analyses between yearly rate of cyclist accidents on one hand and roundabout geometry, age and traffic volume (vehicles and cyclists) on the other. We related all roundabout cyclist accidents recorded by the hospital emergency department of the town of Odense, Denmark, through the years 1999-2003 (N=171) to various geometric features, age and traffic volume of all roundabouts on the Danish island of Funen (N=88). Cyclist and vehicle volumes turned out to be significant predictors in most of our models-the higher the volumes, the more accidents. Moreover, potential vehicle speed was a significant predictor, and so was age of the roundabout-older roundabouts related to more accidents and higher accident probability. Excluding 48 single cyclist accidents strengthened the relationship between accidents on one hand and vehicle and cyclist volume and potential vehicle speed on the other. This stresses the significance of speed and traffic volume for traffic accidents with more than one partner involved. The 48 single cyclist accidents were significantly related to the traffic volume of cyclists only. Due to our limited number of observations, the models should be regarded as indicative.

  14. Morbidity Caused by Accidents in Children under Five Years

    Mariela Dorta Figueredo


    Full Text Available Background: Accidents or unintentional injuries are a global health problem. In addition, they are considered as one of the leading causes of morbidity in children. Objective: To describe the morbidity caused by accidents in children under the age of five years in the V Health Area in Cienfuegos. Methods: A descriptive study was conducted in Area V Polyclinic, Cienfuegos, aimed at analyzing the morbidity caused by accidents (from June to November 2008 in children from zero to five years who belonged to consultations 3, 4, 23 and 25 of that health area. The demographic variables, type of accident, cause, place of occurrence, adult presence at the time of the accident, request for medical assistance, as well as risk factors were analyzed. Results: 40.2% of the population studied had accidents and the accident frequency rate reached 48.2%. Children aged two, three and less than one year were the most affected as well as males. Falls, burns and foreign body aspiration were the most frequent accidents, occurring mostly at home. Conclusions: Unfortunately adults are not doing everything possible to reduce the occurrence of accidents. They need to be more active in the child vigilance and the elimination of potential triggering factors of the accident.

  15. Severe Accident Scoping Simulations of Accident Tolerant Fuel Concepts for BWRs

    Robb, Kevin R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)


    Accident-tolerant fuels (ATFs) are fuels and/or cladding that, in comparison with the standard uranium dioxide Zircaloy system, can tolerate loss of active cooling in the core for a considerably longer time period while maintaining or improving the fuel performance during normal operations [1]. It is important to note that the currently used uranium dioxide Zircaloy fuel system tolerates design basis accidents (and anticipated operational occurrences and normal operation) as prescribed by the US Nuclear Regulatory Commission. Previously, preliminary simulations of the plant response have been performed under a range of accident scenarios using various ATF cladding concepts and fully ceramic microencapsulated fuel. Design basis loss of coolant accidents (LOCAs) and station blackout (SBO) severe accidents were analyzed at Oak Ridge National Laboratory (ORNL) for boiling water reactors (BWRs) [2]. Researchers have investigated the effects of thermal conductivity on design basis accidents [3], investigated silicon carbide (SiC) cladding [4], as well as the effects of ATF concepts on the late stage accident progression [5]. These preliminary analyses were performed to provide initial insight into the possible improvements that ATF concepts could provide and to identify issues with respect to modeling ATF concepts. More recently, preliminary analyses for a range of ATF concepts have been evaluated internationally for LOCA and severe accident scenarios for the Chinese CPR1000 [6] and the South Korean OPR-1000 [7] pressurized water reactors (PWRs). In addition to these scoping studies, a common methodology and set of performance metrics were developed to compare and support prioritizing ATF concepts [8]. A proposed ATF concept is based on iron-chromium-aluminum alloys (FeCrAl) [9]. With respect to enhancing accident tolerance, FeCrAl alloys have substantially slower oxidation kinetics compared to the zirconium alloys typically employed. During a severe accident, Fe

  16. Occupational accidents in Russia and the Russian Arctic

    Alexey A. Dudarev


    Full Text Available Background. According to official statistics, the rate of occupational accidents (OAs and fatal injuries in Russia decreased about 5-fold and 2-fold, respectively, from 1975 to 2010, but working conditions during this period had the opposite trend; for example, the number of people who work in unfavourable and hazardous conditions (particularly since 1991 has increased significantly. Methods. This review summarises the results of a search of the relevant peer-reviewed literature published in Russia and official statistics on OAs and occupational safety in Russia and the Russian Arctic in 1980–2010. Results. The occupational safety system in Russia has severely deteriorated in the last 2 decades, with legislators tending to promote the interests of industry and business, resulting in the neglect of occupational safety and violation of workers’ rights. The majority of workers are employed in conditions that do not meet rules of safety and hygiene. More than 60% of OAs can be attributed to management practices – violation of safety regulations, poor organisation of work, deficiency of certified occupational safety specialists and inadequate personnel training. Research aimed at improving occupational safety and health is underfunded. There is evidence of widespread under-reporting of OAs, including fatal accidents. Three federal agencies are responsible for OAs recording; their data differ from each other as they use different methodologies. The rate of fatal OAs in Russia was 3–6 times higher than in Scandinavian countries and about 2 times higher compared to United States and Canada in 2001. In some Russian Arctic regions OAs levels are much higher. Conclusions. Urgent improvement of occupational health and safety across Russia, especially in the Arctic regions, is needed.

  17. Occupational accidents involving biological material among public health workers.

    Chiodi, Mônica Bonagamba; Marziale, Maria Helena Palucci; Robazzi, Maria Lúcia do Carmo Cruz


    This descriptive research aimed to recognize the occurrence of work accidents (WA) involving exposure to biological material among health workers at Public Health Units in Ribeirão Preto-SP, Brazil. A quantitative approach was adopted. In 2004, 155 accidents were notified by means of the Work Accident Communication (WAC). Sixty-two accidents (40%) involved exposure to biological material that could cause infections like Hepatitis and Aids. The highest number of victims (42 accidents) came from the category of nursing aids and technicians. Needles were responsible for 80.6% of accidents and blood was the biological material involved in a majority of occupational exposure cases. This subject needs greater attention, so that prevention measures can be implemented, which consider the peculiarities of the activities carried out by the different professional categories.

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

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


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

  19. Fatal accident distribution by age, gender and head injury, and death probability at accident scene in Mashhad, Iran, 2006-2009.

    Zangooei Dovom, Hossein; Shafahi, Yousef; Zangooei Dovom, Mehdi


    Several studies have investigated road traffic deaths, but few have compared by road user type. Iran, with an estimated 44 road traffic deaths per 100,000 population in 2002 had higher road traffic deaths than any other country for which reliable estimates can be made. So, the present study was conducted on road death data and identified fatal accident distribution by age, gender and head injury as well as the influences of age and gender on deaths at accident scenes for all road user groups. Data used in this study are on fatal road accidents recorded by forensic medicine experts of the Khorasan Razavi province in Mashhad, the capital of the province, the second largest city and the largest place of pilgrimage, immigration and tourism in Iran. Chi-square test and odds ratio were used to identify the relation of death place with age and gender in 2495 fatal road accidents from 2006 to 2009. The t-test and analysis of variance were employed for continues variable, age, to compare males' and females' mean age for all road user categories. For two genders, all three groups of fatalities (pedestrian, motorcyclist and motor vehicle occupant) had a peak at the ages of 21-30. The youngest were male motorcyclists (mean age = 28). Old pedestrians were included in road deaths very much, too. Male/female overall ratio was 3.41 and the highest male/female ratio was related to motorcyclists (14). The overall ratio of head injury to other organ injuries (torso and underbody) was 2.51 and pedestrians had the largest amount of head injury (38.2%). Regarding death at accident scene, for all road users, gender did not have any significant relation with death at the scene (P-value > 0.1); on the contrary, age had significant relation (P-value accident scenes (male/female ratio at accident sense motorcyclists 41-50 and motor vehicle occupants 31-40 died the most at accident scenes. Identifying the most endangered groups of road accident fatalities, which was conducted in this

  20. Applying the AcciMap methodology to investigate the tragic Sewol Ferry accident in South Korea.

    Lee, Samuel; Moh, Young Bo; Tabibzadeh, Maryam; Meshkati, Najmedin


    This study applies the AcciMap methodology, which was originally proposed by Professor Jens Rasmussen (1997), to the analysis of the tragic Sewol Ferry accident in South Korea on April 16, 2014, which killed 304 mostly young people and is considered as a national disaster in that country. This graphical representation, by incorporating associated socio-technical factors into an integrated framework, provides a big-picture to illustrate the context in which an accident occurred as well as the interactions between different levels of the studied system that resulted in that event. In general, analysis of past accidents within the stated framework can define the patterns of hazards within an industrial sector. Such analysis can lead to the definition of preconditions for safe operations, which is a main focus of proactive risk management systems. In the case of the Sewol Ferry accident, a lot of the blame has been placed on the Sewol's captain and its crewmembers. However, according to this study, which relied on analyzing all available sources published in English and Korean, the disaster is the result of a series of lapses and disregards for safety across different levels of government and regulatory bodies, Chonghaejin Company, and the Sewol's crewmembers. The primary layers of the AcciMap framework, which include the political environment and non-proactive governmental body; inadequate regulations and their lax oversight and enforcement; poor safety culture; inconsideration of human factors issues; and lack of and/or outdated standard operating and emergency procedures were not only limited to the maritime industry in South Korea, and the Sewol Ferry accident, but they could also subject any safety-sensitive industry anywhere in the world.

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

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


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

  2. Factors Associated with Road Accidents among Brazilian Motorcycle Couriers

    da Silva, Daniela Wosiack; Andrade, Selma Maffei de; Soares,Dorotéia Fátima Pelissari de Paula; Mathias,Thais Aidar de Freitas; Matsuo, Tiemi; de Souza, Regina Kazue Tanno


    The objective of the study was to identify factors associated with reports of road accidents, among motorcycle couriers in two medium-sized municipalities in southern Brazil. A self-administered questionnaire was answered by motorcycle couriers that had worked for at least 12 months in this profession. The outcomes analyzed were reports on accidents and serious accidents over the 12 months prior to the survey. Bivariate and multivariate analyses by means of logistic regression were carried ou...

  3. Study of Spanish mining accidents using data mining techniques

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


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

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

    Ardron, K.H.; Cain, D.G.


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



    Aviation crashes all over the world have recently been on the high rise, stemming from negligence, mechanical faults, weather, ground control errors, pilot errors, taxing and maintenance crew errors as probable reasons for such accidents. This study models the probabilistic risk assessment of runway accident hazards in Nigeria aviation sector. Six categories of runway accident hazards with their corresponding basic events were identified and modeled using fault tree analysis method of probabi...

  6. Fukushima nuclear power plant accident was preventable

    Kanoglu, Utku; Synolakis, Costas


    On 11 March 2011, the fourth largest earthquake in recorded history triggered a large tsunami, which will probably be remembered from the dramatic live pictures in a country, which is possibly the most tsunami-prepared in the world. The earthquake and tsunami caused a major nuclear power plant (NPP) accident at the Fukushima Dai-ichi, owned by Tokyo Electric Power Company (TEPCO). The accident was likely more severe than the 1979 Three Mile Island and less severe than the Chernobyl 1986 accidents. Yet, after the 26 December 2004 Indian Ocean tsunami had hit the Madras Atomic Power Station there had been renewed interest in the resilience of NPPs to tsunamis. The 11 March 2011 tsunami hit the Onagawa, Fukushima Dai-ichi, Fukushima Dai-ni, and Tokai Dai-ni NPPs, all located approximately in a 230km stretch along the east coast of Honshu. The Onagawa NPP was the closest to the source and was hit by an approximately height of 13m tsunami, of the same height as the one that hit the Fukushima Dai-ichi. Even though the Onagawa site also subsided by 1m, the tsunami did not reach to the main critical facilities. As the International Atomic Energy Agency put it, the Onagawa NPP survived the event "remarkably undamaged." At Fukushima Dai-ichi, the three reactors in operation were shut down due to strong ground shaking. The earthquake damaged all offsite electric transmission facilities. Emergency diesel generators (EDGs) provided back up power and started cooling down the reactors. However, the tsunami flooded the facilities damaging 12 of its 13 EDGs and caused a blackout. Among the consequences were hydrogen explosions that released radioactive material in the environment. It is unfortunately clear that TEPCO and Japan's principal regulator Nuclear and Industrial Safety Agency (NISA) had failed in providing a professional hazard analysis for the plant, even though their last assessment had taken place only months before the accident. The main reasons are the following. One

  7. Severe Accidents in the Energy Sector

    Hirschberg, S.; Spiekerman, G.; Dones, R


    A comprehensive database on severe accidents, with main emphasis on the ones associated with the energy sector, has been established by the Paul Scherrer Institute (PSI). Fossil energy carriers, nuclear power and hydro power are covered in ENSAD (Energy related Severe Accident Database), and the scope of work includes all stages of the analysed energy chains, i.e. exploration, extraction, transports, processing, storage and waste disposal. The database has been developed using a wide variety of sources. As opposed to the previous studies the ambition of the present work has been, whenever feasible, to cover a relatively broad spectrum of damage categories of interest. This includes apart from fatalities also serious injuries, evacuations, land or water contamination, and economic losses. Currently, ENSAD covers 13,914 accidents, of which 4290 are energy related, and 1943 are considered as severe accidents. Significant effort has been directed towards the examination of the relevance of the worldwide accident records to the Swiss specific conditions, particularly in the context of nuclear and hydro power. For example, a detailed investigation of large dam failures and their consequences was carried out. Generally, while Swiss specific aspects are emphasised, the major part of the collected and analysed data, as well as the insights gained, are considered to be of general interest. In particular, three sets of the aggregated results are provided based on world wide occurrence, on OECD countries, and on non OECD countries, respectively. Significant differences exist between the aggregated, normalised damage rates assessed for the various energy carriers: On the world wide basis, the broader picture obtained by coverage of full energy chains leads to aggregated immediate fatality rates being much higher for the fossil fuels than what one would expect if power plants only were considered. The highest rates apply to LPG, followed by hydro, oil, coal, natural gas and

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

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


    for the design basis for the installation and their associated uncertainties; consideration of hazards due to surface faulting and flooding; monitoring of hazards and periodic review of site specific hazards; strengthening the prevention of unacceptable radiological consequences to the public and the environment; preventing severe accident through strengthening the plant design basis, including strengthening the independence of level four of defense in- depth, consideration of external hazards and sufficient margins; periodic safety review; emergency preparedness; feedback of operating experience. The following examples of the IAEA requirements to mitigate the consequences of DECs are: role of the government and the regulatory body for emergency preparedness and response, strengthening severe accident mitigation measures; well defined and updated accident management program.

  9. Analysis of traffic accidents in children

    Pavlekić Snežana


    Full Text Available Introduction: Violent health damages of different origin (accidents, murders, suicides in children and youth are one of the main causes of death and disabilities in this group of population in most countries. Objective: Objective of our paper was to analyze all related factors of traffic accidents involving children and to propose adequate measures of their prevention. Method: The analysis of fatal traffic accidents of children and youth aged to 18 years on the territory of Belgrade, within the period from 1998 to 2002. Results: In relation to other forms of violent death, the traffic mortality rate in children and youth holds the leading position, accounting for 56.9% with pedestrians as the most frequent category (57.4%. The most frequent age was between 7 and 9 years (46.8% and the boys were more frequently injured than the girls. It was established that the majority of children (51.9% was either running across the street outside the pedestrian/ zebra crossings or they were carelessly running out in the street, especially in April, July, August and September. More than a half of them (55.5%, predominantly school children, were injured by the end of working week, on Thursday and Friday. Conclusion: Results of our research have shown that the traffic education of children in our region is inadequate. Due to the abovementioned, it is primarily necessary to establish long-term and permanent education of this category of population. In addition, some public investments in the City infrastructure will be required in order to reduce the risk of traffic injuries in children.

  10. Preliminary dose assessment of the Chernobyl accident

    Hull, A.P.


    From the major accident at Unit 4 of the Chernobyl nuclear power station, a plume of airborne radioactive fission products was initially carried northwesterly toward Poland, thence toward Scandinavia and into Central Europe. Reports of the levels of radioactivity in a variety of media and of external radiation levels were collected in the Department of Energy's Emergency Operations Center and compiled into a data bank. Portions of these and other data which were obtained directly from published and official reports were utilized to make a preliminary assessment of the extent and magnitude of the external dose to individuals downwind from Chernobyl. Radioactive /sup 131/I was the predominant fission product. The time of arrival of the plume and the maximum concentrations of /sup 131/I in air, vegetation and milk and the maximum reported depositions and external radiation levels have been tabulated country by country. A large amount of the total activity in the release was apparently carried to a significant elevation. The data suggest that in areas where rainfall occurred, deposition levels were from ten to one-hundred times those observed in nearby ''dry'' locations. Sufficient spectral data were obtained to establish average release fractions and to establish a reference spectra of the other nuclides in the release. Preliminary calculations indicated that the collective dose equivalent to the population in Scandinavia and Central Europe during the first year after the Chernobyl accident would be about 8 x 10/sup 6/ person-rem. From the Soviet report, it appears that a first year population dose of about 2 x 10/sup 7/ person-rem (2 x 10/sup 5/ Sv) will be received by the population who were downwind of Chernobyl within the U.S.S.R. during the accident and its subsequent releases over the following week. 32 refs., 14 figs., 20 tabs.

  11. Trend of Elevator-Related Accidents in Tehran

    Ali Khaji


    Full Text Available 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 Organization (TSFO that is officially and solely responsible to conduct rescue missions of civilians in Tehran. Results: The number of elevator accidents has increased steadily during the four year study period. During these four years here was a positive upward trend for serious injuries and mortality resulting from elevator accidents. Technical problems were the main cause with 74.5%, followed by power loss and overcapacity riding with 11.5% and 7.9%respectively. Sixty-three individuals sustained serious injury and 15 people died as a result of elevator accidents. The number of accidents was significantly higher in summer (x2=18.32, P=0.032 and a considerable proportion of incidences (54%, 947 cases out of 1819 occurred between 5 and 12 pm. Conclusions: Establishment of an organization to inspect the settings, maintenance, and repair of elevators is necessary

  12. Cellular phones and traffic accidents: an epidemiological approach.

    Violanti, J M; Marshall, J R


    Using epidemiological case-control design and logistic regression techniques, this study examined the association of cellular phone use in motor vehicles and traffic accident risk. The amount of time per month spent talking on a cellular phone and 18 other driver inattention factors were examined. Data were obtained from: (1) a case group of 100 randomly selected drivers involved in accidents within the past 2 years, and (2) a control group of 100 randomly selected licensed drivers not involved in accidents within the past 10 years. Groups were matched on geographic residence. Approximately 13% (N = 7) of the accident and 9% (N = 7) of the non-accident group reported use of cellular phones while driving. Data was obtained from Department of Motor Vehicles accident reports and survey information from study subjects. We hypothesized that increased use of cellular phones while driving was associated with increased odds of a traffic accident. Results indicated that talking more than 50 minutes per month on cellular phones in a vehicle was associated with a 5.59-fold increased risk in a traffic accident. The combined use of cellular phones and motor and cognitive activities while driving were also associated with increased traffic accident risk. Readers should be cautioned that this study: (1) consists of a small sample, (2) reveals statistical associations and not causal relationships, and (3) does not conclude that talking on cellular phones while driving is inherently dangerous.

  13. Analysis on relation between safety input and accidents

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


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

  14. Modeling accident frequency in Denmark for improving road safety

    Lyckegaard, Allan; Hels, Tove; Kaplan, Sigal

    Traffic accidents result in huge costs to society in terms of death, injury, lost productivity, and property damage. The main objective of the current study is the development of an accident frequency model that predicts the expected number of accidents on a given road segment, provided...... concerning police recorded accidents, link characteristics of the road network, traffic volumes from the national transport models are merged to estimate the model. Spatial correlation between road sections is taken into account for correcting for unobserved correlation between contiguous locations....

  15. Degloving injury of the mandibular mucosa following an extreme sport accident: a case report.

    Revuelta, Regina; Sándor, George K B


    The increasing popularity of high-risk extreme sports such as acrobatic biking, mountain biking, skateboarding, or rollerblading is becoming a notable cause of maxillofacial injuries. Dentists should, therefore, be familiar with the presentation and management of uncommon maxillofacial injuries as a result of these extreme sports. The purpose of this article was to detail a case report of a 7-year-old male with a degloving injury of the mandibular mucosa following an extreme sport accident and to present a description of the patient's multidisciplinary management and follow-up.

  16. Fessenheim plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident; Fessenheim - Rapport d'evaluation complementaire de la surete des installations nucleaires au regard de l'accident de Fukushima



    This CSA (Complementary Safety Assessment) analyses the robustness of the Fessenheim plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)


    Prescott, Steven [Idaho National Laboratory; Smith, Curtis [Idaho National Laboratory; Koonce, Tony


    The ability to better characterize and quantify safety margin is important to improved decision making about Light Water Reactor (LWR) design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the Risk Informed Safety Margin Characterization (RISMC) Pathway provides methods and tools that enable mitigation options known as risk informed margins management (RIMM) strategies. The methods and tools provided by RISMC are essential to a comprehensive and integrated RIMM approach that supports effective preservation of margin for both active and passive SSCs. In this report, we discuss the methods and technologies behind RIMM for an application focused on enhanced accident tolerance design changes for a representative nuclear power plant. We look at a variety of potential plant modifications and evaluate, using the RISMC approach, the implications to safety margin for the various strategies.

  18. Global process industry initiatives to reduce major accident hazards

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


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

  19. The classic. Review article: Traffic accidents. 1966.

    Tscherne, H


    This Classic Article is a translation of the original work by Prof. Harald Tscherne, Der Straßenunfall [Traffic Accidents]. An accompanying biographical sketch of Prof. Tscherne is available at DOI 10.1007/s11999-013-3011-x . An online version of the original German article is available as supplemental material. The Classic Article is reproduced with permission from Brüder Hollinek & Co. GesmbH, Purkersdorf, Austria. The original article was published in Wien Med Wochenschr. 1966;116:105-108. (Translated by Dr. Roman Pfeifer.).

  20. Analysis of FY79 Army Aircraft Accidents.


    materiel failure/ malfunction 1. A accident. taskerrr (E) s Jb prforanc whch evited The acronym for the 3W approach to the Investigation, fro tht rquied y... lulli , It t , 1AZ" l iil~ i ..-... lI :.].,;.’,, - ,- S !5U" i_ ’ , o ’o , "% ", . #.,""" ".’ - "-’.’’’’-. "" " "’ ."- " " " II I S.7 44’ * U 11 Imem <I

  1. Postulated accident scenarios in weapons disassembly

    Payne, S.S. [Dept. of Energy, Albuquerque, NM (United States)


    A very brief summary of three postulated accident scenarios for weapons disassembly is provided in the paper. The first deals with a tetrahedral configuration of four generic pits; the second, an infinite planar array of generic pits with varying interstitial water density; and the third, a spherical shell with internal mass suspension in water varying the size and mass of the shell. Calculations were performed using the Monte Carlo Neutron Photon transport code MCNP4A. Preliminary calculations pointed to a need for higher resolution of small pit separation regimes and snapshots of hydrodynamic processes of water/plutonium mixtures.

  2. Population around the French nuclear power plant sites: a key-parameter for crisis management and safety economics; La population autour des sites nucleaires francais: un parametre determinant pour la gestion de crise et l'analyse economique des accidents nucleaires

    PASCAL, A. [IRSN, Laboratoire d' economie de la surete, DSDP/SPIIC/LAERN, BP 17, 92262 Fontenay-aux-Roses (France)


    This paper undertakes an analysis of population around the French nuclear power plant sites, tackles the problem of evacuation planning and provides a glimpse into ongoing research at the Laboratory of Nuclear Safety Economics of the IRSN, about the cost assessment of a nuclear accident and long-term land contamination. (author)

  3. Memorandum of understanding between the Government of the Kingdom of Norway and the Government of the Kingdom of the Netherlands on early notification of a nuclear accident and exchange of safety related information concerning the operation and management of nuclear facilities


    This Agreement was concluded in implementation of the IAEA 1986 Convention on Early Notification of a Nuclear Accident. Both Governments undertake to notify each other forthwith of any abnormal radiation levels in their respective countries. They will exchange safety related information on nuclear facilities and inform each other of measures to protect the population and the environment. (NEA).

  4. Traffic accident or dumping? - Striking results of a traffic accident reconstruction.

    Nerger, Eric; Bayer, Ronny; Gärtner, Tobias; Dreßler, Jan; Ondruschka, Benjamin


    An atypical traffic accident scenario should be investigated directly at the crash site from all concerned professions, especially police men, forensic pathologists and technical experts, to get a personal overview and impression of the situation and the opportunity for interdisciplinary discussion. We present the rare case of a fatal traffic accident on a German motorway which was initially thought to be an accidental discovery of dumping a corpse. Based on autopsy findings, the technical investigation and the accident reconstruction, this case was solved as a spectacular form of a collision between a pedestrian and a bonnet-front car, which was not described elsewhere in scientific literature to the best of our knowledge. The pedestrian was hit in an upright body position, was lifted up by the car, smashed the windscreen and flew over the car with several body rotations. His flight curve ends directly at the roof of the car during brake processing, where the body touched the roof, smashed the rear-window and landed in the trunk. Based on the technical investigation, the driver of the car was not able to hide the accident. However, the pedestrian could have avoided the collision if he did not cross the motorway on foot.

  5. A concept of countermeasure against radioactive wastewater generated in disastrous nuclear accident such as Fukushima Daiichi site case

    Kim, Kwang-Wook; Lee, Keun-Young; Lee, Eil-Hee; Baek, Yeji; So, Ji-Yang; Chung, Dong-Young; Moon, Jei-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)


    Before the operation of initial wastewater treatment systems supplied by AREVA and Kurion companies, which were installed about 6 months after the accident, the contaminated water was accumulated in reactor and turbine buildings, then was moved and stored in many hurriedly-prepared storage tanks including even mega float barge. The wastewater treatment systems using Cs-adsorption columns and desalination equipment was not properly operated and there were several small and big leakages of contaminated water from the wastewater treatment system and storage tanks, so that tremendous wastewater had been accumulated during those periods. That thereafter led to many secondary problems in management and treatment of the wastewater. Since the disastrous accident at Fukushima, several measures to more enhance safety of nuclear power plants located on coastal area have been asked. As one of them, a countermeasure against generation of tremendous radioactive wastewater in disastrous nuclear accident like the Fukushima Daiichi station was asked to be prepared.

  6. The influence of economic incentives linked to road safety indicators on accidents: the case of toll concessions in Spain.

    Rangel, Thais; Vassallo, José Manuel; Herraiz, Israel


    The goal of this paper is to evaluate whether the incentives incorporated in toll highway concession contracts in order to encourage private operators to adopt measures to reduce accidents are actually effective at improving safety. To this end, we implemented negative binomial regression models using information about highway characteristics and accident data from toll highway concessions in Spain from 2007 to 2009. Our results show that even though road safety is highly influenced by variables that are not managed by the contractor, such as the annual average daily traffic (AADT), the percentage of heavy vehicles on the highway, number of lanes, number of intersections and average speed; the implementation of these incentives has a positive influence on the reduction of accidents and injuries. Consequently, this measure seems to be an effective way of improving safety performance in road networks.

  7. Extending the application range of a fuel performance code from normal operating to design basis accident conditions

    Van Uffelen, P.; Győri, C.; Schubert, A.; van de Laar, J.; Hózer, Z.; Spykman, G.


    Two types of fuel performance codes are generally being applied, corresponding to the normal operating conditions and the design basis accident conditions, respectively. In order to simplify the code management and the interface between the codes, and to take advantage of the hardware progress it is favourable to generate a code that can cope with both conditions. In the first part of the present paper, we discuss the needs for creating such a code. The second part of the paper describes an example of model developments carried out by various members of the TRANSURANUS user group for coping with a loss of coolant accident (LOCA). In the third part, the validation of the extended fuel performance code is presented for LOCA conditions, whereas the last section summarises the present status and indicates needs for further developments to enable the code to deal with reactivity initiated accident (RIA) events.

  8. Vessel traffic safety in busy waterways: A case study of accidents in western shenzhen port.

    Mou, J M; Chen, P F; He, Y X; Yip, Tsz Leung; Li, W H; Tang, J; Zhang, H Z


    Throughout the world, busy waterways near large ports witness heavy vessel traffic in recent decades. The waterways are characterized by high risk in terms of loss of life, property, and pollution to environment. To facilitate maritime safety management with satisfactory efficiency and efficacy, the authors propose a framework of safety indexes to evaluate the risk level in busy waterways according to the accident severity, fatality rate and special indicators of maritime transportation. The safety indexes consist of Safety Evaluation Index (SEI) and Safety Warning Index (SWI), and are derived from the proposed risk criteria of Chinese vessel traffic. As a case study, data on vessel traffic accidents reported in the Western Shenzhen Port, South China from 1995 to 2015 are analyzed. The actual risk level of this area during the period is calculated under the framework. The implementation of the safety indexes indicate that the risk criteria and safety indexes are practicable and effective for the vessel traffic management. The methodology based on long-term accident data can significantly support the risk analysis in the macroscopic perspective for busy ports and waterways, such that SWI can act as threshold to trigger actions, while SEI can act as an indicator to measure safety status.

  9. The Fukushima Dai-ichi accident: additional lessons from a radiological emergency assistance mission.

    Becker, Steven M


    In response to the March 2011 earthquake-tsunami disaster and the Fukushima Dai-ichi nuclear accident, a special nongovernmental Radiological Emergency Assistance Mission flew to Japan from the United States. Invited by one of Japan's largest hospital and healthcare groups and facilitated by a New York-based international disaster relief organization, the mission included an emergency physician, a health physicist, and a disaster management specialist. During the 10 d mission, team members conducted fieldwork in areas affected by the earthquake, tsunami, and nuclear accident; went to cities and towns in the 20-30 km Emergency Evacuation Preparation Zone around the damaged nuclear plant; visited other communities affected by the nuclear accident; went to evacuation shelters; met with mayors and other local officials; met with central government officials; exchanged observations, experiences, and information with Japanese medical, emergency response, and disaster management colleagues; and provided radiological information and training to more than 1,100 Japanese hospital and healthcare personnel and first responders. The mission produced many insights with potential relevance for radiological/nuclear emergency preparedness and response. The first "lessons learned" were published in December 2011. Since that time, additional broad insights from the mission and mission followup have been identified. Five of these new lessons, which focus primarily on community impacts and responses and public communication issues, are presented and discussed in this article.

  10. 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


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

  11. Long-Term Station Blackout Accident Analyses of a PWR with RELAP5/MOD3.3

    Andrej Prošek


    Full Text Available Stress tests performed in Europe after accident at Fukushima Daiichi also required evaluation of the consequences of loss of safety functions due to station blackout (SBO. Long-term SBO in a pressurized water reactor (PWR leads to severe accident sequences, assuming that existing plant means (systems, equipment, and procedures are used for accident mitigation. Therefore the main objective was to study the accident management strategies for SBO scenarios (with different reactor coolant pumps (RCPs leaks assumed to delay the time before core uncovers and significantly heats up. The most important strategies assumed were primary side depressurization and additional makeup water to reactor coolant system (RCS. For simulations of long term SBO scenarios, including early stages of severe accident sequences, the best estimate RELAP5/MOD3.3 and the verified input model of Krško two-loop PWR were used. The results suggest that for the expected magnitude of RCPs seal leak, the core uncovery during the first seven days could be prevented by using the turbine-driven auxiliary feedwater pump and manually depressurizing the RCS through the secondary side. For larger RCPs seal leaks, in general this is not the case. Nevertheless, the core uncovery can be significantly delayed by increasing RCS depressurization.

  12. Current research and development activities on fission products and hydrogen risk after the accident at Fukushima Daiichi nuclear power station

    Nishimura, Takeshi; Hoshi, Harutaka; Hotta, Akitoshi [Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority, Tokyo (Japan)


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

  13. Physical reconstruction of the radiological accident of Chilca (Lima - Peru); Reconstruccion fisica del accidente radiologico de Chilca (Lima - Peru)

    Lachos, A. [Instituto Nacional de Enfermedades Neoplasicas, Departamento de Radioterapia, Av. Angamos Este 2520, Surquillo, Lima (Peru); Marquez, J. F., E-mail: [Univesidad Nacional Mayor de San Marcos, Facultad de Ciencias Fisicas, C. German Amezaga 375, Ciudad Univesitaria, Lima (Peru)


    The radiological accident happened in the Chilca District, the Canete County at 60 km to the south of Lima-Peru, during the night of January 11 to 12, 2012. The physical reconstruction of the accident was carried out in January 21, 2012, by means of the information gathering administrative and technical of the radioactive source as well as of the installation, the personnel and the involved procedures in the accidental event, information of the space geometry where the event took place. The preliminary information indicates that the source could have been locked in the guide tube of the equipment, next to the collimator in the first takes radiographic. The radiation monitors were not activated on the procedure, impeding this way, not to realize the flaw and causing that the personnel were exposed to the radiation during the whole work period. Their hands and especially their fingers would have been only to some millimeters of the source. With the obtained information and the measurements of the exposure rates of the radioactive source, was carried out the dose calculation to total body, the dose received in the hands and the dose received in the index finger of the left hand. The accident happened by operative procedure breach, by lack of training of the operators. The physical reconstruction of the accident contributes fundamental information for the decisions taking in the medical management of the accidents by radiation. (author)

  14. On the conception of accident and injury prevention in the coal industry of Ukraine

    Yaschenko, I.A.; Bryukhanov, A.M.; Lyovkin, N.B. [Ministry of Fuel and Energy of Ukraine (Ukraine)


    In the coal industry of Ukraine there are 160 operating - state, joint-stock and private - mines producing 80 million tons of coal a year, with 400,000 persons working, including about 200,000 underground. Accident/injury level at mines still remains high owing to difficult mining and geological conditions, low comprehensive mechanization of hard and injury-causing work processes, deficiency of emergency protection systems, considerable turnover of personnel, insufficient qualification and low labour discipline, underestimation of hazards by many workers and management. The conception reflecting ways and methods of achieving the planned goals is developed by the Ministry of Fuel and Energy of Ukraine together with MakNII to seriously improve labour protection, completely prevent disasters, and considerably decrease injuries and occupational diseases at mines. Implementation of the Conception will allow to considerably decrease accident and injury rates at the coal mines of Ukraine. 12 refs.

  15. Impact of the Fukushima accident on marine biota, five years later.

    Vives I Batlle, Jordi


    In a previous commentary written in 2011 in the aftermath of the Fukushima accident in Japan, I summarized what was then understood about the effects of accidental radioactive discharges to marine life and forecasted into the future how the marine environment would likely be affected. Since that time, several studies have been conducted on the impact of the accident on marine organisms, and radiation doses arising thereof. I developed a dynamic transfer model for studying the bioaccumulation of Fukushima radionuclides in marine biota and assessed the impact and likelihood of effects to marine life. In the present article, I highlight the lessons learned over the past 5 years. I address whether the environmental consequences in the marine environment are as significant as initially feared and, with respect to the current situation, what remains to be investigated as the radioactivity continues to spread in the marine environment. Integr Environ Assess Manag 2016;12:654-658. © 2016 SETAC.

  16. Porosity effects during a severe accident

    Cazares R, R. I. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Posgrado en Energia y Medio Ambiente, San Rafael Atlixco 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico); Espinosa P, G.; Vazquez R, A., E-mail: [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, San Rafael Atlixco 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico)


    The aim of this work is to study the behaviour of porosity effects on the temporal evolution of the distributions of hydrogen concentration and temperature profiles in a fuel assembly where a stream of steam is flowing. The analysis considers the fuel element without mitigation effects. The mass transfer phenomenon considers that the hydrogen generated diffuses in the steam by convection and diffusion. Oxidation of the cladding, rods and other components in the core constructed in zirconium base alloy by steam is a critical issue in LWR accident producing severe core damage. The oxygen consumed by the zirconium is supplied by the up flow of steam from the water pool below the uncovered core, supplemented in the case of PWR by gas recirculation from the cooler outer regions of the core to hotter zones. Fuel rod cladding oxidation is then one of the key phenomena influencing the core behavior under high-temperature accident conditions. The chemical reaction of oxidation is highly exothermic, which determines the hydrogen rate generation and the cladding brittleness and degradation. The heat transfer process in the fuel assembly is considered with a reduced order model. The Boussinesq approximation was applied in the momentum equations for multicomponent flow analysis that considers natural convection due to buoyancy forces, which is related with thermal and hydrogen concentration effects. The numerical simulation was carried out in an averaging channel that represents a core reactor with the fuel rod with its gap and cladding and cooling steam of a BWR. (Author)

  17. MELCOR modeling of Fukushima unit 2 accident

    Sevon, Tuomo [VTT Technical Research Centre of Finland, Espoo (Finland)


    A MELCOR model of the Fukushima Daiichi unit 2 accident was created in order to get a better understanding of the event and to improve severe accident modeling methods. The measured pressure and water level could be reproduced relatively well with the calculation. This required adjusting the RCIC system flow rates and containment leak area so that a good match to the measurements is achieved. Modeling of gradual flooding of the torus room with water that originated from the tsunami was necessary for a satisfactory reproduction of the measured containment pressure. The reactor lower head did not fail in this calculation, and all the fuel remained in the RPV. 13 % of the fuel was relocated from the core area, and all the fuel rods lost their integrity, releasing at least some volatile radionuclides. According to the calculation, about 90 % of noble gas inventory and about 0.08 % of cesium inventory was released to the environment. The release started 78 h after the earthquake, and a second release peak came at 90 h. Uncertainties in the calculation are very large because there is scarce public data available about the Fukushima power plant and because it is not yet possible to inspect the status of the reactor and the containment. Uncertainty in the calculated cesium release is larger than factor of ten.

  18. Advanced sodium fast reactor accident source terms :

    Powers, Dana Auburn; Clement, Bernard; Denning, Richard; Ohno, Shuji; Zeyen, Roland


    An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic event Energetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolant Entrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached cladding Rates of radionuclide leaching from fuel by liquid sodium Surface enrichment of sodium pools by dissolved and suspended radionuclides Thermal decomposition of sodium iodide in the containment atmosphere Reactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

  19. Road Traffic Accidents: A Wild Life Exterminator

    Hadiseh Kavandi


    Full Text Available Once commonly traced in various parts of Southwest Asia, the Iranian cheetah (Acinonyx jubatus venaticus, a disparagingly endangered cheetah subspecies, seems to have been driven to extinction. Restricted to its only remained appropriate habitat, The Iranian cheetah has barely survived in Iran's Dasht-e Kavir plateau. Throughout the 1970s, about 200 cheetahs were estimated to live in seven protected areas in Iran (1. Nevertheless, the figures dramatically declined to 50 and 60 individuals in 2005–2006. Over ten years, Iranian researchers captured images of 76 individual cheetahs using 80 camera traps implanted throughout the Dasht-e Kavir plateau (2. Disappointingly in 2011, camera traps captured only 20 individuals in the protected areas (2, 3. What adds insult to the injury is knowing the fact that two-thirds of cheetah deaths in 2012–2013 were due to road accidents(4.      Beside the human fatalities and injuries, road traffic accidents remain as serious threats for wildlife. Although numerous measures are taken to hinder the extinction of this subspecies, efforts should be concentrated on long-term planning at both national and international levels to raise awareness and promote willingness to address this ongoing yet controllable damage.

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

    Budu Andrei Razvan


    accident progression consequences up to a certain point. The code assesses the fuel bundle damage progression, but cannot assess further core damage for a CANDU type core, and starting from these data the amount of damaged fuel can be calculated. The radio nuclei present in the damaged fuel are supposed to be released into the main heat transport system and after that into the containment building in the worst case scenario. Assessing the radioactive nuclei maximum release is the purpose of the present paper. The radioactive nuclei release is needed for the accident management plan, limiting the environmental and population impact of the supposed accident, and furthermore for a later site remediation plan that can be put in action after the complete mitigation of the accident consequences. The maximum quantity of radio nuclei released during the accident calculated in this paper is a worst case scenario evaluation that can lead to better preparedness in an accident scenario.

  1. Occupational accidents with mowing machines in Austrian agriculture

    Robert Kogler


    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.

  2. The reactor accident in Fukushima Daiichi. The consequence of design deficiencies and inadequate safety engineering; Der Reaktorunfall in Fukushima Daiichi. Folge fehlerhafter Auslegung und unzureichender Sicherheitstechnik



    The reactor accident in Fukushima Daiichi is discussed in the frame of design deficiencies and inadequate safety engineering. The progress of the accident as consequence of the earthquake and the tsunami is described. The radiological situation for the public is supposed to be blow the dose limit of 20 mSv/year. The WHO and UNSCEAR (United Nations Scientific Committee on the Effects of Atomic radiation) did not observe acute radiation injuries. The Japanese authorities have classified the accident to 7 of the INES scale. The German Atomforum e.V. considers the safety engineering of German NPPs to be superior to the Japanese situation due to higher emergency energy supply, extensive measures to reduce the hydrogen accumulation and mitigating measures for the accident management. German NPPS are considered highly robust as the EU stress tests have shown.

  3. The effects of motor vehicle accidents on careers and the work performance of victims

    Johanna C. Diedericks


    Full Text Available Orientation: Research into the long-term effects of motor accidents on the work performance and careers of victims in South Africa is limited. Results of this research are important for employers who must assist the employees after they return to work.Research purpose: The purpose of this study was to contribute to research on the effects of the injuries by investigating the relationship between the severity of the injuries and the careers and growth potential of victims.Motivation for the study: Employers could use the information on the effects of the injuries on the careers of victims to plan interventions and job accommodations to retain employees and to manage their well-being and performance.Research design, approach and method: The author conducted a quantitative survey on a purposive sample (N = 199 of adult victims of motor vehicle accidents in 2010 in South Africa. She used descriptive and inferential statistics to analyse the data.Main findings: The author observed a number of significant relationships between the effects of the different injuries on the careers and growth potential of victims.Practical/managerial implications: Organisations and managers need to recognise the physical and psychological effects of injuries victims sustain in motor accidents and the associated responsibility of organisations to accommodate these employees.Contribution/value-add: The findings of the study can add to the literature and provide insights into the consequences of the injuries. They also provide information that can assist organisations to create an awareness of job accommodation and employee wellness of accident victims.

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

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


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

  5. MELCOR simulation of postulated severe accidents in OPR1000

    Lee, Seongn Yeon; Kim Sung Joong [Hanyang Univ., Seoul (Korea, Republic of); Kim, Hwan Yeol; Park, Jong Hwa [KAERI, Daejeon (Korea, Republic of)


    Since the Fukushima accident in 2011, severe accidents of a nuclear power plant have been a target of big debate whether the defense in depth philosophy applied to current nuclear system is still vigorous enough to ensure the protection of the operators and the public. Thus an accurate prediction of severe accident has become a critical task for the nuclear engineers with reliable employment of Probabilistic Risk Analysis (PRA). According to a recent PRA result, Small Break Loss Of Coolant Accident (SBLOCA) without safety injection and Station Black Out (SBO) show high probability of proceeding to severe accidents. Thus, these accident scenarios need to be evaluated properly with reliable prediction tools. Song and Ahn analyzed SBO sequences in KSNP using MELCOR 1.8.5. Park and Song examined SBLOCA scenarios based on the PSA of KNSP using MAAP 4.06. Their studies utilized severe accident database. In continuation of the further analysis, several scenarios of postulated SBO and SBLOCA in OPR1000 are investigated using the severe accident database and MELCOR 1.8.6.

  6. Accident rates for heavy truck-tractors in Michigan.

    Blower, D; Campbell, K L; Green, P E


    Accident rates of heavy truck-tractors are modelled using log-linear methods. The accident data used are a census of truck-tractor involvements in Michigan from May 1987 to April 1988. Travel data used to calculate the rates were produced by a survey of truck-tractors in Michigan covering the same time period. Both the accident and travel data were limited to Michigan-registered tractors operating in Michigan. Log-linear models of casualty and property-damage-only accident rates were developed using number of trailers, road type, area type, and time of day as predictor variables. Overall, differences between tractors with one and two trailers were not significant. Tractors with no trailers (bobtails) have significantly higher accident rates. Characteristics of the operating environment were found to have larger effects on the accident rate than tractor configuration (except for the bobtail). Rates varied by a factor of up to 6.8, depending on the road type. Casualty accident risk at night was 1.4 times the risk during the day. The risk of a casualty accident in rural areas was 1.6 times that of urban areas.

  7. Canister storage building design basis accident analysis documentation



    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  8. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    PIEPHO, M.G.


    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  9. 50 CFR 401.17 - Safety and accident prevention.


    ... 50 Wildlife and Fisheries 7 2010-10-01 2010-10-01 false Safety and accident prevention. 401.17 Section 401.17 Wildlife and Fisheries JOINT REGULATIONS (UNITED STATES FISH AND WILDLIFE SERVICE... FISHERIES CONSERVATION, DEVELOPMENT AND ENHANCEMENT § 401.17 Safety and accident prevention. In...

  10. 32 CFR 256.7 - Accident potential zone guidelines.


    ... 32 National Defense 2 2010-07-01 2010-07-01 false Accident potential zone guidelines. 256.7 Section 256.7 National Defense Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) MISCELLANEOUS AIR INSTALLATIONS COMPATIBLE USE ZONES § 256.7 Accident potential zone...

  11. Factors contributing to young moped rider accidents in Denmark

    Møller, Mette; Haustein, Sonja


    , attention error (52%) was the most frequently assigned accident factor. The majority (78%) of the accidents involved road rule breaching on the part of the moped rider. The results indicate that preventive measures should aim to eliminate violations and increase anticipatory skills among moped riders...

  12. Zagreb and Tenerife: Airline Accidents Involving Linguistic Factors

    Cookson, Simon


    The International Civil Aviation Organization (ICAO) is currently implementing a program to improve the language proficiency of pilots and air traffic controllers worldwide. In justifying the program, ICAO has cited a number of airline accidents that were at least partly caused by language factors. Two accidents cited by ICAO are analysed in this…

  13. Evaluation of Accident Frequencies at the Canister Storage Bldg (CSB)

    POWERS, T.B.


    By using simple frequency calculations and fault tree logic, an evaluation of the design basis accident frequencies at the Canister Storage Building has been performed. The following are the design basis accidents: Mechanical damage of MCO; Gaseous release from the MCO; MCO internal hydrogen deflagration; MCO external hydrogen deflagration; Thermal runaway reactions inside the MCO; and Violation of design temperature criteria.


    D. D. Selioukov


    Full Text Available The paper considers problems on better traffic safety at government, authority, engineering and driver activity levels, account of road conditions while investigating traffic accidents. The paper also provides road defects mentioned in forensic transport examinations of traffic accidents.




    At the TRRL/SWOV Workshop on Accident Analysis Methodology, heldin Amsterdam in 1988, the need to establish a methodology for the analysis of road accidents was firmly stated by all participants. Data from different countries cannot be compared because there is no agreement on research methodology,

  16. Prediction of vehicle traffic accidents using Bayesian networks

    Seyed Shamseddin Alizadeh


    Full Text Available Every year, thousands of vehicle accidents occur in Iran and result thousands of deaths, injuries and material damage in country. Various factors such as driver characteristics, road characteristics, vehicle characteristics and atmospheric conditions affect the injuries severity of these accidents. In order to reduce the number and severity of these accidents, their analysis and prediction is essential. Currently, the accidents related data are collected which can be used to predict and prevent them. New technologies have enabled humans to collect the large volume of data in continuous and regular ways. One of these methods is to use Bayesian networks. Using the literature review, in this study a new method for analysis and prediction of vehicle traffic accidents is presented. These networks can be used for classification of traffic accidents, hazardous locations of roads and factors affecting accidents severity. Using of the results of the analysis of these networks will help to reduce the number of accidents and their severity. In addition, we can use the results of this analysis for developing of safety regulations.

  17. Transport Accident Costs and the Value of Safety

    Koornstra, Matthijs; Evans, Andrew; Glansdorp, Cees;

    The publication descibes a study of costs of passenger transport accident by road, rail, air and sea. It is argued that "willingness to pay" theory should be preferred to "human capital" theory in valuations of life and limb. The total costs of passenger transport accidents in the EU is estimated...

  18. Fatal aviation accidents in Lower Saxony from 1979 to 1996.

    Ast, F W; Kernbach-Wighton, G; Kampmann, H; Koops, E; Püschel, K; Tröger, H D; Kleemann, W J


    So far no national or regional studies have been published in Germany regarding the number of fatal aviation accidents and results of autopsy findings. Therefore, we evaluated all fatal aviation accidents occurring in Lower Saxony from 1979 to 1996. A total of 96 aviation accidents occurred in this period involving 73 aeroplanes. The crashes resulted in the death of 154 people ranging in age from 19 to 68 years. The greatest number of victims in a single crash of an aircraft was (n=7). Other types of fatal accidents were crashes of aircraft and helicopter while on the ground (n=5), hot-air balloons (n=2), parachutes (n=10), hang glider accidents (n=5) and the striking of a bystander by a model airplane. Autopsies were performed on 68 of the 154 victims (44.2%), including 39 of the 73 pilots (53.4%). Some of the autopsies yielded findings relevant to the cause of the accident: gunshot wounds, the presence of alcohol or drugs in blood and preexisting diseases. Our findings emphasize the need for autopsy on all aviation accident victims, especially pilots, as this is the only reliable method to uncover all factors contributing to an accident.

  19. Risks of potential accidents of nuclear power plants in Europe

    Slaper H; Eggink GJ; Blaauboer RO


    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed

  20. Risks of potential accidents of nuclear power plants in Europe

    Slaper H; Eggink GJ; Blaauboer RO


    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed o